ML20209H442
| ML20209H442 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/29/1987 |
| From: | Ellis J Citizens Association for Sound Energy |
| To: | Bloch P, Jordan W, Mccollom K Atomic Safety and Licensing Board Panel |
| References | |
| CON-#187-2394 OL, NUDOCS 8702060056 | |
| Download: ML20209H442 (30) | |
Text
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214/946-91A6 Dqg'n (CITIZENS ASSN. FOR SOUND ENERGY) s uutu cqnn m u,uaice
'87 FEB -3 All :20 January 29, 1987 OFF COC" Administrative Judge Peter B. Bloch Dr. Kenneth A. McCollom U. S. Nuclear Regulatory Commission 1107 West Knapp Street Atomic Safety & Licensing Board Stillwater, Oklahoma 74075 Washington, D. C.
20555 Dr. Walter H. Jordan 881 W. Outer Drive Oak Ridge, Tennessee 37830
Dear Administrative Judges:
Subject:
In the Matter of Texas Utilities Electric Company, et al.
Application for an Operating License Comanche Peak Steaa Electric Station Units 1 and 2 Docket Nos. 50-445 and 50-446 - dd Potential 10 CFR 50.55(e) Items To assist the Board in its desire to be kept up-to-date on matters of potential significance, CASE is attaching copies of the potential 50.55(e) items (SDAR's, or Significant Deficiency Analysis Reports) which we have received since we provided the Board on 12/23/86 with such items.
(We have not attempted to separate construction from design items.)
It is our intention to periodically continue to provide these SDAR's unless the Board indicates otherwise.
Respectfully submitted, CASE (Citizens Association for Sound Energy)
NW trs.) Juanita Ellis President cc: Service List m2oggggg gggg 350}
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Log # TXX-6221 File # 10010 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. 4e8 NORTH OLIVE STREET, IJL 81. DALLAS. TEXAS 7520I January 21, 1987 EII","ti?.".Une Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 TRAIN C CONDUIT SUPPORTS SDAR: CP-85-36 (INTERIM REPORT)
Dear Mr. Johnson:
On September 6,1986, we verbally notified your Mr. C. Gould of a deficiency involving the installation of non-safety related conduit (two-inch diameter and smaller) on non-safety related dead weight supports in Category 1 areas.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our last interim report logged was TXX-5041, dated October 3, 1986.
As previously reported, this issue is being evaluated by Impell under CPRT Program Plan ISAP I.c.
The program developed to address this issue involves two parts. The short term program addresses corrective action for previously installed supports.
The long term maintenance program provides for a review of newly installed safety related plant features for adverse interactions and engineerings review for acceptability of the new Train C conduit supports.
Currently, our field verification is continuing (Unit I and Common Area) to determine the adequacy of these Train C conduit supports. To date, the l
evaluation of conduit supports in 50 rooms has been completed. These efforts represent approximately 20 percent of the rooms and 50% of the supports in the l
Unit I and Common areas. Unit 2 will Le started after completion of Unit 1 and Common area.
This evaluation is currently scheduled for completion by early June 1987. We anticipate submitting our next report on this issue no later than July 8, 1987.
Very truly yours, W. G. Counsil DAR:lw 927 m L9% e9S3 A turtsrow or rzxss titurn3 FliCTRIC tintPs%Y
- - -. - _ = =
Log # TXX-6234 File # 10110 t
903.7 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. 4es NORTH OLIVE STREET.1.B. 81. DALLAS. TEXA5 76308 January 21, 1987 sM*". LL.U*%
Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 COMMODITY INSTALLATIONS AT SECONDARY WALL DESIGN GAPS SDAR: CP-86-12 (INTERIM REPORT)
Dear Mr. Johnson:
On February 27, 1986, we verbally notified your Mr. T. Westerman of a deficiency involving attachments at, or in close proximity to, design gaps between secondary walls and adjacent walls / floors. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). Our last interim report was logged TXX-6108, dated November 21, 1986.
We are continuing our evaluation and anticipate submitting our next report by March 27, 1987.
