ML20214N266

Applicant Fifth Progress Rept.* Progress Rept Covers 870126-0430,per 860606 Board Order.Comanche Peak Review Team Listing of Published Results Repts & Other Related Documentation Encl.W/Certificate of Svc

ML20214N266
Person / Time
Site:	Comanche Peak
Issue date:	05/18/1987
From:	Eggeling W ROPES & GRAY, TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
References
CON-#287-3590 OL, NUDOCS 8706020121
Download: ML20214N266 (48)

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.1 DOCKETED Filed: May 18, 1987 UDE 17 MNr 22 PS:04 UNITED STATES OF AMERICA QF(" -

NUCLEAR REGULATORY COMMISSION #^# ' '

• before the ATOMIC SAFETY AND LICENSING BOARD

)

In the Matter of )

) Docket Nos. 50-445-OL TEXAS UTILITIES ELECTRIC ) 50-446-OL COMPANY et al. )

) (Application for an (Comanche Peak Steam Electric ) Operating License)

Station, Units 1 and 2) )

)

APPLICANTS' FIFTH PROGRESS REPORT Pursuant to the Board's " Memorandum and Order (Progress Report and Notice of Available Documents)" entered June 6, 1986, the Applicants submit herewith their fifth " Progress Report". This Progress Report covers the period January 26, 1987 through April 30, 1987.

1. CPRT Progress The Senior Review Team ("SRT") has approved and published 33 Results Reports (representing 32 issue specific Action Plans), as set forth in Attachment 1. Drafts of six additional Results Reports (Attachment 2) are under consideration by the SRT and are being finalized, while nine other issue specific Action Plans are in various steps of implementation (Attachment 3).

8706020121 870S18 "

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j The overall status of the.ISAP Results~ Reports by discipline is summarized in Attachment 4. .As this attachment shows, 15 Results Reports' -. are ~ yet to be published and the breakdown by discipline is as follows:

Number of ISAP Results Reports Discipline Yet To Be Published Electrical 0 Civil / Structural 4 Testing 2 Mechanical 2 QA/QC 7 It should be noted that the completed and published ISAP

'Results Reports cover all nine of the electrical action plans, six

- of the eic-ht testing action plans, five of the seven mechanical action plans, and ten of the eighteen QA/QC action plans.

The notice to CASE of the availability of the Working Files for all of the' published Results Reports has been made. Responses to the Board's 14 questions have been provided for all but 10 of these Results Reports and preparation of responses to the Board's 14 questions for these 10 Results Reports is in process.

During the period since the last Progress Report, the physical inspections and document reviews under Action Plan VII.c were completed and significant progress has been made toward the compilation of the data produced thereby. Once this process has been completed, the collective evaluation process for CPRT Program J

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Plan, Appendix.B will begin. The process, however, will not be completed until (i) all of the constituent issue-specific Action Plans have been completed and (ii) at . least some of the CPRT overview of Project actions in response to corrective action recommendations has been accomplished. The SRT has determined that the Action Plan VII.c Results Report and QOC Collective Evaluation ~ Report will be completed and published at the same time.

Apart from VII.c, fourteen Action Plans . remain to be completed and Results Reports published therefor. All of these

'. Results Reports are expected to be completed (completed, with t

respect to an action plan, refers to the approval of the Results-Report by the SRT) within the third. quarter of 1987; however, as i

noted in prior Progress Reports, the CPRT does not work to a project schedule in the normal sense in which the term is used.

I Applicants are in the process of preparing a revision to the i

CPRT Program Plan, and expect now to issue this revision by the end of May 1987. .The changes'to the Plan from Revision 3 will not change the intent or scope of the CPRT Program in any substantive way, though they will address the elimination, in order.to achieve a higher degree of efficiency in overall program implementation, I of activities that have become redundant, including activities '

that have become redundant as a result of TU Electric moving forward to Corrective Action Program activities. The revision will l

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also describe why continuing certain aspects of the investigative phase of the Design Adequacy Program will not be necessary in order to meet the reasonable assurance statement required of the Senior Review Team (SRT), because, the comprehensive Corrective Action Program launched by TU Electric in response to DAP findings will result in essentially a 100% design validation of safety-related systems, structures and components for CPSES (certain specific design areas, such as NSSS and other vendor design areas are not within the scope of this program).

DSAP Results Reports for DSAP VIII, Civil / Structural will cover cable tray supports, conduit supports, Train A and B conduit and Train C conduit greater than two inches. The Results Report for DSAP IX, Piping and Supports will cover only large bore pipe supports. Because of the TU Electric commitment to review and validate essentially 100 percent of the safety-related design of Comanche Peak Steam Electric Station, CPRT Results Reports for DSAP X, Mechanical Systems and Components, and DSAP XI, Elect r i--

cal /I&C Systems and Components will not be published. For this same reason, there are no plans to summarize the DSAP program in a Design Adequacy Collective Evaluation Report. The CPRT program will be summarized in two callective reports - The Quality of Construction (QOC) Collective Evaluation Report and the Collective Significance Report. It is expected that applicable DSAP Results Reports and the QOC Collective Evaluation Report will be published in the third quarter of 1987, and the CPRT Collective Significance

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s-Report will be published during the fourth quarter of 1987.

In the telephonic pre-hearing conference of March 9, 1987, the Board requested that the Applicants describe the relationship between the Design Adequacy Program (DAP) and the Design Basis Consolidation Program (DBCP), or more specifically, to describe the effect of the DBCP upon the DAP. By way of explanation, the CPRT DAP consists of two parts (i) the investigation of design on a sampling basis, and (ii) the correction of discrepancies. The investigation of design is the responsibility of the CPRT Third Party under direction from the SRT. (This part of the CPRT DAP has essentially been completed.) The correction of discrepancies is the responsibility of TU Electric under the Corrective Action Program (CAP). The CAP is the TU Electric program, which serves, among other things, as the corrective action response vehicle for

.t all DAP findings; in other words, theCh,Pisthemeansbywhich x.

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TU Electric is implementing correctivejactions required to address the findings of the DAP investigations, as well as other results from the essentially 100% design validation of safety-related systems, structures and components. The Design Basis Consoli-dation Program (DBCP) is that part of the Corrective Action Program which provides a consistant basis for implementation of the CAP and management of the various Architect / Engineers.

In answer to the question concerning the effect of the DBCP on the DAP, the DBCP has no effect on the DAP per se. The global nature of the design validation to be accomplished by the CAP, t

however, has affected the DAP, i.e., given the fact that the CAP will result in an essentially 100% validation of the safety-related design of CPSES, completion of certain parts of the sampling-based DAP has become redundant and unnecessary.

TU Electric has received the May 12, 1987, letter from the NRC to Mr. W. G. Counsil (a copy of which is attached) requesting additional information in conjunction with the CPSES program plan update. The information contained in the upcoming program plan revision, as well as TU Electric's response to the NRC's request for additional information, should provide to the Board and other parties a more complete description of the program being conducted at CPSES.

2. Corrective Action Program The following Generic Issues Reports were issued between January 26, 1987 and April 25, 1987:

Evaluation and Resolution of Generic Issues Report for Cable Tray Hangers, Rev. 1 and Rev. 2 Mechanical Generic Issues Report The status of Generic Issue Reports is summarized on Attachment 5.

3. Other Activities During the reporting period, the Applicants had two tran-scribed public meetings with the newly assigned NRC personnel to explain the CPRT Program and to provide a project status update.

