ML20207C553

Forwards Potential 10CFR50.55(e) Items (Significant Deficiency Analysis Repts) Received Since ASLB Received design-related Items on 861104.Related Correspondence

ML20207C553
Person / Time
Site:	Comanche Peak
Issue date:	12/23/1986
From:	Ellis J Citizens Association for Sound Energy
To:	Bloch P, Jordan W, Mccollum K Atomic Safety and Licensing Board Panel
References
CON-#486-2008 OL, NUDOCS 8612300172
Download: ML20207C553 (64)

Text

t A S E ==

(CITIZENS ASSN. FOR SOUND ENERGY) 214/9h6-9446 M"9 ;

ffELATED CORHtseoHoEhce. .g gEt 29 P3 '13 j December 23, 1986 '

Administrative Judge Peter B. Bloch Dr. Walter HoF3ordan s,hf U. S. Nuclear Regulatory Commission Carib Terrae W ph,4 Atomic Safety and Licensing Board 552 North Ocean Boulevard Washington, D. C. 20555 Pompano Beach, Florida 33062 l Dr. Kenneth A. McCollom 1107 West Knapp Street Stillwater, Oklahoma 74074

Subject:

In the Matter of Texas Utilities Electric Company, ,e_t, t g.

Request for an Operating License for Comanche Peak Steam Electric Station, Units 1 and 2 Docket Nos. 50-445 and 50-446 0 l-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 11/4/86 with such design-related items. (However, in this instance, we have not attempted to separate out construction from design items.)

We note that Applicants' 12/1/86 Progress Report included some of these items and included more detailed information than in the past; however, we alread'; had copies made of most of the attached prior to the filing of i

Applicants' Report and are including them also. We also thought it might be f helpful for the Board to have individual copies (rather than just a listing) should it desire to work them in with what we have previously provided and keep them in order by SDAR number.

It is our intention to periodically continue to provide these SDAR's unless the Board indicates otherwise.

Respectfully submitted, Nu dr s.At2 &

) Juanita Ellis resident cc: Service List 9612300172 861223 5 PDR ADOCK 0000 O

hk

3 Log # TXX-6165 File # 10110 s 903.10 j TEXAS UTILITIES GENERATING COMPANY DEVWAV TOWER e est rece?M OL8vs 373337. 8.8. et . DALLAa, TestAs festa December 15, 1986

.i l l2M*.LiL4% '

, i

! Mr. Eric H. Johnson Division of Reactor Safety and Projects 4 U. S. Nuclear Regulatory Commission

611 Ryan Plaza Drive, Suite 1000

' Arlington, TX 76011 4

j

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N0. 50-445 AND 50-446 I EQUIPMENT CONOUIT INTERFACE j

SDAR: CP-85-39 (INTERIM REPORT) l

Dear Mr. Johnson:

On September 18, 1985, we verbally notified your Mr. T. F. Westerman of a 4

deficiency involving conduit which was not installed in accordance with design documents. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). Our most recent interim report was logged

TXX 6016, dated August 18, 1986.

j As previously reported, the program to evaluate this condition consists of the l

following three issues:

l 1) Cable slack adequacy.

)

2) Conduit-to equipment interfaces outside the vendor approved entry area.

I 3) Conduit orientation within the vendor approved entry area.

The cable slack adequacy issue utilizes a sampling approach to evaluate as-

built cable slack. The field verification effort is complete and the

engineering evaluation is in progress. l t

i The engineering evaluation is conducted in three stages. Each stage employs a

! more refined evaluation than the previous stage. Stage ! screening involves a

! direct compsrison between the available slack at a transition and the imposed j seismic displacements. For those transition that fail Stage I screening, a '

i Stage II screening is performed. The primary accostance criteria for the ,

i Stage II screening is the allowable tensions for tie various types of cables.

1 This includes evaluating cable loadings on the equipment and/or terminal ends i to assure that the seismic qualification of the equipment is not invalidated.

l If a transition fails the Stage II screening, then field testing of the j transition will be required in Stage !!!. This stage screening acceptance criteria is based on the ability of the transition to accommodate the required l

displacement without exceeding the equipment or cable allowable loads. Based j on the evaluation finding to date, it is not anticipated that any Stage !!!

screening evaluation will have to be performed. The expected completion date for this evaluation is March, 1987.

4 StHaf0N (W TE245 (7fLITIES SESCfWM* (TMfP4W

o e TXX-6165 December 15, 1986 Page 2 of 2 Engineering is proceeding with the evaluation of the conduit-to-equipment interface issue. Various types of equipment have conduit entry locations which do not conform to the design documents. The completion date will be established pending the receipt of vendor information required to evaluate these entry lacations.