Very truly yours,
?[*
W. G. Counsil JCH/esr c - NRC Region IV (0 + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 ggJ,MO9T7 A DIVisIO4 OF TEXA5 LTILITIES ELECTRIC COhf94NY
Log # TXX-6231 File # 10110 f
903.11 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. 400 NORTH OLIVE STREET. I.B. OR. DALLAB. TEXAS 75208 January 21, 1987
- '#1".LfP.UUL Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 JET IMPINGEMENT LOAD REVIEW SDAR: CP-86-13 (INTERIM REPORT)
Dear Mr. Johnson:
On March 5, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving a computer entry error which could invalidate portions of the jet impingement load review for high energy piping. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Out latest interim report, logged TXX-6088, was submitted on November 14, 1986.
Preliminary evaluations indicate that in the event these conditions had remained undetected, no condition adverse to the safety of plant operations would exist.
Documentation supporting our position is currently in the final stages of reveiw and is scheduled for completion on March 9,1987.
Our next report will be submitted no later than April 7,1987.
Very truly yours, O'NDL W. G. Counsil JDS/esr
- NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
20555 A 01%1.110% OF TEMAS LTILITIFA ELECTRIC CO%f94%Y
Log # TXX-6230 o-File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOwt R. 400 NORTH OLIVE STREET, R.S. 88 DALLAS. TEXAS 75301
- 20dJf.UE January 21, 1987 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAX STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 FIRE EFFECTS ON INSTRUMENT TUBING SDAR:
CP-86-16 (FINAL REPORT)
Dear Mr. Johnson:
On March 21, 1986, we verbally notified your Mr. R. Hall of a deficiency involving the detrimental effects of low melting point metals (zinc) on stainless steel instrument tubing during a fire. Our latest report logged TXX-6034 was submitted October 20, 1986. We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.
Descriotion This deficiency involves the possible damaging effects of low melting point metals on stainless steel instrument tubing associated with instruments required for fire safe shutdown (but not alternate shutdown). The significance of stainless tubing in direct contact with galvanized material (zine) such as Unistrut supports and clamps during a fire has been evaluated by engineering, primarily focusing on the possibility of safey related redundant counterpart instrument tubing designed to route through the same fire zone.
Safety Imolications In the event this deficiency had remained undetected, the integrity of the instrumentation tubing could not be assured during a post-fire accident condition.
.A Dibl510% UT TEX AS LTILITIES ELECTRIC CO%IP AW
6 TXX-6230 January 21, 1987 Page Two of Two Corrt;tive Action Upon completion of the identification of existing installations, modifications will be implemented as required to alleviate all unacceptable conditions. The status of modifications will be reported under 10CFR50.55(e) via SDAR CP 19.
Very truly yours,,
V W. G. Counsil JDS/esr
- NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
20555 4
1
I Log # TXX-6239 File # 10110 903.8
. TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. 489 NORT,6 OLIVE STREET. E.S. 83. DAI.LAS. TEXAS 76301 January 26, 1987 TM1".Sif.W'A U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, DC 20555 l
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) 1 DOCKET NOS. 50-445 AND 50-446 POLAR CRANE SUPPORT STRUCTURE SDAR:
CP-86-62 (INTERIM REPORT)
Dear Mr. Johnson:
On October 3,1986, we notified you by our letter logged TXX-6011 of a deficiency involving a. misinterpretation of the polar crane load cases which we deemed reportable under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-6177, dated December 19, 1986. This is an interim report submitted to status corrective action implemented to date.
In the last interim report, we concluded that reduced loading exists for the polar crane support structure. An analysis of the acceptability of the crane rail structure for these reduced loads is currently under joint evaluation with the third party reviewers.
We anticipate submitting our next report no later than March 30, 1987.
Very truly yours,
/
/M W. G. Counsil RWH/dl c - Mr. Eric H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV A omsros or Texas Lisants stterasc coursvr
o Logs TXX-6180 File # 10110 909.5 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOwsR. ese IWORTH OLIVE STREET. LB. SI. DALLAS. TEXAS 75JSR December 23, 1986
."#M.hf?.E E Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 MINIMUM CONCRETE COVERAGE SDAR: CP-86-17 (FINAL REPORT)
Dear Mr. Johnson:
On March 21, 1985, we verbally notified your Mr. R. Hall of a deficiency concerning the minimum concrete coverage required for reinforcing steel in the walls and floors necessary to maintain a three-hour fire rating. Our last interim report was logged TXX-6111, dated November 24,:1986..
Our evaluation of the subject walls and floors indicated that postulated temperatures would not adversely affect the structural capacity of the reinforced concrete elements.