Applicants also met with the Intervenors and CYGNA to explain the resolution of technical issues. These transcribed meetings were held in February, March and April.

As noted in prior Progress Reports, the foregoing information is provided with certain caveats. The schedules identified are not the sort of firm schedules the Board may have had in mind when it issued its memorandum; such schedules do not exist and will not be created for the CPRT Program. Some of these dates may slip for a number of reasons including some conscious decisions.

The next Progress Report will be issued June 30, 1987.

Respectfully submitted, TEXAS UTILITIES ELECTRIC COMPANY For the Owners of CPSES K

TT Thomas G. Digna[ Jr./

R. K. Gad III (

William S. Egge ing Kathryn A. Selleck ROPES & GRAY 225 Franklin Street Boston, MA 02110 (617) 423-6100 Attorneys for Texas Utilities Electric Company l

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ATTACliMENT 1 CPRT RESULTS REPORTS PUBLISIIED

1. a. 1 IIEAT-SIIRINKABLE CABLE INSULATION SLEEVES I. a. 2 INSPECTION REPORTS ON BUTT SPLICES I. a. 3 BUTT-SPLICE QUALIFICATION I. a. 4 AGREEMENT BETWEEN DRAWINGS AND FIELD TERMINATIONS (Published twice)

I. a. 5 NCRs ON VENDOR INSTALLED AMP TERMINAL LUGS I. b. 1 FLEXIBLE CONDUIT TO FLEXIBLE CONDUIT SEPARATION I. b. 2 FLEXIBLE CONDUIT TO CABLE SEPARATION I. b. 3 CCNDUIT TO CABLE TRAY SEPARATION I. b. 4 BARRIER REMOVAL

1. d. 2 GUIDELINES - QC INSPECTOR TEST '

I. d. 3 CRAFT PERSONNEL TRAINING II. b CONCRETE COMPRESSION STRENGTl!

II. c MAINTENANCE OF AIR GAP BETWEEN CONCRETE STRUCTURES III. a. 2 JTG APPROVAL OF TEST DATA III. a. 3 TECilNICAL SPECIFICATION FOR DEFERRED TESTS III. a. 4 TRACEABILITY OF TEST EQUIPMENT III. a. 5 PREOPERATIONAL TEST REVIEW AND APPROVAL OF RESULTS III. b CONDUCT OF TIIE CLIRT III. d PREOPERATIONAL TESTING IV. PROTECTIVE COATINGS

• V. a INSPECTION FOR CERTAIN TYPES OF SKEWED WELDS IN NF SUPPORTS V. c DESIGN CONSIDERATION FOR PIPING SYSTEMS BETWEEN SEISMIC AND NON-SEISMIC CAT. ONE BUILDINGS V. d PLUG WELDS V. e INSTALLATION OF MAIN STEAM PIPES VI. a GAP BETWEEN REACTOR PRESSURE VESSEL REFLECTIVE INSULATION AND TiiE BIOLOGICAL SilIELD WALL VII. a. 3 DOCUMENT CONTROL VII. a. 4 AUDIT PROGRAM AND AUDITOR QUALIFICATIONS VII. a. 5 PERIODIC REVIEW OF QA PROGRAM VII. a. 6 EXIT INTERVIEWS VII. a. 7 IIOUSEKEEPING AND SYSTEM CLEANLINESS VII. a. 8 FUEL POOL LINER DOCUMENTATION VII. b. 1 ON-SITE FABRICATION

.VII. b. 2 VALVE DISASSEMBLY ,

VII. b. 5 ELECTRICAL RACEWAY SUPPORTS DELETED. ,

1 TIIROUGli April 30, 1987 L

ATTACHMENT 2 CPRT RESULTS REPORTS UNDER CONSIDERATION BY THE SRT I. d. 1 QC INSPECTOR QUALIFICATIONS VII. a. 1 MATERIAL TRACEABILITY VII. a. 2 NONCONFORMANCE AND CORRECTIVE ACTION SYSTEM VII. b. 3 PIPE SUPPORT INSPECTIONS VII. b. 4 IIILTI ANCilOR BOLT INSTALLATION VII. c CONSTRUCTION REINSPECTION / DOCUMENTATION REVIEW PLAN 1 TilROUGil April 30, 1987

F l ATTACilMENT 3 l

CPRT ACTION PLANS IN IMPLEMENTATION I. c ELECTRICAL CONDUIT SUPPORTS II. a REINFORCING STEEL IN Tile REACTOR CAVITY II. d SEISMIC DESIGN OF CONTROL ROOM CEILING ELEMENTS II. e REBAR IN Tile FUEL IIANDLING BUILDING III. a. 1 IlOT FUNCTIONAL TESTING ( IIFT ) DATA PACKAGES III. c PREREQUISITE TESTING V. b IMPROPER SIIORTENING OF ANCIIOR BOLTS IN STEAM GENERATOR UPPER LATERAL SUPPORTS VI. b POLAR CRANE SIIIMMING VII. a. 9 RECEIPT AND STORAGE OF PURCilASE MATERIAL AND EQUIPMENT RECEIVING INSPECTION 1 T!!ROUGli April 30, 1987

ATTACilMENT 4 ISAP RESULTS REPORT STATUS

SUMMARY

l NUMBER NUMBER NUMBER OF l APPROVED UNDER ACTION PLANS l TOTAL NUMBER NUMBER BY SRT AND CONSIDERATION IN DISCIPLINE OF ISAPS DELETED PUBLISilED BY SRT IMPLEMENTATION 1

ELECTRICAL 9 0 9 0 0 CIVIL / STRUCTURAL 6 0 2 0 4 TESTING 8 0 6 0 2 PROTECTIVE COATINGS 1 1 N/A N/A N/A MECIIANICAL 7 0 5 0 2 QA/OC 18 1 10 6 1 49 2 32 6 9 1 Ti!ROUGII April 30, 1987 l

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1 ATTACHMENT 5 ,

GENERIC ISSUE REPORTS STATUS Corrective Action Program Revision Number & Issue Date Large Bore Piping RO 06/27/86 Small Bore Piping RO 12/05/86 Conduit Supports R2 03/30/87 Train A, B, C > 2" Conduit Supports RO 10/16/86 Train C < 2" Cable Tray liangers R2 03/18/87 IIVAC RO 12/15/86 Equipment Qualification RO 12/29/86 Mechanical Systems RO 01/26/87 Electrical RO 12/17/86 Iristrument and Control RO 01/05/87 Civil / Structural RO 12/18/86

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UNITED STATES

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8 n NUCLEAR REGULATORY COMMISSION h WASHINGTON, D. C. 20556

.o May 12, 1987 Docket Nos. 50-445 and 50-446-Ob Mr. William G. Counsil Executive Vice President Texas Utilities Electric Company Skyway Tower, L.B. 81 400 North Olive Street Dallas, Texas 75201

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION IN CONJUNCTION WITH PROGRAM PLAN UPDATE Durina our last manaaement meetina on April 7,1987, representatives from Texas Utilities Electric Company (TUEC) described your intention to prepare and submit Revision 4 to the Comanche Peak Response Team (CPRT) Procram Plan.

That revision would update the Plan to reflect the results of your investiaation thus far into the desian adequacy and quality of construction, TUEC manacement decisions for corrective actions, and other chances to proarams that make up or are related to the Plan which have evolved since the staff's evaluation in Supplement 13 to NUREG-0797 (SSER 13).