As stated previously, engineering's evaluation of the conduit orientation problems within vendor approved entry inreas has found no evidence to indicate that conditions adverse to quality exist.

We anticipate submitting our next report by February 12, 1987.

Very truly yours,

[

G. 5. Keeley & I-Manager, Nuclear Lipnsing RSB/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Log # TXX-6179 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SKYWAY Towga 4se NORTH OLaVE ETRErf. B.S. 88 . DAL. LAB. TEXA5 76381 December 18, 1986 T.M*".Lff.Unh 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  ;

IMPACT OF HELB TEMPERATURES ON QUALIFIED EQUIPMENT OUTSIDE CONTAINMENT '

SDAR: CP-84-12 (INTERIM REPORT)

Dear Mr. Johnson:

On June 4,1984, we verbally notified your Mr. D. Hunnicutt of a deficiency involving the environmental qualification of equipment outside containment for high energy line breaks (HELB). This is an interim report of a potentially reportable item under provisions of 10CFR50.55(e). Our most recent interim report was logged TXX-6045, dated October 21, 1986.

As noted in our last interim report, the remaining qualification issue involves cable temperatures in the area of concern. A preliminary analysis has inoicated that the cable sheath temperatures in the main steam penetration area exceed the temperature to which the cables were qualified. Currently, engineering is in the process of identifying the affected cables, their function, and resolution of this issue.

An assessment of reportability will be made when the analysis and identification of cables are finalized. Current project scheduling indicates our evaluation will be completed by March 3, 1987.

We will submit our next report on this issue no later than April 10, 1987.

Very truly yours, h,

W. G. Counsil By: .

G. S. Keeley W Manager, Nuclear Litensing WJH/mlh A UniMo% of TK%As LTillit9A iLSC1NIC C0%CY4W f

.- ~ - . Log

• IXX-6151 File # 10110 908.3 TEXAS UTILITIES GENERATING COMPANY SRYWAY TOWER e ese 780AT,4 OL8vE STharr,8.5. Si e OAM TEXAS 79398 December 15, 1986 U.'s".Lff.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, Texas 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 CABLE TRAY TEE FITTINGS SDAR: CP-85-50 (INTERIM REPORT)

Dear Mr. Johnson:

On December 6,1985, we verbally notified your Mr. H. S. Phillips of a deficiency involving the use of improper welding processes in the manufacturing of cable tray tee fittings which could affect the equipment qualification. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest report, logged TXX-6050, was submitted on October 21, 1986.

The test program outlined in our last interim report was anticipated to be completed in November, 1986. However, this scheduled date has since been postponed. We are presently scheduled to be finished by March 15, 1987. Our assessment of this deficiency on the safety of plant operations in the event the condition had remained undetected is pending evaluation of these test results.

We anticipate submitting our next report on this issue no later than April 28, 1987.

9 Very truly yours, Y){ KY W. G/ usilj By: N.

G. S. Keeley c- fj Manager, Nuclear u pensing RSB/gj c - NRC Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 4 fit,f 9NW OF W445 (TILITIM #f f CTRIC 004fP4W

Log # TXX-6172 File # 10110 908.3 TEXAS UTILITIES GENERATING COMPANY

• SEYWAY TOWSR . 488 P80RT,4 OLIVE STharf,1.3. el . DALLAS. TEXAS 76888 December 18, 1986 7.'.Y1".ifP.Unh Mr. Eric H. Johnson 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 6.9KV SWITCHGEAR BREAKER JACK SHAFT WELD FAILURE SDAR: CP-86-14 (INTERIM REPORT)

Dear Mr. Johnson On March 11, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving a weld failure in a component of a Class 1E 6.9kV switchgear breaker. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest interim report, logged TXX-6033, was submitted on October 20, 1986.

In our previous report, we noted our assessment of this deficiency was contingent upon completion and receipt of the vendor's evaluation which includes design testing. Currently, the breaker manufacturer (Brown Boveri) is continuing evaluation of the established design criteria to verify breaker operability. Our overview of these activities will result in the assessmept of this deficiency regarding the safety of plant operations -

These activities are scheduled for completion by March 15, 1987. We anticipate submitting our next report no later than April 30, 1987.