The FSAR (Section 9.5.1.5.2) requires that reinforced concrete fire walls, floors and ceilings comply with either Underwriters Laboratories Listed Designs, the Uniform Building Code (UBC), or be of a tested configuration in regard to minimum concrete cover for reinforcing steel. The CPSES fire rated walls and floors were designed to ACI 318-71, Section 7.14.1 which requires a 3/4 inch concrete cover over reinforcing steel. The following evaluation of UBC provisions has concluded that a 3/4 inch concrete cover is adequate for a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire barrier. Neither the code nor the standards specifically address cover requirements for walls as they pertain to fire resistance.
UBC Chapter 43 (Table 43-A) requires a 1 inch concrete cover to attain a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rating for certain grades of concrete.
The UBC Standards allow for an alternative method (Section 4302) to determine fire resistance.
Section 43.908 establishes that the minimum thickness of cover over reinforcing steel in slabs should comply with Table No. 43-9-J which requires a 3/4 inch concrete cover for a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rating (restrained construction).
For the purpose of the UBC Standards, an unrestrained condition is one in which the load-carrying element is free to expand and rotate at its supports.
UBC Section 2607(h) does require a minimum concrete cover for reinforcing steel for corrosion protection which is the same cover requirement as ACI 318-71.
l I
l l
l A DIYLMON OF TEXAS LTELITIES FLECTRIC CO%t9A%Y
6-TXX-6180 December 23, 1986 Page 2 UBC Table 43-A provides general requirements.
The UBC also recognizes that the alternative requirements are equally acceptable and, at least in this particular case, may provide more specific requirements for the conditions of restrained /understrained elements, while Table 43-A does not make any such distinction.
TUGC0 received a clarification of UBC requirements in July 1986.
UBC acknowledged that they did not specifically address cover requirements for walls insofar as fire considerations were concerned. They further stated that ACI 216 (ACI 216R-81, " Guide for Determining the Fire Endurance of Concrete Elements") indicated that fire endurance of concrete walls is generally governed by heat transmission through the wall, and not by structural conditions. The letter stated that the cover required by Section 2607 (h) was adequate, meaning that 3/4 inch cover was adequate for a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated barrier.
l We have concluded that the CPSES. design is in compliance with the UBC.
This issue is not reportable under the provisions of 10CFR50.55(e). Records supporting this conclusion are available for your inspectors to review at the CPSES project site.
i.
p Very truly yours,
~*
~W.G. Counsil J
By:
G. S. Keeley &
I Manager,Nuclearycensing JCH/gj i
Q c, Region IV (0 + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission i.
Washington, D. C.
20555 i
l Log # TXX-6235 File # 10110 910.3 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. est NORTH OLl% E STREET. LB 88. DALLAB. TEXAS 78208 January 21, 1987
"'##".LfP.U E Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 INSTRUMENTATION INSTALLATIONS SDAR:
CP-86-19 (INTERIM REPORT)
Dear Mr. Johnson:
On March 21, 1986, we notified you of a reportable item involving the installation of steam service pressure transmitters (see TXX-4824). This is a follow-up interim report to status the corrective actions for a reportable item under the provisions of 10CFR50.55(e). Our last interim report was logged TXX-5045, dated September 26, 1986.
The scope of this item has been expanded to include corrective action implementation for SDAR(s) CP-86-77, " Instrument Tubing Minimum Wall Thickness," CP-86-70, " Elevated Temperature Effects on Instrument Supports and Tubing," and CP-86-16, " Fire Effects on Instrumentation Tubing," all of which have been reported under the provisions of 10CFR50.55(e). Corrective action for these deficiencies will be identified and implemented after a comprehensive evaluation is performed of instrument installations.
We will submit our next report no later than March 20, 1987.
l Very truly yours, W
W. G. Counsil GLB/gj c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
20555 4 DIbiSIO% OF TEX AS LTILITIES ELECTRIC LintPA%Y
Log # TXX-6206 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SEYWAY TOWER ese f* ORT,8 OLIVE STREET.12 88. DAI.LAS. TEXAS ?Sapt January 8, 1987
.'##".hR.U'i Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects V. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKETS NOS. 50-445 AND 50-446 LARGE BORE PIPING AND SUPPORTS SDAR: CP-86-36 (INTERIM REPORT)
Dear Mr. Johnson:
On June 9,1986, we verbally notified you of a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program (see TXX-4844). This is a follow-up interim report on a reportable item under provisions of 10CFR50.55(e). Our latest interim report logged TXX-6117 was l
submitted on November 25, 1986.