Althouah the staff recoanizes the need to update the Plan at this time so that it will more accurately reflect evolvino results and other related activities (i.e. a "livina" proaram), we have identified the need for you to develop a more comprehensive plan that identifies all of the activities required to sup-port licensina, and the relationships between those activities. Toward that end, we have identified certain information and explanations, outlined below, that the staff needs to clearly understand the present and future course of your efforts. I am aware that this request is beina made late in the process.

However, I believe this course of action is necessary to facilitate the iden-tification and resolution of issues without further delay. Your response to the questions should distinauish between what we consider to be three distinct phases of your activities: (1) investiaation, (2) corrective actions and (3) verification or overview.

You should provide the followina information and clarifications:

1. Provide a concise description of the present scope, purpose, and objectives of the Desian Adequacy Proaram (DAP) and the Quality of Construction and QA/QC Adequacy Proaram (QOC).

RECEIVED i'AY 151937 c,r_uAiA G. COUNSiL

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Mr. William G. Counsil Y '2 . Provide a concise description of the scope, purpose, and objectives of the Correction Action Procrams (CAPS), the Desian Basis Consolidation i Proaram (DBCP), and any other major onaoing proarams necessary for the licensina of Comanche Peak.

3. Where the purposes of the procrams described in your response to Items 1 and 2 above are similar, clearly describe the differences and interrelationships between these proarams. Include in your response a diaoram showina the functional and timina relationships between each of the programs. For clarity, it may be necessary to provide a series of diaorams showing the programs in increasing levels

.of detail. With respect to the relationship between DBCP and DAP, specifically address the interface between these proarams in each of the phases: (1) investication, (2) corrective actions, and (3) veri- '

fication or overview.

4. Clarify the present role of the " safety sionificance evaluations" and the identification of " critical desian parameters" with respect to your redesian and construction verification efforts.

Explain the oraanizational controls you apply to ensure that these screening processes do not overly constrain the scope of the corrective actions required.

5. Identify the documentation that will be produced for each of the activities described in your response to Items 1 and 2. Specify whether the documents will be submitted on the docket or filed at the site. It should be recoanized that we will docket any information, not otherwise so submitted, that the staff relies on for conclusions in its safety evaluations.

i 6. Identify the as-built verifications and/or walkdowns that have been or will be conducted for each proaram. Indicate which of

. those verifications will be relied on for the " final" desian.

Inasmuch as future design chances may be undertaken for a variety of reasons, you should define " final" design with respect to the CPRT efforts.

. 7. Explain how the TUEC Technical Audit Proaram SWEC Enaineerino

l. Functional Evaluations, SWEC Enaineerina Assurance Procram, TERA .

, evaluations CYGNA Independent Assessment Proaram, and vendor / '

, contractor QA/QC procrams relate to the overall QA/QC procram for

! Comanche Peak. Identify which of these verification methods will i apply to each procram. It appears that the evolution of these verification methods have resulted in a QA/QC procram that is I different from that currently described in the FSAR and possibly l different from that evaluated in SSER 13. Therefore, you should:  !

- (1) describe the present QA/QC proaram for Comanche Peak, (2)iden- l 4

tify differences between the present proaram, the proaram described )

in the FSAR, and the proaram evaluated in SSER 13, and (3) indicate 1 the schedule by which you will update the FSAR to reflect the QA/QC l procram for future reference. In addition, explain how QA/QC has been applied to the CPRT activities over time, particularly for work

performed prior to Revision 3 of the Plan.

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Mr. William G. Counsil l l

8. In SSER 13, the staff noted that the desian activities and, by implication, the quality proarams of certain " proven" vendors may be exempt from a desian adequacy evaluation; for example, the vendor for the nuclear steam supply system. Please identify other vendors that you believe would fall into this catecory, in that you feel that l' their design and QA/QC procrams had substantial credibility prior to Revision 3.

9. Please explain what the role and purpose of the Senior Review Team (SRT) will be in the future. We believe that this role should be explained particularly with reaard to the transition from the CPRT I to TUEC responsibility for implementina the Plan. '

10. With respect to the CYGNA Independent Assessment Proaram, the stsff notes that recent Phase IV activities appear to have value as an adjunct to the Technical Audit Program. Please indicate the extent to which the CYGNA evaluation will or can apply to any of the proarams described in your response to Items 1 and 2.

11. Durina the April 7,1987 meetina, you provided listinas of "licensina open items" other than those included as part of CPRT and related activities. We request that you provide the status of the resolution of those issues. The status should include identification of those issues that will require plant modifications, interfaces with CPRT activities (i.e., dependencies), and projections for future FSAR amendments.

We intend to use all of the information you provide to develop a comprehensive review and inspection procram for Comanche Peak licensina activities. Further, we intend to review this information to determine whether to request that you make chanaes or additions to your planned activities. Once we approve this broader Plan, we will require that any chanaes to this Plan be submitted to the staff before they are implemented to ensure the most efficient use of our respective resources. Should you have any questions reaardina this request, please contact me.

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Christopher I. G mes, Director Comanche Pest Aroject Division Office of ipec al Projects cc: See next pace

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W. G. Counsil Comanche Peak Steam Electric Station Texas Utilities Generating Company Units 1 and 2 cc:

Thomas G. Dignan, Jr. NRC Resident Inspector Ropes & Gray Comanche Peak Steam Electric Station 225 Franklin Street c/o-U.S. Nuclear Reaulatory Commission i Boston, Massachusetts 02110 P. 0.~ Box 38 Glen Rose Texas 76043 Robert A. Wooldridae, Esq. Reaional Administrator, Region IV.

Worsham, Forsythe, Sampels & U.S. Nuclear Reaulatory Commission Wooldridae - 611 Ryan Plaza Drive, Suite 1000 2001 Bryan Tower, Suite 2500 Arlington, Texas 76011 Dallas, Texas 75201 ,

i Lanny A. Sinkin Mr. Homer C. Schmidt Christic Institute Manaaer - Nuclear Services 1324 North Capitol Street Texas Utilities Generatino Company Washinaton, D.C. 20002 Skyway Tower 400 North Olive Street, L.B. 81 Ms. Billie Pirner Garde Dallas, Texas 75201 Government Accountability Project-Midwest Office  !

Mr. Robert E. Ballard, Jr. 104 E. Wisconsin Avenue l Director of Projects Appleton, WI 54915-8605 Gibbs and Hill, Inc.

11 Pen Plaza New York, New York 10001 David R. Piaott, Esq.

Orrick, Herrinaton & Sutcliffe 600 Montgomery Street Mr. R. S. Howard San Francisco, California 94111 Westinahouse Electric Corporation P. O. Box 355 Anthony Z. Roisman, Esq.

Pittsburgh, Pennsylvania 15230 Suite 600 1401 New York Avenue, NW Renea Hicks, Esq. Washinoton, D.C. 20005 Assistant Attorney General Environmental Protection Division Robert Jablon P. O. Box 12548 Capitol Station Bonnie S. Blair Austin, Texas 78711 Spieael & McDiarmid 1350 New York Avenue, NW Mrs. Juanita Ellis, President Washington, D.C. 20005-4798 Citizens-Association for Sound Eneray 1426 South Polk Dallas, Texas 75224 Ms. Nancy H. Williams CYGNA 101 California Street San Francisco, California 94111

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Texas Utilities Electric Company Comanche Peak Electric Station Units 1 and 2 cc:

NRC Resident Inspector Joseph F. Fulbriaht Comanche Peak Steam Electric Station Fulbrioht & Jaworski c/o U.S. Nuclear Regulatory Commission 1301 McKinney Street P. O. Box 1029 Houston, Texas 77010 Granbury, Texas 76048 Mr. John W. Beck Vice President Texas Utilities Generating Company Skyway Tower 400 N. Olive Street, L.B. 81 Dallas, Texas 75201 Mr. Jack Reddino c/o Qatel Service Corp.

