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| {{Adams | | {{Adams |
| | number = ML20238D460 | | | number = ML20149K706 |
| | issue date = 12/18/1987 | | | issue date = 02/11/1988 |
| | title = Insp Repts 50-445/87-31 & 50-446/87-23 on 871104-1201. Violations & Deviations Noted.Major Areas Inspected: Applicant Actions on Previous Insp Findings & Corrective Action Program | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/87-31 & 50-446/87-23 |
| | author name = Ellershaw L, Livermore H | | | author name = Warnick R |
| | author affiliation = NRC OFFICE OF SPECIAL PROJECTS | | | author affiliation = NRC OFFICE OF SPECIAL PROJECTS |
| | 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 = 50-445-87-31, 50-446-87-23, NUDOCS 8801040267 | | | document report number = NUDOCS 8802230426 |
| | package number = ML20238D401 | | | title reference date = 01-29-1988 |
| | 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 = 15 | | | page count = 4 |
| }} | | }} |
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| {{#Wiki_filter:' | | {{#Wiki_filter:. _ _ _ _ _ _ _ _ _ _ _ ____ - -_ _ - _ _ _ |
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| APPENDIX C d S. NUCLEAR REGULATORY COMMISSION
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| OFFICE OF SPECIAL PROJECTS f
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| NT// Inspection Repe.:t 50-445/87-31 Permits: CPPR-126 50 - 4 4 6 / 8 ~1,- 2 3 CPPR-127 Dockets: 50-46 4 Category: A2 50-446
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| g i Construction N rmit E.xpiration Dates s .
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| Ifnit 1: August i, 1988 Unit 2: Extension request submitte Applicar t. : ..TU Slect:'ic i Skyway Tower
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| 400 North Olive Street
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| Lock Box 81 Dallas, Tm:as 75201 l Facility Name: Comanche Peak Steam Electric Station (CPSES), .
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| Units 1 & 2 ,
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| Inspection At: Comanche Peak Sif;e'; Glen Rose, Texas
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| Inspection Conducted: Nover.'03er 4 through DecedMr 1, 1987
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| , l Inspectors: s d '
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| D. E. El'lershaw, Reactor Inspector Diat9'
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| (paragraphs 2, 3, 4, and 5.b) ..>
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| Consultants: FG&G - J. Dale (paragraph 2) ,, .
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| hrameter - K. Graham (paragraphs 3.a and b)
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| P. Stanish (paragraphs 3.c and d)
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| 1 's Reviewed by: RFliian,rtM & -
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| /W/r/87 H. H. Livermore, Lead Project Date Inspector
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| 8801040267 871213 PDR ADOCK 05000445 G PDR s
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| | i FEB l l 1988 In Reply Refer To: |
| | Dockets: 50-445/87-31 50-446/87-23 . |
| | TU Electric ATIN: Mr. W. G. Counsil , |
| | Executive Vice President ! |
| | 400 North Olive, Lock Box 81 r Dallas, Texas 75201 I |
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| | Gentlemen: [ |
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| | Thank you for your Letter TXX-88162 dated January 29, 198 t We have reviesed your revised response and have no further , |
| | questions at this tim We will review the implementation of your corrective and preventative actions during a future r inspection to determine if full compliance has been achieved and ! |
| | will be maintaine |
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| Inspection Sumrpay:
| | Sincerely, |
| Inspection Conducted: November 4 through December 1, 1987 (Report 50-445/87-31; 50-446/87-231 Areas Inspected: Nonroutine, unannounced inspection of applicant actions on previous inspection findings and the corrective action ;
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| progra l Results: Within the two areas inspected, two violations l (incorrect walkdown data was recorded, paragraph 3.c; and i uncontrolled rework was performed, paragraph 2.c and 2.d) and one l deviation (several departures from the criteria of the post l construction hardware validation program not identified, paragraph 3.d) were identifie i I
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| | ORIGINAL SIGNID BY R. F. V/AP'iICF ! |
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| | R. F. Warnick, Assistant Director , |
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| | for Inspection Programs : |
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| | Comanche Peak Project Division l Office of Special Projects j cc [ |
| | (See attached) ; |
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| | AD IP R M ! |
| | OSP:CPPD:IP HLivermore W j//, RWarnick ! |
| | 2/11/88 2/11 /88 j I |