' The continuing engineering evaluation has not identified any additional instances which are considered reportable pursuant to 10CFR50.55(e). The attached list shows the support modifications issued to date. The evaluation is continuing and we anticipate submitting our next report by February 20, 1987.
Very truly you's, r
ncjl[
1 l
W. G. Counsil f/ l/
'./
BY:
G. S. Keeley Manager, Nuclear ing BSD/amb Attachment c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
~
U. S. Nuclear Regulatory Commission -
l Washington, D.C. 20555 1
A Dt%1SION OF TEXAS LTELETTES ELECTRIC COhiPANY I
l
TXX-6206 January 8, 1987 Attachment I
Page 1 of 1 ATTACHMENT LARGE BORE PIPE SUPPORT MODIFICATIONS Number of Mail Cateoory Modifications
- 1 Prudent 862 Recent Industry Practice 1303 Adjustment 655 Cumulative Effects 853 2
Prudent 1265 Recent Industry Practice 286 Adjustment 184 Cumulative Effects 474 Changes in these figures from the last report represent not only identification of further modifications but a reclassification and/or recategorization of certain supports.
Reductions in these figures from the previous report are due in part to the removal of some small bore pipe support modifications which were inadvertantly included in the previous report.
9 e
W L.
Log # TXX-6227 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY January 26, 1987 7.'M"aff.Uli Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 APPLICATION OF NON-QUALIFIED AGASTAT RELAYS SDAR: CP-86-40 (INTERIM REPORT)
Dear Mr. Johnson:
On October 10, 1986, we notified you by our letter logged TXX-6017 of a deficiency involving the procurement and use of non-qualified Agastat relays in several Class IE applications which we deemed reportable under the provisions of 10CFR50.55(e). This is an interim report submitted to status corrective action implemented to date.
The identification of non-qualified relays by document review and inspection is continuing. Additional corrective action steps will be established upon completion of these reviews and inspections.
We anticipate submitting our next report by March 6, 1987.
Very truly yours,
/
/
f jWJ/
W. G. Counsil WJH/dl c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
20555 A Dl%ESION OF TEXAS LTILITIES ELECTRIC CostPA%Y
~
Log # TXX-6238 File # 10110 903.9 Re: 10CFR50.55(e)
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1UELECTRIC January 27, 1987 tmusa,au nu, U. S. Nuclear Regulatory Commission ATTN: Document Control Desk hshington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 ANCHOR BOLTS SUPPLIED BY HILTI SDAR: CP-86-51 (INTERIM REPORT)
Gentlemen:
On July 17, 1986, we verbally notified your Mr. Ian Barnes of 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. This is an interim report of a potentially
~
reportable item under the provisions of 10CFR50.55(e). Our most recent interim report was logged TXX-6093, dated November 14, 1986.
Our evaluation of this issue to date indicates that a comparison of the revised allowable loads with those used for design and the associated safety factors will provide adequate justification for our position that reevaluation of the existing work and revision to the appropriate technical documents is not required.
We expect to submit our next report by March 20, 1987.
l l
Very truly yours, (W
W. G. Counsil By:
G. S. Keeley
/
u Manager, Nuclear Licensing l
s/
I GLB/dl c - Mr. Eric H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV l
l 400 North Olise Street t..H 81 Dallas. Tesas 75201 l
Log #TXX-6177 File #10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. ess NORT96 OLIVE STREEF. l.5. St. DAIM TEXA5 78301 December 19, 1986
.T.'c'#". iff.U*i Mr. Eric H. Johnson.. Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 POLAR CRANE SUPPORT STRUCTURE SDAR: CP86-62 (INTERIM REPORT)
Dear Mr. Johnson:
On October 3,1986, we notified you by our letter logged TXX-6011 of a deficiency involving a misinterpretation of the polar crane load cases which we deemed reportable under the provisions of 10CFR50.55(e).
This is an interim report submitted to status corrective action implemented to date'.