Very truly yours, Y

W. G. C nsil By: .

m /

G. S. Keeley Manager, Nuclea Licensing i DAR/amb 4 DntfMW OF TERA.9 LTILiffLT FlfCTRfC C(MfP44)

Log # TXX-6175 File # 10110 909.4 TEXAS UTILITIES GENERATING COMPANY DmYWAY TOWSR . des NORT,6 OLIVE STRSET. l.5. 88 . DALLAS. TEMAS 76308 December 18, 1986

• '#3".h N.U h 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 SAFETY CHILLED WATER CHILLER UNITS SDAR: CP-86-18 (INTERIM REPORT)

Dear Mr. Johnson:

On May 21, 1986, we notified you that the issue involving difficulties in starting and operating the safety chilled water chiller units was reportable under the provisions of 10CFR50.55(e). This issue identifies the failure of the Component Cooling Water (CCW) supply to maintain its temperatures at or above the chilled water return temperature for both the operating and standby chillers. We have submitted interim reports logged TXX-4875. TXX-4934, and TXX-50*7 dated June 26, 1986, July 24, 1986, and September 17, 1986, respectively. On December 17, 1986 we verbally received an extension for submitting this response to December 19, 1986.

Currently, we are continuing detailed review of vendor specifications and updating the list of components serviced by the component cooling water system. The supplier (York) is also continuing the evaluation of the installation of the chiller flow control valves with regard to a standby, non-operating safety chiller. Westinghouse is also continuing to evaluate the impact of the 400F CCW temperature on NSSS components.

We anticipate completing the evaluations by February 16, 1987, and submitting our next report by March 9, 1987.

Very truly yours, (7

/ M G. S. Keeley - /

Manager, Nuclear' jLicensing GLD/amb A bibl% ION UV 1 MAS t*19811892 OlS t'INIC ( UslP4 % Y

_-... l 1 Log # TXX 6166 File # 10110 1 908.3

TEXAS UTILITIES GENERATING COMPANY SEVWAY TOWBA e ens NORTH 001%E STRLrf,8.5. 88 e DALLAS. TEMA4 76494 December 16, 1986 f#Mf.tf..Unh Mr. Eric H. Johnson 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 NO. 50-445 ANO 50-446 TRACEABILITY OF lE PIGTAIL EXTENSIONS SDAR: CP 86-38 (INTERIM REPORT)

Dear Mr. Johnson:

On May 27, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the failure of project procedures to adequately address the installation and inspection criteria for cable runs used as device pigtail extensions. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). Our last interim report logged was TXX 5010, dated Septembwr 12, 1986.

The field verification effort to obtain cable and splice data noted in our previous report is currently underway. As-built data obtained from this effort is under evaluation in preparation of an assessment of the impact of this issue on the safety of plant operations.

We anticipate submitting our next report by February 4, 1987.

Very truly yours, l

W. G. Co il - .

By: ._. M G. S. Keeley Manager, Nuclear Licensing RSB/amb c - NRC Region IV (0 + 1 copy)

Director, inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 3

4 f)f t f9N)4 f)F TR243 477f.lff8J 8&FC72fC Cl)4f744F

Log # TXX 6168 File # 10110 903.7 TEXAS UTILITIES GENERATING COMPANY SSYWAY TOwee . 480,eOSTM OLIVE WfSSWT. LS. On . DARJ.AS, TEMAS 708D8 December 18, 1986 wituAM e. couwell Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission f

611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 '

ORIGINAL DESIGN OF CONTROL ROOM CEILING SDAR: CP-86 54 (INTERIM REPORT)

Dear Mr. Johnson:

On October 3, 1986, we notified you of a reportable item involving the design and installation of the control room ceiling (see TXX-6007). We have submitted a follow up interim report logged TXX-6091, dated November 14, 1986.

This is a follow up interim report on a reportable item under the provisions of 10CFR50.55(e) and is provided to status the implementation of corrective actions. -

Quality control verification of construction activities concerning the control -

room ceiling will be complete upon closure of outstanding inspection findings.

These activities are tentatively scheduled for completion by January 30, 1987.

Our next status report on this issue will be submitted no latnr than February 20, 1987.

Very truly yours, W. G. Counsil By:

• l G. S. Keeley - '-

Manager,NuclearLIMsing JCH/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

, A Dist9Nm 09 TEMAS L'11811IR.E SLEC1RIC CUhW4MV

o Lo'g # IXX 6181 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SFYW AY TOWSA e 4 9 NOST,0 OLIVE STSSWF. l.SL se e DALLAS. TRAAS 768DI December 18, 1986

!!.YJ^f.!JEUh 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 GIRDER AND GIRDER SUPPORT SHIM GAPS SDAR: CP-86-60 (INTERIM REPORT)

Dear Mr. Johnson:

On September 4, 1986 we verbally notified your Mr. I. Barnes of a deficiency involving gaps between the polar crane girder and the girder support brackets.

This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest interim report was logged TXX 6009 dated October 3, 1986. On December 17, 1986, we verbally received an extension for submitting this response to December 19, 1986.

Preliminary review results indicate this issue is not reportable.

Calculations supporting our position are currently undergoing final review.