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| | l 8802230426 890211 ! |
| | PDR ADOCK oS000445 r G PDR i |
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| | TU ElGctric cct Roger D. Walker Bureau of Radiation Control Manager, Nuclear Licensing State of Texas Texas Utilities Electric Company 1100 West 49th Street skyway Tower Austin, TX 78756 400 North Olive Street, L.B. 81 Dallas, TX 75201 Nancy H. Williams CYGNA Energy Services Juanita Ellis Suite 390 President - CASE 2121 N. California Blvd 1426 South Polk Street Walnut Creek, CA 94596 Dallas, TX 75224 Thomas G. Dignan, J Renea Hicks, Es Ropes & Gray Assistant Attorney General 225 Franklin Street Environmental Protection Division Boston, MA 02110 P.O. Box 12548, Cap'.tol Station Austin, TX 78711-7.548 Robert A. Wooldridge, Es Worsham, Forsythe, Sampels Administrativo Judge Peter Bloch and Wooldridge U.S. Nuclear Rogalatory Commission 2001 Bryan Tower Washington, DC 20555 Suite 2500 Dallas, TX 75201 Elizabeth B. Johnson Administrative Judge Mr. Homer C. Schmidt Oak Ridge National Laboratory Director of Nuclear Post Office Box X, Building 3500 Services Oak Ridge., TN 37830 TU Electric Skyway Tower Dr. Kenneth A. McCollom 400 N. Olive St., L.B. 81 1107 West Knapp Dallas, TX 75201 Stillwater, OK 74075 Mr. Robert E. Ballard, J Dr. Walter H. Jordan Director of Projects clo Carib Terrace Motel Gibbs and Hill, In N. Ocean Boulevard 11 Penn Plaza Fcmpano Beach, Florida 33062 New York, NY 10001 Anthony Z. Roisman, Es Mr. S. Howard Suite 600 Westinghouse Electric 1401 New York Avenue, Corporation Washington, DC 20005 Post Office Box 355 Pittsburgh, PA 15230 l Ms. Billie Pirner Garde, Es Government Accountability Project Lanny A. Sinkin Midwest Office Christic Institute 304 East Wisconsin Avenue 1324 N. Capitol Street Appleton, WI 54911 Washington, DC 20002 |
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| i DETAILS Persons Contacted
| | TV Electric cc (continued) |
| *R. P. Baker, Engineering Assurance (EA) Regulatory Compliance Manager, TU Electric | | David R. Pigott, Es Jack R. Newman, Es Orrick, Herrington & Sutcliffe Newman & Holtzinger, Montgomery Street 1615 L Street, San Francisco, CA 94111 Washington, Robert Jablon Bonnie S. Blair Spiegel & McDiarmid 1350 New York Avenue, NW Washington, DC 20005-4798 George A. Parker, Chairman Public Utility Committee Senior Citizens Alliance of Tarrant County, In Wonder Drive Fort Worth, TX 76133 Joseph F. Fulbright Fulbright & Jaworski 1301 McKinney Street Houston, TX 77010 Mr. Jack Redding c/o Bethesda Licensing TU Electric 3 Metro Center, Suite 610 Bethesda, MD 20814 William A. Burchette, Es Counsel for Tex-La Electric Cooperative of Texas Heron, Burchette, Ruckert & |
| *R. D. Best, Nuclear Operations Inspection Report Item Coordinator, TU Electric l *D. N. Bize, EA Regulatory Compliance Supervisor, TU Electric | | Rothwell Suite 700 1025 Thomas Jefferson St., NW Washington, DC 20007 James P. McGaughy, J GDS Associates, In Suite 720 1850 Parkway Place Marietta, GA 30067-8237 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 |
| *J. T. Conly, Lead Licensing Engineer, Stone & Webster Engineering Corporation (SWEC)
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| C. G. Creamer, Instrumentation & Control (I&C) Engineering Manager, TU Electric
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| *R. D. Delano, Licensing Engineer, TU Electric
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| *M. D. Gaden, CPRT, IT Corporation
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| *P. E. Halstead, Manager, Quality Control (QC), TU Electric
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| *T. L. Heatherly, EA Regulatory Compliance Engineer, TU Electric !
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| *D. A. Hodge, CPRT Interface, TU Electric .
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| *R. T. Jenkins, Manager, Mechanical Engineering, TU Electric
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| *J. J. Kelley, Manager, Plant Operations, TU Electric
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| *J. J. LaMarca, Electrical Engineering Manager, TU Electric
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| *0. W. Lowe, Director of Engineering, TU Electric
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| *D. M. McAfee, Manager, Quality Assurance (QA), TU Electric-
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| *D. E. Noss, QA Issue Interface Coordinator, TU~ Electric
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| *D. M. Reynerson, Director.of Construction, TU Electric
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| *M. J. Riggs, Plant Evaluation Manager, Operations, TU Electric
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| *A. B. Scott, Vice President,. Nuclear Operations, TU Electric
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| *C. E. Scott, Manager, Startup, TU Electric
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| *J. C. Smith, Plant Operations Staff, TU Electric
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| *J. F. Streeter, Director, QA, TU Electric _ .