Texas Utilities Generatina Company 7910 Woodmont Avenue, Ste. 208 4

Bethesda, Maryland 20814 William A. Burchette, Esq.

. Counsel for Tex-La Electric Cooperative of Texas Heron, Burchette, Ruckert & Rothwell Suite 700 1025 Thomas Jefferson Street, NW Washington, D.C. 20007

- James M. McGaughy GDS Associates, Inc.

2525 Cumberland Parkway Suite 450 Atlanta, Georgia 30339 Administrative Judae Peter Bloch U.S. Nuclear Reaulatory Commission Washincton, D.C. 20555 Elizabeth B. Johnson Administrative Judge Oak Ridae National Laboratory P. O. Box X, Buildina 3500 Oak Ridae, Tennessee 37830 Dr. Kenneth A. McCollom 1107 West Knapp Stillwater, Oklahoma 74075 Dr. Walter H. Jordan Administrative Judae 881 West Outer Drive Oak Ridae Tennessee 37830

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Texas Utilities Electric Company Comanche Peak (other) cc:

Mr. Paul Gosselink Attorney General's Office P. O. Box 12548,. Capitol Station Austin, Texas 78711 Bureau of Radiation Control State of Texas 1100 West 49th Street Austin, Texas 78756 Office of the Governor ATTN: Darla Parker Office of Intergovernmental Relations P. O. Box 13561 Austin, Texas 78711 Honorable Georae Crump County Judoe Glen Rose, Texas 76043 Honorable Milton Meyer County Judae Hood County Courthouse Granbury, Texas 76048 4

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ANN 0TATED BIBLIOGRAPHIES Pursuant with the Board's Order of June 6, 1986, Applicants submit the attached Annotated Bibliographies of documents for the time period of January 26, 1987 - April 25, 1987. The principals that were utilized, document sources the documents that are ~ annotated and the are consistent with the guidelines and procedures that were used by Applicants in previous Annotated Bibliographies.

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10 CFR 50.55(e)  ;

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. During the period of January 26, 1987 to April 25, 1987, Applicants issued 65 letters to the NRC concerning 54 items which had previously been identified as potentially reportable under the provisions of 10 CFR 50.55(e). The letters are catagorized as follows:

A. 25 letters - Interim Report - Evaluation to determine reportability is continuing.

(No listing provided)

8. 31 letters - Interim Report - Item determined to be reportable and evaluation / corrective action is continuing.

(See listing as follows)

Date Letter No. SDAR No. Subject 01/26/87 TXX-6227 CP-86-40 Application of Non-Qualified Agastat Relays This report was submitted to status corrective action implemented to date regarding a deficiency involving the procurement and use of non-qualified Agastat relays in several Class 1E applications.

Date letter No. SDAR No. Subject 01/26/87 TXX-6239 CP-86-62 Polar Crane Support '

Structure This report was submitted to status corrective action implemented to date regarding a deficiency involving a misinterpretation of the polar crane load cases.

Date Letter No. SDAR No. Subject 01/30/87 TXX-6248 CP-85-35 Cable Tray Hanger Design This report was submitted to status corrective action implemented to date regarding a deficiency involving the design and construction activities of the cable tray support program.

a j Date Letter No. SDAR No. Subject

-01/30/87 TXX-6249 CP-87-01 Safeguards Bullding This report was submitted regarding a deficiency involving an

. error in the finite element computer model for the Safeguards Building. Evaluation as a part of the Design Basis Consolidation Program is continuing.

Date Letter No. SDAR No. Subject 01/30/87 TXX-6251 CP-86-07 Service Water System Leakage This report was submitted tc status corrective action implemented to date regardjng a deficiency involving weld failure and coating degradation in the Service Water System. l i

Date Letter No. SDAR No. Subject 01/30/87 TXX-6254 CP-86-49 Conax Adaptor Modules This report was submitted to status corrective action implemented to date regarding a deficiency involving the effects of polar-

' organic solvents on the sealants of'Conax adaptor modules and electrical penetrations.

Date Letter No. SDAR No. Subject 02/02/87 TXX-6260 CP-86-63 Pipe Support

, Installations This support is a follow-up report on a reportable item involving pipe construction deficiencies. The requirements for the Hardware Validation Program (HVP) have been incorporated into the applicable quality inspection procedures and personnel training has been performed to assure consistency and accuracy in the implementation of this program.

, Date Letter No. SDAR No. Subject 02/06/87 TXX-6266 CP-86-11 Impeller Linear Indications This report was submitted to status corrective action regarding a deficiency involving the linear indication on impellers for the Component Cooling Water (CCW) pump.

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Date letter No. SDAR No. Subject U 02/13/87 TXX-6260 CP-86-04 Richmond Inserts to Embedded Plates and Welded Attachments This is a report of a deficiency regarding the placement of Richmond inserts in the proximity of loaded embedded plates which could compromise the structural integrity of adjacent shear cones. (Previous responses to this item have been reported under SDAR CP-86-44. The scope of SDAR CP-86-04 has been expanded to include evaluation of SDAR CP-86-44.) This report provides the required information regarding description of the problem, safety implication and corrective action.

Date letter No. SDAR No. Subject 02/20/87 TXX-6286 CP-86-53 Seismic Design of Conduit This report was submitted to status corrective action implemented to date regarding a deficiency involving the seismic design of conduit.

Date Letter No. SDAR No. Subject 02/20/87 TXX-6291 CP-86-54 Original Design of Control Room Ceiling This report was submitted to status corrective action implemented to date regarding a deficiency involving the design and installation of the control room ceiling.

Date Letter No. SDAR No. Subject 02/20/87 TXX-6296 CP-86-36 Large Bore Piping and Supports This is a follow-up report on a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program.

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Date Letter No. SDAR No. Subject 02/20/87 TXX-6297 CP-86-72 Small Bore Piping and Supports This is a follow-up report on a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program.

Date Letter No. SDAR No. Subject 02/27/87 TXX-6305 CP-85-34 Conduit Support Design This report was submitted to status corrective action implemented to date regarding a deficiency involving the adequacy of conduit supports to perform their intended design functions.

4 Date Letter No. SDAR No. Subject 03/02/87 TXX-6313 CP-86-40 Application of Non-Qualified Agastat Relays This report was submitted to status corrective action implemented to date regarding a deficiency involving the procurement and use of non-qualified Agastat relays in several Class IE applications.

(Most recent interim report was logged TXX-6227, dated January 26, 1987).

Date Letter No. SDAR No. Subject 03/06/87 TXX-6317 CP-85-19 Conduit Support Spans This report was submitted to status corrective action implemented to date regarding a deficiency involving the use of a l nonrepresentative sample in determining generic values' for typical conduit span calculations.

Date Letter No. SDAR No. Subject 03/06/87 TXX-6319 CP-85-31 Electrical Raceway l Support System This report was submitted to status corrective action implemented to date regarding a deficiency involving the Unit 1 Class 1E Electrical Raceway Support System.

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o Date Letter No. SDAR No. Subject 03/09/87 TXX-6323 CP-86-18 Safety Chilled Water Chiller Units This report was submitted to status corrective action implemented to date regarding the reportable issue involving difficulties in starting and operating the safety chilled water chiller units.