These :-forts are scheduled to be completed by January 28, 1987. We anticipate submitting our final report no later than February 15, 1987.

Very truly yours, bY Msb W. G. Counsil By: / /

G. S. Keeley - '

Manager,NuclearL[ensing RWH/mlh c NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 l

t 4 cenen,* pr tsau (Trursu es actasc ro*er4*r l

Log # TXX-6167 File

• 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 PsORTM UL8WE STREET. LA, al DALLA 5. TEMAS 75308 December 17, 1986

.,#W.hM.U!n, Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. fluclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMAflCHE PEAK STEAM ELECTRIC STAT 10ft (CPSES)

DOCKET fl0. 50 446 UtlC0flSOLIDATED C0flCRETE - Uti1T 2 RCD EXTERIOR WALL SDAR: CP 86 65 (IllTERIM REPORT)

Dear Mr. Johnson:

On September 15, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving unconsolidat,d concrete in the exterior wall of CPSES Unit 2 Reactor Containment Buildit% We have submitted an interim report logged TXX 6024, dated October 15,*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 would exist. Documentation supporting our position is currently in the final st.gos of review. We anticipate submitting our final report no later than January 23, 1987.

c. Very truly yours, W. G. Counsil hk

// /

By:'G. S. Keeley /

Manager, fluele consing JDS/mlh c - flRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S,fluclear Regulatory Commission Washington, D.C. 20555 4 ,,,is ,m or is n, erre errn es erenic ro 4, ,, ry

Log # TXX-6171 1 -

File # 10110 908.1 TEXAS UTILITIES GENERATING COMPANY tEYWAY TOWSS e ese #4087,8 OLiv B Staggr, 4.5. 8, e D48. LAG. TEXAS tem, December 18, 1986

..'.'C,?. LUE*L Mr. Eric H. Johnson 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 SUPPORT OF CLASS lE 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). Our latest interim report, logged TXX 6066, was submitted on October 28, 1986.

Preliminary evaluations indicate that in the event these conditions had -

remained uncorrected no condition adverse to the safety of plant operations would exist. Documentation supporting our position is currently in the final stages of review.

We anticipate submitting our final report no later than January 23, 1987.

Very truly yours, W.G.C si By: , . / (f N G. S. Keeley Manager,NuclearLTeensing DAR/amb c NRC Region IV (0 + 1 copy)

Director, inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A NtteNDM 0918140 Vitt1186.9 SLStintC CCH094Nt'

Log # TXX 6176 File # 10110 908.3 TEXAS UTILITIES GENERATING COMPANY December 19, 1986

.i. % ". L ffd h l Mr. Eric H. Johnson, Director Olvision of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 l Arlington, Texas 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50 445 AND 50 446 ROCKWELL TERMINAL BOXES l SDAR: CP8674(INTERIMREPORT) l l

Dear Mr. Johnson:

l On October 21,'1986, we verbally notified your Mr. Ian Barnes of a deficiency I regarding internal wiring discrepancies and rusty close nipples and fittings in terminal boxes for Unit 2 main steam isolation valves supplied by Rockwell.

Our preliminary evaluation indicates this deficiency potentially effects Units 1 and 2. This is an interim report of a potentially reportable item under the provisionsof10CFR50.55(e). We have submitted an interim report logged TXX-6084, dated November 17, 1986.

l Currently, we are reviewing the applicable nonconformance reports and performing a field verification of the affected terminal boxes, conduit fittings and the internal wiring to ascertain the significance of this issue in the event the condition had remained undetected. Our assessment will be determined pending completion of the document review and field verification of l affected hardware. These efforts are currently scheduled for completion on March 4, 1987.

We will submit our next report on this issue no later than April 10, 1987.

Very truly yours,

%I l

L , / 4/

5. Keeley A 4 Manager, Nuclea teensing WJH/amb c Region IV (Original + 1 copy)

Director,inspectionandEnforcement(15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 s u,nnom ur nsse n un nu s oucunuc umem

~

Lo$e#TXX-6132 Fi # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY DETWAV TOWBA e eED P.(HBf H OLIVR STREET. LB. el e DALLAS. TEMAS 768DB December 3, 1986 f.'.W. L#.UM.

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

COMANCHEPEAKSTEAMELECTRICSTATION(CPSES)

DOCKET NOS. 50-445 UPPER LATERAL RESTRAINT EMBEDMENT DESIGN SDAR: CP 85 26 (FINAL REPORT)

Dear Mr. Johnson:

On July 19, 1985, we verbally notified your Mr. D. Powell of a deficiency regarding the Unit I steam generator upper lateral restraint embedment design.

This is a final report of a potentially reportable item under the provisions of10CFR50.55(e). Our last interim report was logged TXX 6063, dated October 27, 1986.