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| *C. L. Terry, Unit 1 Project Manager, TU Electric
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| *T. G. Tyler, Director of Projects, TU Electric j The NRC inspectors also interviewed other applicant employees during this-inspection perio * Denotes personnel present at the December 1, 1987, exit intervie . Applicant Action on Previous Inspection Findings (92701) (Closed) Open Item (445/8511-0-04): During reinspection of ERC's Verification Package I-M-HVIN-038, it was identified that (a) the exhaust flange gasket did not cover the entire area, (b) the gasket was unevenly compressed, and (c) some lock washers did not have full contact with the flange. Similar conditions were identified for the inlet duct connectio i A subsequent reinspection of this verification package by' I the NRC inspector revealed that the exhaust gasket, while ,
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| not covering the entire flange, did cover the entire mating surface of the flange connections.. The gasket is more compressed just beneath the bolt heads; however, it is acceptable in accordance with Revision 1 of QI-02 The NRC inspector found all lock washers to be fully compressed and in contact with the flang The NRC inspector determined by reinspection that the above items are in conformance with inspection requirements and should not have been identified as potential deviations by the ERC inspector. Therefore, this item is close (Open) Open Item (446/8511-0-09): A potential deviation regarding grout not completely covering the base plate shims for Verification Package I-S-PWRE-51 Note: The NRC discussion pertaining to this open item in NRC Inspection Report 50-445/87-06; 50-446/87-05 is incorrect and is being restated her Subsequent to the identification of this potential deviation, ERC initiated Deviation Report (DR)
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| I-S-PWRE-518-DR1 on October 11, 1985. The DR was invalidated on November 26, 1985, based on the fact that grout and shims are not attributes to be inspected in the pipe whip restraint population. The DR further stated that "an out-of-scope observation may be written."
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| Further NRC review of this open item has determined that an out-of-scope (DOS) observation was written (1344);
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| however, it has.not yet been evaluated, thus an nonconformance report (NCR) has not been initiated. This item will remain open pending evaluation of the OO (Closed) Open Item (446/8511-0-11): This item addressed damaged grout (a crater) which was identified during an ERC inspection of Verification Package I-S-PWRE-51 Note: The NRC discussion pertaining to this open item in NRC Inspection Report 50-445/87-06; 50-446/87-05 is incorrect with respect to the OOS and NCR numbers, and is being restated her ERC initiated OOS 205 on October 23, 1985, which documented the presence of a crater which had been chipped out of the base plate grout. The 005 was evaluated and resulted in the issuance of NCR C 86-200378X on February 14, 1986. The disposition of the NCR required rework by correcting the defective area in accordance with the latest revision of CCP-1 It required the use of an approved commercial nonshrink
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| grout with mixing to be performed in accordance with manufacturers instruction. QC was to inspect per the latest revision of QI-QP-11.0-5. This disposition was approved by engineering and-QA on January 8, 1987, and February 9, 1987, respectively. . Subsequently on June 20, 1987, the disposition, verification'and closure block was annotated with the' statement " Transferred to NCR
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| #CC-87-8190X."
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| The NRC inspector reviewed NCR CC-87-8190X dated June 16, 1987, and identified the following:
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| The disposition had been' changed to use-as-is with the following note, "This disposition includes pages 1 thru 8."
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| All disposition approval blocks were signed off and dated, including QA/QC verification which was dated August 10, 198 Page 6 of the NCR is a memorandum dated June 12,.1987, and addressed to the NCR group and states ir, part,
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| "Between the time NCR disposition was issued and then corrected . . . the area in question was repaired on general preparation of room for coatings. Area is repaired but not to the disposition of [the] NCR."
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| Page 5 of the NCR is a memorandum dated June 16, 1987, addressed to SWEC Civil / Structural group and references the above memo (page 6).- It recognizes the fact that the disposition must be changed because the work had already been performed, but not to the stated disposition. It stated that in order to revise the disposition, a new NCR must be issue Page 4 is a memo dated July 14, 1987,.from SWEC' I civil / Structural to QC in which it is stated that visual inspection shows no damage at the specified location. It .
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| also requests verification of location and that this i clarification is required for the disposition-(use-as-is)
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| of NCR CC-87-8190X. The reply from QC on July 16,.1987, states that " Indication of damage can not be ascertained at this date because paint craft patched the damage ,
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| unaware of the reporting NCR . . . . "
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| l Criterion XVI of Appendix B to 10 CFR Part 50, as implemented by Section 16.0, Revision 0, of the TU Electric Quality Assurance Plan (QAP), states, in part, " Measures shall be established to assure that conditions adverse to quality . . are promptly identified and corrected . . . and corrective action ) | |
| taken to preclude repetitio j l
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| Nuclear Engineering and Operation Procedure NEO 3.06,
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| " Reporting and Control of Deficiencies," requires deficiencies (principally programmatic and not directly related to hardware problems) to be identified, the cause established, and action taken to prevent repetitio The changing of the NCR disposition from " rework" to .