In our last report, we established corrective action which included the issuance of design changes to provide for weld modifications at the girder seat and re-placing existing rail clips with stronger clips. Upon further review, however, we have concluded that reduced loading exists and that this load reduction could negate the need for replacement of the crane rail hold down clips. We are now initiating an analysis of the rail and clips for these reduced loads.
Additional corrective action steps will be established depending on the results of this analysis to evaluate the adequacy of the existing condition. These activities should be completed by January 5, 1987.
We anticipate submitting our next report no later than January 26, 1987.
Very truly yours, W. G. Counsil By:
G. 5. Keeley Manager, Nuclea icensing RWH/mlh c - NRC Region IV (0 + 1 copy)
~
Director, Inspection & Enforcement (15 copies)
A DiVESFON Of TEXAS L*TELETTES ELECTEX MANY l
Log # TXX-6208 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY January 21, 1987 7.MlL"dJf.U!L Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-446 UNCONSOLIDATED CONCRETE - UNIT 2 RCB EXTERIOR WALL SDAR:
CP-86-65 (INTERIM REPORT)
Dear Mr. Johnson:
On September 15, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving unconsolidated concrete in the exterior wall of CPSES Unit 2 Reactor Containment Building. Our latest interim report was logged TXX-6167, dated December 17, 1986. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e).
Preliminary evaluations indicate that in the event this issue had remained undetected, no condition adverse to the safety of plant operations should exist.
Documentation supporting our position is currently in the final stages of review and is scheduled for completion on February 13, 1987. We will submit our final report no later than March 13, 1987.
Very truly yours, l'N W. G. Counsil JCH/esr c - NRC Region IV (0 + 1 copy)
Director, Inspection and Enforcement (15 copies)
~
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 A DIVESIO% OF TEXAS LTILITIES ELECTRIC C0%f94%Y
100 # TXX-6187 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. 4se NORTH OLIVE STREET. LB. 88. DALLAS. TEXAS 75301 December 19, 1986
.2l^".h&.UUL Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKETS NOS. 50-445 AND 50-446 PRE-0PERATIONAL VIBRATIONAL TEST CRITERIA SDAR:
CP-86-67 (INTERIM REPORT)
Dear Mr. Johnson:
On September 26, 1986, we verbally notified your Mr. Ian Barnes of a potential deficiency regarding the design calculations and tests used to qualify the Pre-operational Piping Vibration Program.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
We have subm;tted an interim report logged TXX-6~072 dated October 27, 1986.
We are continuing our evaluation of this issue and anticipate submitting our next report by February 19, 1987.
Very truly yours, w. c. cA W. G. Counsil By:
. b>-
l
~
J.6W. Beck l
Vice President Nuclear Engineering BSD/amb c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DnTSION OF TEXAS LTELITIES ELECTRIC COMPANY
Log # TXX-6226 File # 10110 908.3 TEX.AS UTILITIES GENERATING COMPANY SKYWAY TOwEA. 400 NORTH OLIVE STREET. LB. 88. DALLAS. TEXAS 75308 January 21, 1987
."#c%"de#.U!L Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects V. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 WEATHER PROTECTION FOR CLASS 1E COMPONENTS SDAR: CP-86-68 (INTERIM REPORT)
Dear Mr. Johnson:
On October 2,1986, we verbally notified your Mr. Ian Barnes of a deficiency regarding provisions for weather protection of Class IE components used in outdoor installations.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
We have submitted interim reports logged TXX-6081 and TXX-6124 dated October 31, 1986, and November 26, 1986, respectively.
A field verification program is currently being developed to inspect weather proofing on all outdoor Class IE junction / terminal boxes. The results of these efforts are required prior to our assessment of the possible effects of this issue on the safety of plant operations. Where deficiencies are identified, deficiency and nonconformance reports will be issued.
We anticipate submitting our next report by May 15, 1987.
Very truly yours,
!70G W. G. Counsil JCH/mlh c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
20555 A DistSION OF TEXAS LTILITIES ELECTRIC CO%tPAhY
Log # TXX-6225 File # 10110 909.1 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. 400 NORTH OLIVE STREET. L B 88. DAI.AAS. TEXAS 75301 l
January 21, 1987 T.'#1".hff.U h Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects V. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-416 SUPPORT OF CLASS IE WIRING SDAR: CP-86-69 (INTERIM REPORT)
Dear Mr. Johnson:
On October 2,1986, we verbally notified your Mr. I. Barnes of a deficiency regarding the failure to incorporate specific restraining / support requirements defined by IEEE Standard 420-1973, " Class IE Control Switchboards," into project specifications and procedures. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Preliminary evaluations indicate that in the event these conditions had remained uncorrected no condition adverse to the safety of plant operations should exist. Documentation supporting our position is currently in the final stages of review and is scheduled for completion on February 13, 1987.