The deficiency involves the design / analysis of the steam generator upper lateral (SGUL) beam anchorage. Specifically, the beam end movement contribution to embedmont pullout forces was omitted, and an unjustified assumption, that the mobilization of shear friction would resist embedment pullout stresses, was used in the analysis.

Evaluations were performed for LOCA loading under a design bounding assumption where the steam generator compartment platforms are considered removed (resulting in higher 3ressures in the upper portion of the compartment). From these evaluations it 1as been concluded that the pullout stresses in the SGUL beam end anchorage at the 45 degree wall will exceed the ACI allowable when the higher pressure loads are considered. However, local overstress during a LOCA condition is permitted when there is no loss of function of any safety related system (see FSAR Section 3.8.4.3.2). Confirmatory calculations were performed to demonstrate that the SCUL beam and concrete structure to which it is connected would perform their required function (i.e. support the steam generator during the LOCA). Furthermore, the above evaluation was in progress before General Design Criterion (GDC) 4 was modified by rulemaking as published in the Federal Register (April 11,1986). This rule allows the exclusion from the design basis, of the dynamic effects associated with the rupture of primary coolant loop piping. Had this rule been applied to the above analysis, peak LOCA forces would be reduced to approximately one half.

The values used in this analysis and the SGUL beam embodment stresses would be reduced accordingly.

. < wnom no sm nunun sunnonwrem

i TXX-6132  ;

December 3, 1986 '

Page 2 of 2 i

We have concluded that in the event this issue had remained undetected, no  ;

condition adverse to safety would exist. This issue is not reportable under the provisions of 10CFR50.55(e). Records supporting this conclusion are available for your inspector s review at the CPSES project site.

Very truly yours, '

l wake W. G. Counsil By: , .

G. 5. Keeley M'

Manager, Nuclear Li nsing_

BSD/amb j c - NRC Region IV (0 + 1 copy) -

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 >

l ,

f t

i i

i

Log # TXXo6138 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY

.. , , . om ouv meer. u ei . 04u.4 me. v December 5, 1986

"##". *JMh 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 NO. 50 445 l

ELECTRICAL RACEWAY SUPPORT SYSTEM SDAR: CP-85-31 (INTERIM REPORT) l

Dear Mr. Johnson:

On August 27, 1985, we verbally notified your Mr. D. Hunnicutt of a deficiency involving the Unit 1 Electrical Raceway Support System. Specifically, due to additional weight imposed by the installation of Separation Barrier Material (58M) and Radiant Energy Shield (RES) Material without a complete interdisciplinary review and destgn analysis, the structural integrity-of the raceway is indeterminate. As noted in our previous report (TXX 6030, dated October 20,1986), the impact of weights imposed by SBN on Unit 1 Cable Tray Hanger (CTH) Systems is being evaluated as part of the overall CTH design verification activities addressed by SDAR CP 85 35, Cable Tray Hanger Design.

Wearereportingthisissueundertheprovisionsof10CFR50.55(e)andthe required information follows.

DESCRIPTION SBN and RES Material have been installed on Class 1E Electrical Raceways consistent with FSAR and Regulatory Guide 1.75, Revision 1 " Criteria for the Separation of Redundant Class 1E Equipment and Circuits." Preliminary engineering evaluations prior to SBN and RES Material installation did not include analysis to verify that the additional weight imposed by these materials would not adversely affect the conduit support system. Subsequent engineering evaluations have resulted in the identification of conduit and conduit support installations which would. fall under accident conditions due to overload conditions. Specifically, from a total population of seventeen (17) conduit runs and eight (8) junction boxes, three (3) conduit runs and thirty fivo (35) conduit supports were overstressed.

This issue is applicable to Unit 1 electrical raceway systems only.

(

4 infifWt99 f)F 78445 ("fff fffM Flarf alt'i t)4fP4W

.. O' TXX-4138

• December 5, 1906 Page 2 of 2 Although this concern is not a specific CPRT Program Plan Item, the evaluation and disposition of this issue is being formulated by Ebasco in the course of the Civil / Structural Design Verificat' on Program outilned in CPRT Program Plan Item DSAP VIII. This planned design verification activity is being subjected to third party overview to assure resolution of external source issues and compliance to CPSES licensing commitments.

SAFETY IMPLICATIONS Failure of seismic category conduits and conduit supports to meet the recuired design criteria could result in an inability of associated safety relatec systems to perform as required for safe operation and shutdown.