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| "use-as-is" subsequent to engineering becoming aware that i the conditions which created the need for the NCR had been corrected by uncontrolled work; i.e., outside the l scope and control of the NCR, constitutes a violation of Criterion XVI of Appendix B to 10 CFR Part 50 and NEO Procedure 3.06, " Reporting and Control of Deficiencies."
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| Further, by revising the disposition and closing out the NCR, actions were not taken to determine the cause of the deficiency (uncontrolled work) or to prevent repetition (445/8731-V-02A; 446/8723-V-01A). (Closed) Open Item (445/8514-0-16): This item addressed two sending Units 1-LS-6712 and 1-LS-6717 which were identified by the ERC inspector to the NRC inspector, as being reversed during a reinspection of Verification Package I-E-ININ-069. As a result of this observation, ERC DR I-E-ININ-069-DR1 was initiated which resulted in the issuance of NCR I-85-101890 SX. The disposition of the NCR required rework by TUGCo I&C calibration l
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| personnel which consisted of returning the switch housings to their originally installed positions and for QC to verify location and serial number in accordance with the current revision of QI-QP-11.8-5. This disposition was approved by engineering on June 6, 1986, and QA on June 9, 1986. The comments block was annotated with the statement "Rev. 2 For Disposition." The disposition of Revision 2 to NCR I-85-101890 SX shows the Use-As-Is box checked off and contains the statement,
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| "This is no longer a non-conforming conditio Instruments are located per location drawing 2323-M1-2610 and serial number. See attached instrument installation j checklist and material received record." A check was 1 made with permanent plant maintenance (PPM) to determine if the sending units had been corrected during routine ] ,
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| maintenance. PPM was unable to locate any work requests for the sending units in questio The changing of the NCR disposition from " rework" to
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| "use-as-is" as a result of uncontrolled work being
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| | l DISTRIBUTION: |
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| | 49eekettriles:(50 44S/446)12 l NRC PDR > |
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| | LPDR OSP Reading l CPPD-LA l CPPD Reading (HQ) |
| | | Site Reading CPRT Group i SRI-OPS SRI-CONST i AD for Projects l |
| performed, is another example of the violation contained in paragraph 2.c above (445/8731-V-02B; 446/8723-V-01B).
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| | | MIS System, RIV RSTS Operator, RIV " |
| 3. Corrective Action Program (CAP)
| | DRP, RIV I RIV Docket File i DWeiss, RM/ALF l JTaylor SEbneter/JAxelrad I CGrimes PMcKee ' |
| NRC inspections were performed to verify the applicant's activities associated with the Post Construction Hardware Validation Program (PCHVP). The PCHVP was established to reconcile the design to the design bases appropriate to satisfy licensing commitments, and to reconcile the hardware ; | | JLyons AVietti-Cook MMalloy i JMoore, OGC [ |
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| to the design: 1.e., the constructed / installed systems meet the intent of the design. The following CAPS were inspected during this report perio HVAC (50100)
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| The NRC inspector has reviewed the following procedures associated with implementation of the HVAC CAP and will continue to evaluate the implementation of these procedures during subsequent NRC inspections:
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| CPE-EB-FVM-CS-029 - Revision 5, " Field Verification Method Procedure for Seismic HVAC Duct and Duct Hanger As-Built Verification in Unit 1 and Common Areas" CPE-EB-FVM-CS-066 - Revision 1, " Field Verification 1 Method Procedure for As-Built Verification of Seismic HVAC Air Handling Units, Plenums, and Equipment Supports in Unit 1 and Common Areas" CHV-101 - Revision 1, "HVAC - Detailing, Fabrication, Installation, Rework, and Repair" CHV-106 - Revision 1, " Qualitative Walkdown of HVAC Supports and Ducts (Unit 1 and Common Areas)"
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| The NRC inspector reviewed the construction operation travelers (COT) listed below to determine if the applicants safety class, system pressure, and duct construction type designation are in accordance with Comanche Peak Engineering Specification 2323-MS-85,
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| "HVAC - Ducts, Louvers, and Accessories," Revision 5, dated September 15, 198 B-1-801-751-091, Revision 0 B-1-801-751-093, Revision 0 B-1-801-751-094, Revision 0 B-1-801-751-150, Revision 0 B-1-801-751-151, Revision 0 B-1-3201-752-158, Revision 0 B-1-3201-752-163, Revision 0 B-1-3201-752-164, Revision 0
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| B-1-3201-757-037, Revision 0 )
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| B-1-3201-757-042, Revision 0 B-1-3601-653-091, Revision 0 B-1-3602-655-027, Revision 0 B-1-3603-654-044, Revision 0 B-1-3603-654-050, Revision 0 B-1-3901-658-014, Revision 0 B-1-3901-658-022, Revision 0 B-1-3901-658-023, Revision 0 B-1-3901-658-025, Revision 0 The NRC inspector reviewed the COTS listed below in order to evaluate the adequacy and completeness of engineering instructions for performance of craft work activitie B-1-701-756-249, Revision 0 B-1-701-756-272, Revision 0 B-1-701-758-059, Revision 0 B-1-701-758-139, Revision 0 B-1-701-758-144, Revision 0 B-1-701-758-145, Revision 0 B-1-701-758-148, Revision 0 B-1-702-758-081, Revision 0 B-1-702-758-082, Revision 0 B-1-702-758-083, Revision 0 B-1-2401-760-055, Revision 0 The NRC inspector determined that, for the listed COTS, the applicant has correctly designated the classifications in accordance with Specification 2323-MS-85, Revision 5, and that the engineering instructions are adequate and complet No violations or deviations were identifie b. Large Bore Piping and Pipe Supports (50090)