Date Letter No. SDAR No. Subject 03/19/87 TXX-6327 CP-86-67 Pre-Operational Vibrational Test Criteria This letter transmitted information regarding a deficiency involving the design calculations and tests used to qualify the Pre-Operational Piping Vibration Program. The required information as to description of the problem, safety implication and corrective action for the issue is provided.

Date Letter No. SDAR No. Subject 03/20/87 TXX-6315 CP-86-73 ASME Snubber Attachment Brackets This letter transmitted information regarding a deficiency involving installation of ASME snubber attachment brackets. The required information as to description of the problem, safety implication and corrective action is provided for this issue.

Date Letter No. SDAR No. Subject 03/20/87 TXX-6332 CP-86-19 Instrumentation Installations This report was transmitted to status corrective action implemented to date concerning a reportable item involving the installation of steam service pressure transmitters.

Date Letter No. SDAR No. Subject 03/20/87 TXX-6343 CP-86-51 Anchor Bolts Supplied by Hilti This letter transmits information regarding a deficiency involving a condition cited at another nuclear facility in which anchor bolts supplied by Hilti do not meet average ultimate tensile loads in certain sizes as published by the supplier.

Date Letter No. SDAR No. Subject 03/23/87 TXX-6335 CP-86-31 Diesel Generator Lube Oil Sump Tank Foot Valves This report was submitted to status corrective action implemented to date regarding a deficiency involving the possible failure of luberubber the oil sump facing tank.on foot valves mounted i n the diesel generator Date letter No. _SDAR No. Subject 03/23/87 TXX-6336 CP-86-64 Coatings for Unit 2 Diesel Fuel Oil Tanks This report concerns a deficiency involving the protective coatings for the Unit 2 diesel fuel storage tanks. The report identifies that assessment of NRC Information Notice 87-04 impact on this i ssue has been completed. Evaluation of this issue with regard to the safety of plant operations is continuing.

Date Letter No. _SDAR No. Subject 1

03/23/87 TXX-6346 CP-86-62 Polar Crane Support Structure This report was submitted to status corrective action implemented to date regarding a deficiency involving the misinterpretation of the polar crane load cases.

Date Letter No. SDAR No. Subject 03/26/87 TXX-6348 CP-86-07 Service Water System Leakage This report was submitted to status corrective action implemented to date regarding a deficiency involving weld failure and coating degradation in the Service Water System.

! Date Letter No. SDAR No. Subject 03/27/87 TXX-6357 CP-86-10 Electrical Penetration Assemblies This report was submitted to status corrective action implemented to date regarding a deficiency involving the electrical penetration assemblies supplied by Bunker-Ramo.

i i

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r, Date Letter No. SDAR No. Subject 03/27/87 TXX-6358 CP-86-36 Large Bore Piping and Supports This report was submitted regarding a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program.

Date Letter No. SDAR No. Subject 03/27/87 TXX-6359 CP-86-72 Small Bore Piping and Supports This report was submitted regarding a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program.

Date Letter No. SDAR No. Subject 04/03/87 TXX-6383 CP-86-82 Cable Tray Hanger Splice Welds This report was submitted to status corrective action implemented to date regarding a deficiency involving certain welds which are used to splice cable tray hangers channel sections end-to-end to 1

form posts.

• Date Letter No. SDAR No. Subject 04/16/87 TXX-6391 CP-86-63 Pipe Support Installations This report was submitted regarding a reportable item involving pipe support construction deficiencies.

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C. 5 letters - Final Report - Deficiency is not reportable.

(See listing as follows) i Date Letter No. SDAR No. _ Subject 02/18/87 TXX-6282 CP-86-66 Non-Contact Lap Splices in Auxiliary Building This is a report of a deficiency regarding vertical rebar in the Auxiliary Building that apparently does not s at i s fy the criteria of an ACI code defined lap splice. Engineering calculations and the review of applicable quality documents have been completed.

Based on these results, it is concluded that this issue is not reportable under provisions of 10 CFR 50.55(e).

Date Letter No. SDAR No. Subject 02/19/87 TXX-6287 CP-86-75 Air Actuators of PAPC0 Dampers This is a report of a deficiency involving ASCO solenoid valves in piston air actuators of PAPC0 dampers. The etylene propylene diaphrams, seals and 0-rings in these valves were replaced with units of Viton material per design changes issued on 1983 (DCA i 13243). In addition, an evaluation demonstrated that failure of these seals would not adversely affect the safety of plant operations. Therefore, this deficiency is not reportable under the provisions of 10 CFR 50.55(e).

Date Letter No. _SDAR No. Subject 03/09/87 TXX-6316 CP-87-02 Fisher Control Valves This is a report involving an evaluation of equipment supplied by Fisher Controls to assure that two anomalies identified by the vendor do not create conditions adverse to the safety of plant operations. The evaluation concluded that CPSES does not have any of these valves installed in safety related systems; therefore, the anomalies are not applicable to CPSES and not reportable per 10 CFR 50.55(e).

Date Letter No. SDAR No. Subject 03/13/87 TXX-6330 CP-86-65 Unconsolidated Concrete Unit 2 RCB Exterior Wall This is a report regarding a deficiency involving unconsolidated concrete in the exterior wall of CPSES Unit 2 Reactor Containment l

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

O Building. During an evaluation, a review of the QA documentation related to the specified area was conducted. There was no evidence of a significant breakdown in the QA program.

Additionally, an engineering analysis has concluded no condition adverse to the safety of plant operations or the structural integrity of the exterior wall would exist in the event the deficiency had remained undetected. The issue is not reportable under the provisions of 10 CFR 50.55(e).

Date Letter No. SDAR No. Subject 04/23/87 TXX-6403 CP-86-39 Cable Tray "C-Type" Clamp Shim Dimension This is a report of a deficiency involving dimensional tolerances of the shims used in conjunction with "C-Type" clamps on cable trays. An evaluation of test results has concluded that this issue is not reportable under the provisions of 10 CFR 50.55(e).

D. 4 letters - Final Report - Deficiency is reportable and corrective action taken.

( See listing as follows)

Date _ Letter No. SDAR No. Subject 02/13/87 TXX-6261 CP-86-44 Welded Attachments to Embedded Strip Plates This is a report of a deficiency involving the design / construction requirements for minimum separation of welded attachments to embedded strip plates which were not properly reflected in inspection procedures. The scope of SDAR CP-86-04,

" Proximity Placement - Richmond Inserts to Emledded Plates" has been expanded to include the deficiency identif ad in SDAR CP 44, " Welded Attachments to Embedded Strip Platet".

Date Letter No. SDAR No. Subject 02/23/87 TXX-6292 CP-86-50 Unistrut Spring Nuts on Instrument Supports This is a report of a deficiency involving nut alignment and torque requirements for Unistrut spring nuts on instrument mounts. Plans requiring rework of affected installations are being integrated with other instrumentation issues and the status of modifications will be reported via SDAR CP-86-19,

" Instrumentation Installations".

Date Letter No. SDAR No. Subject 03/16/87 TXX-6334 CP-87-03 6.9KV Switchgear Installation This letter transmits a report of a deficiency involving the installation of the safety-related 6.9KV switchgear on structural embedments which were not level. The required information as to description of the problem, safety implication and corrective action for this item is provided in the report.