CGMECTIVI ACTim new The three supports (3)and added conduit runs identified the thirty-five (35) conduit will have supports a totalwiof eleven (11 identified modified. The necessary design chan accordance with approved travelers. ges will be initiated and performed inPh January 1987. The TUGC0 Engineering Design Control Program has been revised to provide for more positive . interface controls. This revised program includes the estabitshing of procedural requirements for interdise'pline engineering analysis to be performed for all proposed changes tests and experiments. Thisprogramwillpreventtheoccurrenceofstellar deficiencies. The identification of additional corrective actions, if required, will be included in our next report.

We anticipate submitting our next report no later than March 10, 1947.

Very truly yours.

W. G. Counsil DAR/amb c NRC Region IV (0 + 1 copy)

Director, U. 5. Nuc lear Regulatory CommissionInspection& Enforcement (15 copies Washington, D. C. 20555

i g Log # TXXo4153 File # 10110 I TEXAS UTILITIES GENERATING COMPAh4Y esTW4V TWWW e e pesette 88.898 cm. La M e DA4AAE Tenee ,est December it, 1986 l l

MM. Ll*.*.**,.

Mr. Eric M. Johnson, Director *l Division of Reactor Safety and Projects  !'

U. 5. Nuclear Regulatory Commission 411 Ryan Plaza Drive, Suite 1000 Arlington, TX 74011 -

j i

SUBJECT:

COMANCHEPEAKSTEAMELECTRICSTATION(CPSES)

• DOCKET NO. 50 445  !

THEM0 LAG ON CONOUlf Supp0RT

'l '

. SDAR: CP0542(INTERIMREPORT)

Dear Mr. Johnson:

On October te, 1906, we notified you (TUSCO Letter TXX 604g) that the  !

deficiency involving the possible adverse effect of the substitution of I rectangular and overstaed preformed sections of therselag on condutt installations is reportable under the provision of 10CFR50.55(e). This is an interim report submitted to status corrective action implemented to date.  ;

An engineering verification was performed, which provided the shape and :1ze o specific conduit dimensions, support location and i of installed thermolag,his configuration. Also, t verificatten effort provided a complete survey of l the original unique IN FP drawings from the 5 0g10 document which comprised  :

32g conduit runs, 141 junction boxes and approximately 1500 conduit supports t (lneluding44UnistrutsupportswhtcharebeingaddressedaspartofSDARCP-  !

5534). i The IN FP drawings have been revised to incorporate the engineering  !

verification information, existing desten changes and inspection reports, i With the uttitaation of the revised IN 4P draw ngs each conduit span had the therselee wetehts conservatively calculated and dynamic system analysts  !

performed. All support leads have been estabitshed, but final evaluation of  !

the adequacy of the supports cannot be performed until the test data on clamp  !

capacity has been fully evaluated. This specific evaluation is being i conducted as a separate isaue. )

l Our present evaluations have estabitshed the following conclusions l conduit runs have been identified as overstressed due to

1) Nine(g)dconditions.

overloade t

I o Four(4)ofthesenine(g runs are overstressed due to the presence of conduit coup 1)tngs at the critical section between supports. ,

t 4 Jettles,88v (8F F9444 L'fN#Ffte 81HTDN' f 784884" f f I

.6 TXX-6153 December 12, 1986

, Page 2 o One (1) conduit run will have the existing thermolag removed and replaced with a smaller size. i o Out of these nine (9) conduit runs eight (8) runs will have a total l j of ten (10) supports added.

2) Fifteen (15) junction box failures were identified.

3) Thirteen (13) conduit support failures were identified by analysis.

o The number of conduit support failures (13) may be reduced as a result of refined analysis that is currently being conducted. Any found to be unacceptable through refined analysis will be modified.

Additional corrective action steps will be established for the remaining identified areas after the Fire Protection analysis of existing conditions to evaluate the adequacy of existing thermolag applications.

. We anticipate submitting our next report no later than April 28, 1987.  !

. Very truly yours, W. G. Counsil By: i G. S. Keele,-

/

Manager,NuclearLp'nsing DAR/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies) .

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

- - ~- t_

~ ~

- " . Log # TXX-6106

~

File H ERO 903.7 TEXAS UTILITIES GENERATING COMPANY ywar w . no.= on.sv. er r. sa. = . - = -4. v =

. November 20, 1986 -

Y $ =^".

• S "S . h .

1 i

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Consission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 '

SEISMIC QUALIFICATION OF HVAC SUPPORTS SDAR: CP-85-54 (INTERIM REPORT)

Dear Mr. Johnson:

On September 26, 1986, we verbally notified you that a deficiency involving ~ '

discrepancies in supplier provided HVAC support documents was resportable under the provisions of 10CFR50.55(e). This is a follow-up interim report to status the implementation of corrective getions for this issue.