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| The NRC inspector performed a review of Brown and Root (B&R) Instruction QI-QAP 11.1-28, Revision 38, l
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| "Fa'orication and Installation Inspection of Safety Class Component Supports." Revision 38 provides relaxed quality control inspection criteria for the determination of acceptable versus unacceptable welding arc strikes on pipe supports. The basis for this change in pipe support inspection requirements _was Design Change Authorization (DCA) 18322, Revision 3, to mechanical specification 2323-MS-100, " Field Fabrication and Erection of Piping and Pipe Supports, which resulted in the subsequent revision of the B&R instruction. NRC inspectors reviewed the following references supporting the technical justification for approval of the DCA:
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| i Van Malssen, S. H., "The Effects of Arc Strikes on Steels !
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| Used in Nuclear Construction" - Welding Journal, July 1984 Kasen, M. B., Hicho, G. E., and Placious, R. C.,
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| " Inherent Through-Wall Depth I. imitations on Blunt Discontinuities in Welds" - Welding Journal, June 1984 Kasen, M. B., " Significance of Blunt Flaws in Pipeline Girth Welds" - Welding Journal, May 1983 l From this review, the NRC inspectors concur with the DCA and the resulting revision to QI-QAP 11.1-2 No violations or deviations were identifie c. Conduit Supports A & B Train and C Train > 2" (48053)
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| During this inspection period the NRC inspector selected a sample of six conduit walkdown packages to verify the accuracy and correctness of the EBASCO collected dat The following is a list of the NRC inspected packages:
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| Conduit Size Room * Area ** Supports ,
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| FC14B13125 3" 155A RB1 6 i C13OO7808 3" 108 SG1 8
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| C13OO7294 1 1/2" 154 RB1 3 ;
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| C13008625 1 1/2" 161A RB1 6 l C14G21398 1" 66/70 SG1 7 CO2011930 3" 135/148 ECB 3 C12K15004 3" 133 ECB 10
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| *SG1 - Unit 1 Safeguards Building
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| *RB1 - Unit 1 Reactor Building
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| *ECB - Electrical / Control Building
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| ** Number of supports includes conduit, junction box and pull box support The NRC inspector's walkdowns were performed while l adhering to the criteria of field verification method (FVM) CPE-EB-FVM-CS033, Revision 3, and resulted in the l
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| identification of the following discrepancies:
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| i (1) on Conduit Support C13007808-04, the walkdown engineer lined out the anchor bolts in locations A, E, and F. This implies that these bolts do not exist for this suppor During a subsequent walkdown by the NRC inspector, it was noted that an additional anchor bolt did exist in the position designated on the support sketch as location I | |
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| ,' 10 This anchor bolt was determined to be a 1/4" Hilti Kwik bolt with the letter designation "D" and a projection of 1". While the existence of this additional anchor bolt will not have a detrimental effect on the structural integrity of the support, the fact that it was not identified during the EBASCO walkdown is of significance relative to the adequacy of the walkdown itsel (2) For Support C14G21398-03, a 2323-S-0910 sh. CSM-18 type support, the walkdown engineer failed to report one of the dimensions required to fully locate the structural tubing on the baseplate. This information is required to calculate the baseplate stress and anchor bolt loads. The dimension not provided locates the bottom of the structural tubing relative to the bottom of the baseplate as installed and is a dimension that is required to be reported for this type of suppor (3) on support C14B13125-02, the walkdown engineer failed to note a spacing violatic? between the 1/4" Hilti Kwik bolt designated as Bolt F on the support in question, and a 3/8" HKB on an adjacent conduit support. The NRC inspector found these anchor bolts to be 2 1/4" apart; while the FVM required a spacing of at least 3 1/8". | |
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| Criterion V of Appendix B to 10 CFR Part 50, as implemented by section 5.0, Revision 3 of the TU Electric QAP, states, in part, " Activities affecting quality shall be prescribed by documented instructions, procedure, or drawings, or a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. . . . "
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| Section 7.7.1 of Revision 2 to EBASCO's FVM CPE-EB-FVM-CS-033, states, in part, "The Walkdown Engineer will identify each type of support by comparison with j Supplement I and/or 2323-S-0910 sketches or drawings, and
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| will as built the support on the applicable sketch or drawing . . . . " Paragraph K of this section of the FVM further states, "All dimensions and/or attributes shown will be verified . . . . If the designed dimensions / attributes are incorrect, they shall be lined out and the actual dimension / attribute recorded."