Our next report will be submitted no later than March 13, 1987.
Very truly yours,
'Id $ X W. G. Counsil DAR:lw c - NRC Region IV (0 + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 A DIVl5 DON OF TEXA5 LTELETIES ELECTRIC CO6tPANY
Log #TXX-6220 File # 10010 903.11 TEXAS UTILITIES GENERATING COMPANY EMYWAY TOWER. 400 NORTH OLIVE ETREET. LB. 88. DALLAS. TEXA5 75201 Uh'O SB.UM, January 16, 1987 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) 1)DCKET NOS. 50-445 AND 50-446 El.U ATED TEMPERATURE EFFECTS ON INSTRUMENT SUPPORTS AND TUBING SDAR: CP-86-70 (FINAL REPORT)
Dear Mr. Johnson:
On October 2,1986, we verbally notified your Mr. I. Barnes of a potential deficiency regarding elevated temperature effects on instrument supports and tubing. Our latest report was logged TXX-6067 and was submitted October 29, 1986. We are reporting this issue unde the provisions of 10CFR50.55(e) and the' required information follows.
Description i
A design assessment review has identified a concern relating to the maximum design operating temperature of instrument supports and tubing. All tubing ir currently being designed and instailed using a maximum operating temperature i
criteria of 122 degrees F.
Instrument supports and tubing could be exposed to temperatures in excess of 300 degrees F during certain accident scenarios (HELB or LOCA).
Safety Imolications In the event the deficiency had remained undetected, the integrity of the instrumentation tubing could not be assured during accident conditions.
A DEUSION OF TEXAS L71LETIES ELECTRIC COAtrANY l
TXX-6220 January 16, 1987 Pagt 2 of 2 Corrective Action Upon completion of the evaluation of existing installations, modifications will be implemented as required to alleviate unacceptable conditions. The status of modifications will be reported under 10CFR50.55(e) via SDAR CP 19.
Very truly yours, v'T4 W. G. Counsil
~.,
JDS/est c - NRC Region IV (0 + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 N
L.,,,...
Leg # TXX-6207 File # 10110-903.9 g
TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. 400 NORTH OLIVE STREET. L.B. 85. DALLAS. TEXAS 75201 January 9, 1987
- M0 hff.U*L Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKETS NOS. 50-445 AND 50-446 SMALL BORE PIPING AND SUPPORTS SDAR: CP-86-72 (INTERIM REPORT)
Dear Mr. Johnson:
On June 9,1986, we verbally notified you of a reportable item involving th~e scope of plant modifications resulting from the project's pipe support reverification program (see TXX-4844). This is a follow-up interim report on a reportable item under provisions of 10CFR50.55(e). We have submitted interim reports logged TXX-6042 and TXX-6120 dated October 15, 1986, and November 25, 1986, respectively.
The continuing engineering evaluation has not identified any additional instances which are considered reportable pursuant to 10CFR50.55(e).
The attached list shows the support modifications issued to date. The evaluation is continuing and we anticipate submitting our next report by February 20, 1987.
Very truly yours, (fl W. G. Counsil l
BSD/amb Attachment l
c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear. Regulatory Commission Washington, D.C. 20555 l
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l A mvusion or reus vriuruzs rucraic courav I
TXX-6207 January 9, 1987 Attachment Page 1 of I ATTACHMENT SMALL BORE PIPE SUPPORT MODIFICATIONS Number of Unit Catecory Modifications
- 1 Prudent 14 Recent Industry Practice 21 Adjustment 187 Cumulative Effects 80
'2 Prudent 8
Recent Industry Practice 18 Adjustment 13
~
Cumulative Effects 77
- Changes in these figures from the last report represent not only identification of further modifications but a reclassification and/or recategorization of certain supports.