Date Letter No. SDAR No. Subject 03/16/87 TXX-6341 CP-86-14 6.9KV Switchgear Breaker Jack Shaft Weld Failure

^

This letter transmits a final report of a deficiency involving a weld failure in a component of a Class IE 6.9KV switchgear breaker. The required information as to description of the problem, safety implication and corrective action for this item is provided in the report.

l RESPONSES TO NRC INSPECTION REPORTS /

4 NOTICE OF VIOLATION / NOTICE OF DEVIATION The following correspondence was issued by Applicants to'the NRC Region IV, concerning inspection reports, during the period of January 26, 1987 --April 25, 1987:

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Date Letter No. Subject

'02/02/87 TXX-6144 Response to Notice of Violation

.This letter transmitted responses to Items I and 2 of the NOV related to Inspection Report Nos. 50-445/84-32 and 50-446/84-11.

The response to Item 3 of the NOV was provided in an earlier transmittal (TXX-4453 dated 02/15/85).

Date Letter No. Subject 02/02/87 TXX-6250 Response to Notice of Violation and Notice of Deviation This letter transmitted responses to the NOV and NOD related to i Inspection Report Nos. 50-445/86-15 and 50-446/86-12. Seven (7) items were identified in the NOV to which Applicants responded.

'Five (5) items were identified in the NOD to which Applicants responded.

I

! .Date Letter No. Subject l 02/06/87 TXX-6269 Response to Notice of Violation This letter transmitted a response to the NOV related to Inspection Report Nos. 50-445/86-15 and 50-446/86-12. One item was identified in the NOV to which Applicants responded.

i Date Letter No. Subject 02/10/87 TXX-6272 Request for Information Regarding Inspection Reports

! This letter transmitted additional information, as requested, on i the following inspection reports: 50-445/85-07, 50-446/85-05; t

50-445/85-14, 50-446/85-11; 50-445/85-16, 50-446/85-13; 50-445/86-06, 50-446/86-04. Six (6) items were identified to which Applicants responded.

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

Date Letter No. Subject 02/13/87 TXX-6277 Request for Information Regarding Inspection Reports This letter transmitted additional information, as requested, regarding the following Inspection Reports: 50-445/85-07, 50-446/85-05; 50-445/85-14, 50-446/85-11; 50-445/85-16, 50-446/85-13; 50-445/86-06, 50-446/86-04. In an earlier transmittal (TXX-6272 dated 02/10/87), Applicants stated that based on discussions with the NRC staff (02/09/87), TU Electric would respond to Question 1 of NRC's letter dated 02/05/87. This letter (TXX-6277) responds to Question 1 based upon the guidance received from the NRC staff.

Date Letter No. Subject 02/18/87 TXX-6222 Response to Notice of Violation and Notice of Deviation This letter transmitted responses to the NOV and NOD related to Inspection Report Nos. 50-445/86-07 and 50-446/86-05.

items were identified in the NOV to which Applicants responded. Six(6)

Fifteen (15) items were identified in the N0D to which Applicants responded.

Date Letter No. Subject 02/20/87 TXX-6252 Clarification of Response to Notice of Violation & Notice of Deviation This letter was transmitted in regards to the NOV and N00 concerning Inspection Report Nos. 50-445/85-16 and 50-446/85-13.

This letter provided clarification of a supplemental letter that was transmitted previously in response the to NOV and N00, namely, TXX-4992 dated September 5, 1986.

Date Letter No. Subject 02/20/87 TXX-6284 Supplemental Request for Information to Notice of Violation This letter transmitted additional information, as requested, to NOV Item 2.b relating to Inspection Report Nos. 50-445/85-07 and 50-446/85-05.

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,Date _ Letter Mo. Subject 02/27/87 TXX-6262 EA No. 86-09 This letter transmitted revised responses reflecting new completion schedules and description changes for each item listed in two NOVs, designated Appendix A and Appendix B to an NRC letter dated May 2, 1986. By letters dated 08/04/86 and 08/25/86, TU Electric had provided responses to these NOVs providing information relating to corrective actions to be taken for each item listed in the NOVs, including completion schedules.

, Date Letter No. Subject 03/06/87 TXX-6306 Supplemental Response to Notice of Violation and Notice of Deviation This letter transmitted supplemental responses to the NOV Items B, C, D, E and F and to the N00 Item I.5 relating to Inspection Report Nos. 50-445/86-07 and 50-446/86-05.

,0 ate, Letter No. Subject 03/12/97 TXX-6337 Response to Notice of Deviation This letter transmitted a response to NOD Item E.2 relating to Inspection Report Nos. 50-445/86-03 and 50-446/86-02.

Date Letter No. Subject 03/27/87 TXX-6349 Clarification of Supplemental Response to Notice of Violation This letter transmitted a clarification to the supplemental response to NOV 445/8507-01 and 446/8505-01 provided on January 28, 1987 per TXX-6211.

Date Letter No. Subject 03/27/87 TXX-6366 Revised Date for Full Compliance for Notice of Violation This letter transmitted a revised date for full compliance in regard to response to NOV 445/8614-V-01 and 446/8611-V-01 (Item A).

F Date Letter No. Subject 03/27/87 TXX-6374 Response to Notice of Violation /

Deviation This letter transmitted revised dates for full compliance in regard to commitments made in TXX-6222 dated 02/18/87 in response to Inspection Report Nos. 50-445/86-07 and 50-446/86-05.

Date Letter No. Subject 04/14/87 TXX-6386 Revised Date for Full Compliance for Notice of Violation This letter transmitted revised dates for full compliance in regard to response to NOV 445/8518-V-15 (Item C) provided on July 9, 1986 per TXX-4848.

Date Letter No. Subject 04/15/87 TXX-6392 Revised Response for Notice of Violation This letter transmitted notice of a revised plan currently being /

formulated to update the corrective actions required in regard to /

response to NOV 446/8612-V-03 (Item C) provided on February 2, ,/

1987 per TXX-6250.

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CPRT/ CORRECTIVE ACTION PROGRAM The following correspondence was issued by Applicants to the NRC concerning CPRT and/or the Corrective Action Program during the time period of January 26,1987 - April 25, 1987:

Date Letter No. Subject

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01/ 2 6/',/ TXX-6237 CPRT Checklists Thi, letter transmitted revisions to be included in previously svumitted manuals which describe the use of CPRT Checklists.

Date Letter No. Subject

' 01/27/87 TXX-6242 Evaluation and Resolution of Generic Technical Issues for Cable Tray Hangers This letter transmitted copies of Evaluation and Resolution of Generic Technical Issues for Cable Tray Hangers, Revision 1, prepared by EBASCO Services Incorporated and Impell Corporation.

Date Letter No. Subject 01/29/87 TXX-6247 Corrective Action Plan This letter transmitted information, as requested, regarding the Comanche Peak Corrective Action Programs established by TV Electric.

Date Letter No. Subject 02/18/87 TXX-6183 Mechanical Generic Issues Report This letter transmitted copies of Mechanical Generic Issues Report.

Date Letter No. Subject 02/27/87 TXX-6312 CPRT Results Reports This letter transmitted copies of approved Results Reports, namely, Conduct of CILRT. Revision 0 (III.b) and Onsite Fabrication, Revision 1 (VII.b.1).

T' CYGNA The following correspondence was issued by Applicants concerning CYGNA during the time period of January 26, 1987 -

April 25, 1987:

Date Letter No. Subject 02/11/87 TXX-6259 Document Request This letter transmitted copies of various documents as requested by CYGNA. Advance copies of the documents were provided during the January 26-27, 1987 meeting with CYGNA at CPSES.