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| Further, paragraph N states that the walkdown engineer will redline ". . . any HKB/HSKB spacing violation per Table 2."
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| The three above examples of incorrectly documenting existing conditions constitutes a violation of
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| D:
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| Criterion V of Appendix B to:10 CFR Part 50 and FVM CPE-EB-FVM-CS-033-(445/8731-V-01).
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| On the remaining conduit runs, the results of the NRC
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| . walkdown revealed certain data that did not match that recorded by EBASCO; however, it was deemed to be acceptable.since the. difference in the recorde dimensions was still within.the tolerances specified in the applicable FVM. This is not considered to.be a proble Conduit Supports C Train Less Than or Equal to'2" (48053)
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| For this inspection period, the NRC inspector performed a
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| review /walkdown of the total scope of work Impell performed.for_ Room 155 of the Unit 1 Containment building and Room 101 of the Unit 1' Safeguards buildin Room 155 Containment Building l
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| The following calculation /walkdown packages were-included in the NRC inspector's review of Room 15 ,
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| Calculation Title ,
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| N !
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| 1 .
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| RC01-CT155 Room Closecut' Calculation / Documentation L2-S1-CT155 Level 2 - Conduit Support Evaluation A02454 Level 5 Support Evaluation A02603 Level 5 Support' Evaluation L6-1-CT155 Level 6 - Train C Conduit' Interaction Evaluation l
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| Section 4.1, "Walkdown Guidelines" of Revision 2 to Impell Project Instruction (PI) 0210-052-004~ states, in part, "The Walkdown information will be documented using i the checklists provided in Attachment B . . . . Table 1- l l
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| provides the acceptable tolerances to be'used in the walkdown proces ;
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| "Guildelines for performing the conduit support and conduit routing walkdowns are provided below:
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| " Item Support configuration
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| - Draw an as-built sketch
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| - Identify all structural /Unistrut membe sizes, lengths . . .
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| 1 -____-- - _ _ _ - _ -
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| - _ - _ _ _ _ _ _ - _ - _ _ . ._ . -_ - - _
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| '. j
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| 12 1 i
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| " Item Hilti Kwik Anchor bolt Information
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| Ident'ify letter' stamp'and projection length ]'
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| of all anchor bolts on supports . . .. .
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| " Conduit Routing Checklist
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| " Item 1 Conduit' Isometrics )
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| - Draw an as-built sketch s'> wing conduit routing . . .
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| 1 i
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| - Determine span lengths"
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| -4 l Section 4.1.4, " Seismic Evaluation of Train C, Conduit Supports," of Revision 3 to Impell PI: 02310-052-003, states, in part, " . . . SSE support loads.are' generally calculated by multiplying'the conduit tributary: mass times the equivalent static. acceleration . . . . "
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| Paragrapk 4.3.4 further states, ". . .. for interaction of . . . loads, the following interaction . .. . equation shall be used . . . . "
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| While performing the review /walkdown for. Room.155, the .
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| NRC inspector identified the following discrepancies with respect to the walkdow (1) While performing the load calculation for the northeast / southwest direction'for support'A02605 (a-Type 5 support) in Calculation / Problem A02454, the engineer neglected to include.a 14"-length of conduit between the support being evaluated and an adjacent support. This omission would'cause.the load on this support to be understate (2) On the Type 5 support evaluation for the support-identified as analysis tag No. A02605/NQ16507, the calculated embedment length for the Hilti Kwik bolt was found to be incorrect. The Impell evaluation sheet reports the embedment to be 2 3/4";.however, based on the data. recorded by the NRC inspector, the embedment was' determined to be 1 3/4". Furthermore, on this evaluation, the interaction check for the-
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| " finger" clamp. indicates a'value of'l.05 versus an allowable of 1.0. There is a note appended to the calculation stating'"this is acceptable due to the conservatism in the evaluation"; however, this support is the same support mentioned in (1)'above for which the load. calculation is incorrect'
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| (unconservative).. Therefore, the. actual interaction will be higher than the-l.05 calculated.and Impell l
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| , 13 should review this in light of the change in applied load to insure adequacy of the suppor (3) On the Type 7 support identified as analysis tag 1 number A02456/NQ16508, the NRC inspector identified I several discrepancies. The baseplate mounted on the j wall was reported to be 3/8"x8"x8"; however, it is !