W"e
Log # TXX-6188 File # 10010 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. 400 NORTH OLIVE STREET, L.B. 88. DAM TEXAS 783D1 December 23, 1986 I
wtLLIAM G. COUNSIL Mr. Eric H.-Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 l
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 ASME SNUBBER ATTACHMENT BRACKETS SDAR: CP-86-73 (INTERIM REPORT)
Dear Mr. Johnson:
On October 20, 1986, we verbally notified your Mr. Ian Barnes of a deficiency involving installation of ASME snubber attachment brackets. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).. We have submitted a previous interim report logged TXX-6104 dated November 19, 1986.
Our last report identified 165 snubbers that required additional field checks to determine the adequacy of swing clearances.. There are nine supports
.i remaining to be checked.
Information provided by the field checks will be evaluated to identify snubbers with restricted movement. Any snubbers so identified will require further evaluation involving input from the snubber manufacturer, pipe support l
engineering, and the pipe stress analyst prior to final disposition.
Our evaluation of reportability pursuant to 10CFR50.55(e) is dependent on the results of these evaluations. We anticipate submitting our next report by March 6, 1987.
Very truly ours, W. G. C'ounsil l
l By:
G. S. Keeley e
/
l Manager,Nucleap/ Licensing JCH/gj c - Region IV (Original + 1 copy) l Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 l
A omsson or rxxAS LTILMES ELECTRDC COMPANY
Log # TXX-6228 File 0 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER e 400 NORTH OLIVE STREET. LB 51. DALLAS. TEXAS 75301 January 21, 1987 0.0".hff.UE Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects V. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKETS NOS. 50-445 AND 50-446 INSTRUMENT TUBING MINIMUM WALL THICKNESS SDAR:
CP-86-77 (FINAL REPORT)
Dear Mr. Johnson:
On October 21, 1986, we verbally notified your Mr. Ian Barnes of a deficiency involving specification of minimum wall thickness in instrument tubing which may not meet the stress allowables required by the ASME B&PV Code,Section III. Our latest report was logged TXX-6103 dated November 19, 1986.
We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.
Description A review of DCA 13346 to specification 2323-MS-625, " Instrument Tubing and Fittings", and construction procedure ICP-4, " Instrument Tubing Installation and Inspection" has identified a concern in that 0.035 inch wall thickness was approved for use in all instrument tubing sizes.
For certain size tubing in high temperature and pressure reactor coolant applications, this wall thickness may be insufficient to meet ASME Code stress allowables.
Safety Imolications In the event the deficiency had remained undetected, the integrity of the instrumentation tubing could not be assured during accident conditions.
Corrective Action Upon completion of the evaluation of existing installations, modifications will be implemented as required to alleviate all unacceptable conditions. The status of any modifications will be reported under provisions of 10CFR50.55(e) via SDAR CP-86-19.
Very truly yours, Of%:
W. G. Counsil BSD/amb 4 DIVISION OF TEXA5 LTILITIES ELECTRIC ConIPAW
Log # TXX-6253 File # 10110 908.3 Re:
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1UELECTRIC
%ilham G. ( oumil im urne i a e Premlem U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 OVER-TORQUED WESTINGHOUSE AR RELAYS SDAR: CP-86-79 (INTERIM REPORT)
Gentlemen:
On November 7,1986, we verbally notified your Mr. T. Westerman of a deficiency involving the possible overtightening of the contact cartridge terminal screws on the Westinghouse AR Relays. This is an interim report of a potentially reportable' item under the provisions of 10CFR50.55(e). We submitted an interim report on December 5,1986, logged TXX-6141.
Specifically, overtightening of the screws could possibly result in deformation of the stationary contact assembly, reducing contact overtravel, which may result in loss of contact continuity.
Currently, efforts to secure confirmation of relay operability from the vendor is in process. We are proceeding with the identification of the affected components while our assessment of impact of the deficiency on the safety of plant operations continues.
These efforts are scheduled for completion on March 9, 1987.
We anticipate submitting our next report by March 30, 1987.
Very truly yours, h<
nJb(.