Date Letter No. Subject 02/18/87 TXX-6258 Document Request This letter transmitted copies of the letters logged TXX-6259 and TXX-6280 (with enclosures), dated 02/11/87 and 02/18/87, respectively, as requested by CYGNA.

Date Letter No. Subject 02/18/87 TXX-6280 Resolution of CYGNA Concerns

, Document Transmittal This letter transmitted copies of documents requested by CYGNA to facilitate its review of pipe stress and pipe support issues.

Date Letter No. Subject 02/18/87 TXX-6294 Meeting Notice i

This letter transmitted a notice of a forthcoming meeting between i CYGNA'and Stone & Webster Engineering Corporation. The purpose of the meeting is to discuss the Corrective Action Program (Piping and Pipe Support).

_ QLQ Letter No. Subject I

I 02/19/87 TXX-6300 Meeting Notice This letter transmitted notice that the meeting scheduled between CYGNA and SWEC has been rescheduled for one day, rather than two.

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1 Date Letter No. Subject 02/20/87 TXX-6302 Meeting Notice This letter transmitted notice of a forthcoming meeting between CYGNA, SWEC, EBASCO and IMPELL. The purpose of the meeting is to discuss the Corrective Action Programs involving cable tray hangers and attachments to embedded plates. This notice supercedes the notice provided by TXX-6294 dated 02/18/87.

Date Letter No. Subject 03/20/87 TXX-6354 Meeting Notice This letter transmitted notice of a forthcoming meeting between TU Electric, CYGNA, SWEC, IMPELL and E8ASCO. Purpose of the meeting is to discuss conduit supports, cable trays, pipe stress and pipe supports.

Date Letter No. Subject 03/25/87 TXX-6355 Transmittal of Documents This letter transmitted copies of documents as requested by CYGNA.

Date Letter No. Subject 04/16/87 TXX-6401 Meeting Notice This letter transmitted notice of a forthcoming meeting between

. TU Electric, CYGNA, SWEC, IMPELL and EBASCO. Purpose of the meeting is to discuss design control and design basis consolidation program, electrical issues, mechanical issues, instrumentation and control issues, civil / structural issues,

conduit supports and cable tray hangers.

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INTERNAL AUDITS The following internal audit reports of Engineering and Construction activities were January 26, 1987 - April 25, 1987:

issued during the time period of Number: TCP-87-01 Date: 01/05/87-03/03/87 Report Date: 02/24/87 Scope: This audit was conducted to verify _ implementation of the Construction Phase Program for purchasing safety-related materials, parts, components and services.

Number: TCP-87-03 Date: 01/08-15/87 Report Date: 02/12/87 Scope: This audit was performed to verify program implementation of the Unit I and Unit 2 Bunker Ramo Electrical Penetration Module replacement activities, including the training of personnel and generation of the appropriate documentation.

Number: TCP-87-04 Date: 02/02-03/87 Report Date: 03/24/87 Scope: This audit was conducted to verify the readiness and adequacy of SWEC-CAP's program for performing work both at the CPSES site and in their Boston, MA., facility.

Number: TCP-87-06 Date: 02/16/87 - 03/04/87 Report Date: 03/20/87 Scope: The scope of the audit was to perform an evaluation of the ASME Section XI program for the repair, replacement or modification of Unit I and common component supports.

The scope did not include verification of the program implementation.

r Number: TIN-86-06 Date: 12/15-19/86 Report Date: 04/10/87 Scope: This audit was performed to review and evaluate the controls and functions associated with the TU Electric Nuclear Engineering and Operations -

Nuclear Licensing Department. The audit scope included applicable requirements of 10 CFR 50 Appendix B, CPSES FSAR, Corporate QA Program, and NE0 Procedures.

MISCELLANEOUS The following additional correspondence was issued by Applicants to the NRC during the time period of January 26, 1987 - April 25, 1987:

Date _ Letter No. Subject 02/13/87 TXX-6236 Status of the CPSES Diesel Generator Action Items This letter transmitted the results of TU Electric's review of "NRC Safety Evaluation Report of the Operability / Reliability of Emergency Diesel Generators Manufactured by Transamerica DeLaval, Inc." as applicable to CPSES Unit 1.

Date Letter No. Subject 02/09/87 TXX-6270 BISCO Electrical Penetration Seals and NAMCO Switches This letter transmitted additional information, as requested, on BISCO electrical penetration seals and NAMCO switches.

Date Letter No. Subject 02/13/87 TXX-6279 Transmittal of WCAP-11174 This letter transmitted a copy of Westinghouse Report WCAP-11174 pertaining to the heat treatment and shotpoening of the CPSES Unit I steam generator tubes. This report was transmitted earlier (TXX-6112 dated 11/24/8), but apparently copies were not received by the NRC.

Date Letter No. Subject 02/18/87 TXX-6298 Document Request by Gibbs & Hill This letter transmitted various documents as requested by Gibbs &

Hill per letters dated 01/20/87 and 01/29/87.

r Date _ Letter No. Subject 02/19/87 TXX-6299 OIA Report 86-10 This letter transmitted additional information, as requested, on OIA Report 86-10 regarding a piping spool piece. Additionally, Prawings 4260, 1212E59 and 1457F27 with Component Modification Card Rev.1 and Design Change Authorization 16813, Rev.8 were provided as requested.

Date Letter No. Subject 02/27/87 TXX-6295 Final Report Re: Allegations This letter transmitted information concerning an evaluation of an allegation involving cans of trash buried in the containment wall.

Date _ Letter No. Subject 03/04/87 TXX-6324 Meeting Notice This letter transmitted notice of -a forthcoming meeting between CASE and TV Electric at which Stone & Webster will be in attendance.

Pipe Supports.

The purpose of the meeting is to discuss large Bore Date Letter No. Subject 03/13/87 TXX-6320 Mild Environment Equipment Category This letter transmitted information concerning the definition of a mild environment equipment category to be incorportated into the Equipment Qualification Program at CPSES and provides background information supporting the establishment of such a category.

Date Letter No. Subject 03/16/87 TXX-6314 Response to Notice of Nonconformance - SWEC This letter transmitted information regarding a Notice of Nonconformance involving an inspection of the program implementation of Stone & Webster's Quality Assurance activities relating to the Design Requalification of piping and pipe supports for CPSES.

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Date letter No. Subject 03/26/87 TXX-6345 SWEC Procedure CPPP-7, Revision 3 This letter transmitted Revision 3 to Stone & Webster Engineering Corporation's Comanch Peak Project Procedure CPPP-7.

Date letter No. Subject 03/27/87 TXX-6367 Arbitrary Intermediate Pipe Breaks This letter transmitted additional information regarding NRC's request of 09/11/86 for information concerning elimination of arbitrary intermediate pipe breaks. A previous response had been provided on 10/21/86 per TXX-6057.

. Date letter No. Subject 04/01/87 TXX-6385 SWEC Memo re: CPPP-7, Revision 3 This letter transmitted a project memorandum used to identify sections of CPPP-7, Revision 3, which require confirmation for their usuage, where this is not specified in the text.

Date Letter No. Subject 04/01/87 TXX-6364 Amendment 62 This letter transmitted Amendment 62 to the CPSES FSAR.

Date Letter No. Subject 04/01/87 TXX-6365 Amendment 62 Description This letter transmitted a description of Amendment 62 to the CPSES FSAR.

Date Letter No. Subject 04/08/87 TXX-6347 Intent to Remove Hot Cell This letter transmitted notification to TU Electric's intent to remove the Hot Cell as described in the FSAR, sections II.B.2 and II.B.3.