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| actually 3/8"x9"x8". This change in the length of the baseplate would have a detrimental effect on the calculated loads on the anchor bolt Impell reported that the anchor bolts en this support were 1/2" Hilti Kwik bolts and the NRC inspector determined that .ey are 1/2" Hilti Super j Kwik bolt While this is an error which is j
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| conservative in nature, it could bring into question '
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| the adequacy of the information being provided as a result of Impell's walkdow ,
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| Also, on the same support, Impell reported that the Nelson studs being used to secure the clamp to the '
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| support were 1/4" diameter, while the NRC inspector determined these bolts to be 3/8" diamete (4) On the support identified as detail "B", a Type 7 support, Impell reported that the anchor bolts were 1/2" Hilti Kwik bolts, but the NRC inspector !
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| observed that they were actually 1/2" Hilti Super Kwik bolt (5) On the isometric provided on page 4 of 8 in Appendix A, Calculation / Problem No. A02603, Impell reported a length of conduit between the Type 5 support identified as A02628 and an adjacent Type 5 i support as 21". The NRC inspector determined this length to be 12 1/2".
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| The five items above constitute a deviation to the commitments made in "Walkdown Guidelines" and " Seismic Evaluation of Train C Supports" (445/8731-D-03).
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| (6) During the review of the calculation package provided for the Level 5 support evaluation A02454, ,
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| there were several apparent inconsistencies note I First, on pages 15 and 16 of 39, the person checking the calculations dated them prior to the day the calculations were performed. Second, the support load calculations in this package were performed during several days in March 1987, the last of the calculations being performed on the 20th of March and checked on the 23rd of March. However, page 19 of 39 entitled " Summary of Loads," appears to have
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| . 14 been prepared on the 9th of March and checked on the 10th of March, which is before the date indicating when the calculations were performe !
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| Item 6 above constitutes an Unresolved Item pending further review by the NRC inspector (445/8731-U-04).
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| Room 101 Safeguards Building The following calculation /walkdown packages were included in the NRC inspector's review of Room 101:
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| Calculation Title N RCO1-SG101 Room Closecut Calculation / Documentation L2-S1-SG101 Level 2 - Conduit Support Evaluation A00389 Level 5 - Support Evaluation L6-1-SG101 Level 6 - Train C Conduit Interaction Evaluation The results of the review /walkdown revealed certain data which did not match that recorded by Impell; however, it was deemed to be acceptable since the difference in the recorded dimensions was still within the tolerances specified in the applicable Project Instruction (PI).
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| No violations or deviations were identified during the !
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| NRC inspector's review /walkdown of Room 10 J 4. Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations, or deviations. One unresolved item disclosed during the inspection is discussed in paragraph . Exit Meetings (30703)
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| Meetings held during this report period are as follows: On November 25, 1987, R. F. Warnick met with A. B. Scott and L. D. Nace to discuss items of mutual interest and the significance of inspection findings for Novembe The following topics were discussed:
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| (1) All five October inspection reports for NRC site staff were issued in less than 20 days (13.2 days average).
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| (2) The NRC staff met at the site on November 4 and 5 for the purpose of finalizing OSP's schedule for
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| 4
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| , 15 Comanche Peak and to reach a position regarding the adequacy of the applicant's corrective action program. See J. G. Keppler's memorandum to Victor '
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| Stello, dated November 6, 1987, which is in the docket file and the public document room. A public meeting to discuss the CAP will be held on December 9, 198 (3) A program has been laid out by the NRC staff for the resolution of open NRC concerns regarding ASME ,
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| issue See Inspection Report 50-445/87-20, J 50-446/87-1 (4) Four additional NRC inspectors have been hired to I fill onsite staff vacancies - Preoperational I Testing, Civil / Structural, Resident Inspector - I Operations, and Project Inspector. One vacancy remains to be filled (Ellershaw will be transferring to RIV).
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| (5) The NRC plans to resume the SALP assessments for Comanche Peak. The appraisal period being proposed by the NRC site staff to Headquarters is September 1, 1987 through August 31, 198 (6) The electrical area has several issues of concern to the staff - separation, cable pulling, lubricant, preinsulated environmental seal splices, DCAs with clarifications to the code, and DCAs liberalizing TUE commitment These issues have been documented in inspection reports, 50.55(e) reports, and FSAR amendment (7) The findings that will be documented in the November j
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| inspection reports appear to be caused by human t error Utility management must be sensitive to j identifying and preventing human error ,
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| b. An exit interview was conducted December 1, 1987, with j the applicants representatives identified in paragraph 1 I of this report. During this interview, the NRC l inspectors summarized the scope and findings of the l inspectio The applicant acknowledged the finding j l
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| g, k DISTRIBUTION:
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| ? .c m. c. n, =m n. . -.