The following corrective measures are being implemented to resolve this issue:

1. The Project organization and responsibilities for Unit I and Common HVAC activities have been realigned. Engineering and QC activities previously performed by Bahnson have been assumed by Ebasco and TUGCO, respectively. ,,

2. The field. verification effort has been expanded to encompass all Unit,I and Common Seismic Category 1 duct supports.

Ebasco's progress to date, for this effort, is as follows:

- Collection of existing documents is complete.

l

- Procedure training of walkdown engineers is complete. .,,

- Preliminary walkdown is complete.

- Walkdown and field data collection is in progress and is being j

performed in accordance with TNE Procedure FVM-CS-029 (Field l

Verification Method Procedure for Seismic Duct Hanger As-Built

! Verification in Unit I and Common Areas).

l M As ,

(

A N OF TEXAS t/71LJ73ES $2ECTRfC NANY

TXX-6106 - >

. November 20. 1986 _

Page 2

3. Engineering evaluations will be. performed to ensure compliance with FSAR comunitments. ., .

. 4. _ Constru'ction rework will be performed, as deemed necessary by the engineering ' evaluations of field verified information, to ensure compliance with FSAR criteria for the affected supports.

P

5. To ensure Unit 2 installations comply with prescribed requirements,-

Unit 2 HVAC supports are being field verified. The as-built effort is being conducted b'y Bahnson, with QC verification by TUGCO.

, Ebasco has been given the responsibility for the evaluation of design adequacy.

Unit I activities are scheduled for completion by May 1,'1987. Unit 2 activities are scheduled for completion in the fall of 1987.

We will submit our next report no later than May 22, 1987.

4

, Very truly yours,

~

~

~

Y- { '

i

- W. Counsil l

s. S. Marshall -

~ ~ Supervisor, Generic Licensing RWH/mlh c - NRC Region IV (0 + 1 copy) 3 Director, Inspection & Enforcement (15 copie,s)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 l

l e

e

+

D-

--h

.- -_,_r- _ _ - _ - , . ,-.

Log 0 TXX-6122 File 0 10'10 9G3.9 TEXAS UTILITIES GENERATING COMPANY

$EYWAY TOWEA . 400 NORTH OLIVE STREE'T.1 B. 88 . DALLAS. TEXAS 75301 December 1, 1986 e

"#1".LB.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 INSTALLATION OF SUPER HILTI KWIK BOLTS SDAR: CP-86-08 (INTERIM REPORT)

Dear Mr. Johnson:

On February 6,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the control of stamps used to identify Super Hilti Kwik Bolts. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest interim report, logged TXX-4963, was submitted on August 22, 1986.

As noted in our previous response, the portion of this deficiency which involves ASME installations has been completed without the identification'of conditions adverse to safety. All installations were evaluated and determined to be acceptable "as-is".

For the portion of this issue involving non-ASME applications (such as cable tray supports, structural steel, conduit supports, and electrical equipment installations), our evaluation is continuing. This effort, which consists of ultrasonic testing of a sample of non-ASME installations, must be completed prior to our assessment of the possible adverse effects of this deficiency.

These testing activities are currently scheduled for completion on February 27, 1987.

l We anticipate submitting our next report by March 20, 1987.

Very truly yours, l

l /

. G Zs11o- '

W. G. Counsil GLB/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies) l U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Log # TXX-6137 File # 10110 909.2 ,

TEXAS UTILITIES GENERATING COMPANY ]

SKYWAY TOWER . 400 NORTH OLIVE STREET. L2. O! . DA1J AS, TEXAS 70388 December 5, 1986 I

OS'".hfP.U:n, Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 1

Arlington, TX 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ,

COMPONENT COOLING WATER PUMP IMPELLER LINEAR INDICATIONS SDAR: CP-86-ll (INTERIM REPORT)

Dear Mr. Johnson:

On June 23, 1986, we notified you of a reportable item involving linear indication on impellers for the component cooling water (CCW) pumps (see TXX-4871). This is a follow-up interim report on a reportable item under the provisions of 10CFR50.55(e) and is provided to status the implementation of

! corrective action. Our last interim report was logged TXX-5036, dated October 1, 1986.

Inspections of the Unit 1, Train A, CCW pump impeller have revealed that rework is required and should be completed by December 1986. The Train B impeller will be inspected following the availability of Train A service water (scheduled for December 1986). Upon completion of the inspection, the extent of the required rework will be determined and the repair will be scheduled as required.

The vendor should complete repair of the replacement " spare" impeller by January 1, 1987.

We anticipate submitting our next report by February 6, 1987.