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_Date Letter No. Subject 1

04/15/87 TXX-6376 Fire Protection Program This letter transmitted comments containing clarifications of the CPSES Fire Protection Program as they relate to the NRC's SER

' discussion , as well as updates of the CPSES program.

Dats Letter No. Subject 04/15/87 TXX-6398 Performance Testing of Relief Safety Valves

, This letter transmitted additional information as requested regarding the TU Electric submittal of 06/13/86, "NUREG-0737, Item 11.0.1- Performance Testing of Relief and Safety Valves."

Date Letter No. Subject 04/21/87 TXX-6393 Transmittal of DOE Form EIA-254 This letter transmitted a copy of DOE Form EIA-254, " Semiannual i y, Report on Status of Reactor Construction" for CPSES Unit 1 and 2.

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e OTHER On behalf of TU Electric, R. A. Wooldridge has submitted various documents to the ASLB for their information. These documents include the following for the time period of January 26, 1987 -

April 25, 1987:

02/19/87 Appearance of Counsel in Dockets 50-445, 50-446 and 50-445-CPA.

02/23/87 Notice of meeting between CYGNA, SWEC, EBASCO and IMPELL.

02/27/87 Approved Results Reports: III.b & VII,b.1 03/04/87 Notice of meeting between CASE and TU l Electric with SWEC attending.(Large Bore l Pipe Supports) l 03/20/87 Correction to notice of meeting between CYGNA SWEC, EBASCO and IMPELL.

03/26/87 Transmittal of TXX-6355 which provided j information as requested by CYGNA.

l 03/26/87 Transmittal of TXX-6345 which provided copies of CPPP-7, Revision 3 to the NRC.

l The following reports were issued by the CPRT Overview Quality Team 1987:

(0QT) during the time period of January 26, 1987 - April 25, 01/28/87 QQD Internal memo from J.F. Streeter to J.W. Beck transmitting the CPRT 0QT Progress and Status Report. This report includes a summary of the OQT meeting held January 5-9, 1987 and a Progress and Status Report of 0QT activities.

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O The following listing represents the consultants' reports received 26, by CPSES Engineering during the time period -of January 1987 - April 25, 1987:

Instrumentation & Control Generic Issues Report

• Unit 1 Large Bore Piping Final Report

• Generic Technical Issues Report for CTH-Rev.1

• Fire Protection System Corrosion Evaluation and Study

• Evaluation and Resolution of Generic Technical Issues for CTH

• Mechanical Generic Issues Report

• EPM Purchasing and Receiving Computer System Study Report

• Relaxtion Testing

• Cinched,-Single-Strut U-Bolt Supports Design Review, Application Procedure and Acceptance Criteria Report i

• Richmond Report Insert / Structural Tube Steel Connection

• Richmond Insert / Structural Tube Steel Connection Design Interaction Equation for Bolt / Threaded Rods Report

• Richmond Insert / Structural Tube Steel Connection-Evaluation of CPPP-7 Modeling Procedures Report

• Evaluation DM 86-001 Pressurizer Spray Bypass Valve l

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• Seismic Analysis Verification Study i

• Interaction Relation for a Structural Member of Circular Cross Section

• Survey of Structural Tubing-Field Damages

• Installation of Main Steam Pipes Rev.'s 0,1,2

Technical Approach for Resolution of Installation Requtrements for Hilti Wedge Expansion Anchors, Rev.0 Technical Approach for Resolution of Installation Requirements for Hilti Wedge Expansion Anchors, Rev.2 Generic Issues Report, Evaluation and Resolution of Generic Technical Issues for Cable Tray Hangers, Rev.1 Generic Issues Report, Evaluation and Resolution of Generic Technical Issues for Cable Tray Hangers, Rev.2 Final Summary Report - Comanche Peak Cable Tray Test, Rev.0 Test Report for Cable Tray Shim Test, Rev.0 Systems Interaction Program, Generic Issues Report Acceptable Support Bearing Loads on Pipe Based on Plastic Analysis, Rev.0 Benchmark of IMPELL Superpipe and Superpost Computer Programs Used for Cable Tray Structural Requalification Train C Conduits - Level 6 Lightly Loaded Support Rev. 0 CPSES Cable Tray System-Analysis / Test Correlation Rev. 0 PORY Discharge Transient Test Test Procedure for Obtaining and Testing Drilled Core Samples of Concrete 1

Review of TSI Protective Envelope Fire Test 4702

• Visual Inspection of Painted HVAC Support / Duct Welds Seismic Simulation Test Program on Four Terminal Blocks

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Report #01-0210-1583 " Anchor Bolt Installation Torque Issue" Rev.0, Report #01-0210-1584 " Rod Hanger Coupler Issues" Rev.0

" Survey of Structural Tube Steel Dimensions to Verify the Effective Thrust of Flare Bevel Welds" (CP0-5673)

Project Status Report-Large Bore Piping and Pipe Supports CPSES (CP0-5927) 3 4

acur ti r uur CERTIFICATE OF SERVICE

'87 MAY 22 P5 :04 I, William S. Eggeling, hereby certify that on May 18, 1987, I 0FFu i ..- r. t , >

made service of the " Applicants' Fif th Progress Report'! :by rmailing BHMic' copies thereof, postage prepaid, to:

Peter B. Bloch, Esquire Mr. James E. Cummins Chairman Resident Inspector Administrative Judge Comanche Peak S.E.S.

Atomic Safety and Licensing c/o U.S. Nuclear Regulatory Board Commission U.S. Nuclear Regulatory P.O. Box 38 Commission Glen Rose, Texas 76043 Washington, D.C. 20555 Dr. Walter H. Jordan Ms. Billie Pirner Garde Administrative Judge GAP-Midwest Office 881 W. Outer Drive 104 E. Wisconsin Ave. - B Oak Ridge, Tennessee 37830 Appleton, WI 54911-4897 Chairman Chairman Atomic Safety and Licensing Atomic Safety and Licensing Appeal Panel Board Panel U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 Lawrence J. Chandler, Esquire Mrs. Juanita Ellis Office of the Executive President, CASE Legal Director 1426 S. Polk Street U.S. Nuclear Regulatory Dallas, Texas 75224 Commission Washington, D.C. 20555

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Renea Hicks, Esquire Ellen Ginsberg, Esquire Assistant Attorney General Atomic Safety and Licensing Environmental Protection Division Board Panel P.O. Box 12548, Capitol Station U.S. Nuclear Regulatory Commission Austin, Texas 78711 Washington, D.C. 20555 Anthony Roisman, Esquire Mr. Lanny A. Sinkin Suite 600 Christic Institute 1401 New York Avenue, N.W. 1324 North Capitol Street Washington, D.C. 20005 Washington, D.C. 20002 Dr. Kenneth A. McCollom Mr. Robert D. Martin Administrative Judge Regional Administrator 1107 West Knapp Region IV Stillwater, Oklahoma 74075 U.S. Nuclear Regulatory Commission Suite 1000 611 Ryan Plaza Drive Arlington, Texas 76011 Elizabeth B. Johnson Geary S. Mizuno, Esq.

Administrative Judge Office of the Executive Oak Ridge National Laboratory Legal Director P.O. Box X, Building 3500 U.S. Nuclear Regulatory Commission Oak Ridge, Tennessee 37830 Washington, D.C. 20555 Nancy Williams Cygna Energy Services, Inc.

101 California Street Suite 1000 San Francisco, California 94111 s . .b William S. Eglithg l