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| fh,peccu :
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| u . n-DocketdrilesR(504445/446)?
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| NRC PDR Local PDR ;
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| OSP Reading I CPPD-LA-CPPD Reading (HQ).
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| * Site Reading
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| *CPRT Group '
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| * SRI-OPS
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| * SRI-CONST !
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| AD for Projects l
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| * MIS System, RIV
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| *RSTS. Operator,.RIV RPB, RIV RIV Docket File
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| *DWeiss, RM/ALF JTaylor SEbneter/JAxelrad CGrimes PMcKee JLyons AVietti-Cook MMalloy JMoore, OGC JGilliland,-RIV FMiraglia
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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] |
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i FEB l l 1988 In Reply Refer To:
Dockets: 50-445/87-31 50-446/87-23 .
TU Electric ATIN: Mr. W. G. Counsil ,
Executive Vice President !
400 North Olive, Lock Box 81 r Dallas, Texas 75201 I
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Gentlemen: [
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Thank you for your Letter TXX-88162 dated January 29, 198 t We have reviesed your revised response and have no further ,
questions at this tim We will review the implementation of your corrective and preventative actions during a future r inspection to determine if full compliance has been achieved and !
will be maintaine
Sincerely,
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ORIGINAL SIGNID BY R. F. V/AP'iICF !
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R. F. Warnick, Assistant Director ,
for Inspection Programs :
Comanche Peak Project Division l Office of Special Projects j cc [
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TU ElGctric cct Roger D. Walker Bureau of Radiation Control Manager, Nuclear Licensing State of Texas Texas Utilities Electric Company 1100 West 49th Street skyway Tower Austin, TX 78756 400 North Olive Street, L.B. 81 Dallas, TX 75201 Nancy H. Williams CYGNA Energy Services Juanita Ellis Suite 390 President - CASE 2121 N. California Blvd 1426 South Polk Street Walnut Creek, CA 94596 Dallas, TX 75224 Thomas G. Dignan, J Renea Hicks, Es Ropes & Gray Assistant Attorney General 225 Franklin Street Environmental Protection Division Boston, MA 02110 P.O. Box 12548, Cap'.tol Station Austin, TX 78711-7.548 Robert A. Wooldridge, Es Worsham, Forsythe, Sampels Administrativo Judge Peter Bloch and Wooldridge U.S. Nuclear Rogalatory Commission 2001 Bryan Tower Washington, DC 20555 Suite 2500 Dallas, TX 75201 Elizabeth B. Johnson Administrative Judge Mr. Homer C. Schmidt Oak Ridge National Laboratory Director of Nuclear Post Office Box X, Building 3500 Services Oak Ridge., TN 37830 TU Electric Skyway Tower Dr. Kenneth A. McCollom 400 N. Olive St., L.B. 81 1107 West Knapp Dallas, TX 75201 Stillwater, OK 74075 Mr. Robert E. Ballard, J Dr. Walter H. Jordan Director of Projects clo Carib Terrace Motel Gibbs and Hill, In N. Ocean Boulevard 11 Penn Plaza Fcmpano Beach, Florida 33062 New York, NY 10001 Anthony Z. Roisman, Es Mr. S. Howard Suite 600 Westinghouse Electric 1401 New York Avenue, Corporation Washington, DC 20005 Post Office Box 355 Pittsburgh, PA 15230 l Ms. Billie Pirner Garde, Es Government Accountability Project Lanny A. Sinkin Midwest Office Christic Institute 304 East Wisconsin Avenue 1324 N. Capitol Street Appleton, WI 54911 Washington, DC 20002
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David R. Pigott, Es Jack R. Newman, Es Orrick, Herrington & Sutcliffe Newman & Holtzinger, Montgomery Street 1615 L Street, San Francisco, CA 94111 Washington, Robert Jablon Bonnie S. Blair Spiegel & McDiarmid 1350 New York Avenue, NW Washington, DC 20005-4798 George A. Parker, Chairman Public Utility Committee Senior Citizens Alliance of Tarrant County, In Wonder Drive Fort Worth, TX 76133 Joseph F. Fulbright Fulbright & Jaworski 1301 McKinney Street Houston, TX 77010 Mr. Jack Redding c/o Bethesda Licensing TU Electric 3 Metro Center, Suite 610 Bethesda, MD 20814 William A. Burchette, Es Counsel for Tex-La Electric Cooperative of Texas Heron, Burchette, Ruckert &
Rothwell Suite 700 1025 Thomas Jefferson St., NW Washington, DC 20007 James P. McGaughy, J GDS Associates, In Suite 720 1850 Parkway Place Marietta, GA 30067-8237 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
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