W. G. Counsil
/
By:
G. S. Keeley
/
Manager, Nuc sing RDD/dl c - Mr. Eric H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 400 North Ohve Street I.11 MI Dalla. Tean 75201
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Log # TXX-6201 File # 10110 TEXAS UTILITIES GENERATING COMPANY 903.9 y
bKYWAY TOWER. ene PdORTH OLIVE ETREET, t_B. 88. DALLAS. TEXAS 7520I January 6, 1987
- W#MJf.UE Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 CABLE TRAY HANGER SPLICE WELDS SDAR:
CP-86-82 (INTERIM REPORT)
Dear Mr. Johnson:
On December 8,1986,- we verbally notified your Mr. Ian Barnes of a deficiency involving certain welds which are used to splice cable tray hangers (CTHs) channel sections end-to-end to form posts. We have concluded that this deficiency is reportable under the provisions of 10CFR50.55(e) The required information follows.
DESCRIPTION OF PROBLEM During the as-built program of the Unit 1 CTHs, occasionally welds were used to splice CTHs channel sections end-to-end to form posts.
Visual inspections
.could not confirm that the required full penetration welds have been achieved and that the structural and functional design requirements of the hanger were met. Accordingly, these inaccessible welds have been designated as seal welds in the as-built drawings.
Radiographic examination of a sample of these welds has shown that in every instance, the weld penetration is incomplete and the welds are inadequate to achieve the structural and functional design requirements of the hanger.
The lack of a proper weld at the splice of the channel sections in the CTH posts could result in the failure of the post at that location.
This condition could prevent the hanger from functioning as designed resulting in failure of the hanger and the supported tray (s).
SAFETY IMPLICATION In the event the deficiency had remained uncorrected, the failure of a CTH could affect the functionability of essential electrical cables and result in the inability of the safety related systems to perform as required for safe operation and shutdown of the plant.
6 DIbl%IO% OF Tn A% LTilITII:h ELE C1NIC C0%fP4%1
TXX-6201 January 6, 1987 6
Page 2 of 2 CORRECTIVE ACTION The CTHs of both units have been subjected to an as-built program. The CTHs without thermolag have been. visually examined and the locations where this condition has occurred are noted on the as-built drawings.
Each condition will be repaired in accordance with established project procedures.
To determine where splice welds may exist in Unit 1 CTHs which are covered with fire protection material (thermolag, thermoblanket), the as-built CTH drawings will be reviewed and those having full or partial fire protection will be identified. CTHs will be checked in cases where the absence or presence of a splice can be identified without the removal of fire protection material. Other CTHs will have fire protection material removed to the extent required to confirm the presence or absence of a splice. CTHs with identified splices will be repaired in accordance with established site procedures.
We anticipate submitting our next report no later than April 3,1987.
Very truly yours,
/(.Y, tmuk W. G. Counsil, jf By: d
, E(I M G. S. Keeley e
/ --
Manager, Nuclear J/icensing DAR/grr c - U. S. Region IV (0 + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
20555 f
i e
O 4
TEXAS UTILITIES GENERATING COMPANY Log # TXX-6195 SKYWAY TOWER. m P90RM OMYE WFREFF.1.B. 88. DAM.AS. MXA8 MMI File # 10110 908.3 EN#"dJUS January 5, 1987 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SEPARATION BARRIER MATERIAL ON POWER CABLES AND POWER RACEWAYS SDAR: CP-86-83 (INTERIM REPORT)
Dear Mr. Johnson:
On December 8,1986, we verbally notified your Mr. Ian Barnes of a deficiency involving the use of Separation Barrier Material (SBM) on power cables and power raceways. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
CPSES design requirements do not normally allow the use of B&B "PROMATEC" fire barrier wrap system on power cables and raceways, since a large cable ampacity derating factor is required when this material is applied.
Inadvertently, this material has been applied to perform as an electrical separation barrier for power cables and raceways without proper cable ampacity derating. The locations with these conditions have been documented by a Non-conformance Report (NCR). Degradation of the cable insulation could have occurred if the cables were operated in excess of the wrap derated cable ampacity during the CPSES test program.
Currently, we are evaluating the possibility that the conductor temperature of some power cables may have exceeded the insulation temperature rating. Our preliminary assessment indicates that significant inherent conservatism in i
cable sizing design may offset the significant ampacity derating associated with the use of this barrier material.
Our preliminary evaluation is currently scheduled for completion by January 16, 1987.
A DEVESION OF TEXAS LTEUTIES ELECTRIC CO%IPANY
.e TXX-6195 January 5, 1987 Page 2 Our next report on this issue will be submitted by February 13, 1987.
Very truly yours, "A
W. G. Counsil WJH/grr c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i
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