Very truly yours, -

UH W. G. Counsil GLB/amb c - NRC Region IV (0 + 1 copy) i Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A gnyESCON OF TEXAS L7ELETTES ELECTRIC COMPANY

~ ~~

Log # TXX-6108 File # 10110 903.7 TEXAS UTII.lTIES GENERATING COMPANY SKYWAY TOWER 400 NORTH OLIVE STREET. I.B. 88 . DALLAS. TEXAS 75308 November 21, 1986 EWE".hff.Unb 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 COMM0DITY 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-5007, dated September 12, 1986.

Since the last interim report, our approach to evaluate the installed commodities from a generic displacement standpoint has been superseded by the following activities. The secondary wall relative movements will be calculated. After determining this information, the affected engineering contractors will initiate revisions to the applicable design procedures to incorporate the required relative horizontal and vertical movements between secondary walls and adjacent walls / floors. These movements will also be used in the performance of a field verification to identify potentially unacceptable interactions and in the engineering resolution of any unacceptable interactions. The relative movement criteria will be included in an inspection procedure to ensure that the minimum separation is maintained for future installations.

We anticipate submitting our next report by January 23, 1987.

Very truly yours, 74 .

W. G. Counsil JCH/mlh J

c - NRC Region IV (0 + 1 copy) ,,

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEYislaw 0F TEXAS LTELETILS ELECTRIC C0%fPANY

Log 0 TXX-6088 File 0 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SEYWAY TOWER . 400 NORTH OLIVE STREET. I.B. el . DALLAS. TEXAS 75398 November 14, 1986 E's'P.Eff.0%h 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 NO. 50-445 JET IMPINGEMENT LOAD REVIEW SDAR: CP-86-13 (INTERIM REPORT)

Dear Mr. Johnson:

On March 5,1986, we verb' ally notified your Mr. T. F. Westerman of a .

deficiency involving a computer entry error which could invalidate of portions the jet impingement load review for high energy piping. This is an interim i report of a potentially reportable item under the provisions of 10CFR50.55(e).

Our latest interim report, logged TXX-6032, was submitted on October 20, 1986.

We have reviewed all component shape factors, with the exception of four, whose jet loads were calculated using the PIPSCIN jet load program.

Completion of this review is currently scheduled for December 15, 1986. All component shape factors evaluated to date have been verified to be acceptable.

We are continuing our evaluation and anticipate submitting our next report no later than January 21, 1987.

Very truly yours, NEGt W. G. Counsil

.I By:- ' -

G. S. Keeley h /-

Manager, Nuclear Lic(nsing 4

JDS/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A onu,o* or rExAs onunss stscraic cower

Log # TXX-6111 File # 10110 909.5 l TEXAS UTILITIES GENERATING COMPANY I SKYWAY TOWER 488 NORT,8 OLIVE STREET. LB. 48 . DAL.LAS. TEXAS 75301 November 24, 1986 E'c%^".?cN.UUh 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 MINIMUM CONCRETE COVERAGE SDAR: CP-86-17 (INTERIM REPORT)

Dear Mr. Johnson:

On March 21, 1986, 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-5015, dated September 17,-1986.

We ar the process of completing our evaluation and the issue appears to be non-reportable. We anticipate submitting our next report no later than December 23, 1986.

Very truly yours,

, ~

/ $%

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 DitTSION OF TEXAS LTillTIES ELECTRIC COMPANY

g Log # TXX-6158 File # 10110 909.4 6 TEXAS UTILITIES GENERATING COMPANY SEYWAY TOWER . eSD NOftTM OLIVE STREET. I.B. SI . DALLAS. TEXAB M381

, December 12, 1986 WILLIAM G. COUNSIL l

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 SAFEGUARDS AREA FAN COOLERS SDAR: CP-86-22 (INTERIM REPORT)

Dear Mr. Johnson:

On April 2,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the capacity of the present fan cooler design in the

Safeguards area to adequately handle the heat load in several rooms. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4780, TXX-4894,

' and TXX-5008, dated April 30,1986, July 3,1986, and September 12, 1986, respectively.

During a review of Unit 2 preoperational test procedures, a comparison of fan i cooler specifications and drawings identified cooling capacities below the calculated heat loads in the design basis calculation. Test performance data for Unit I coolers may have been accepted at values below both the design heat loads and equipment capacities.

In order to assess the impact of this condition on the safety of plant

operations, an engineering evaluation was undertaken to determine if failure

, of equipment cooling capacities to meet required design criteria could result

in an inability of associated safety-related systems to perform as required following LOCA with loss of offsite power.

I The completed calculations for Unit I have determined that the emergency fan coolers (served by the safety chilled water system) are adequately sized to i maintain the room temperatures, within the FSAR requirements, following a LOCA coincidental with loss of offsite power. However, we have determined that the

- chilled water flow rates require rebalancing.

We are continuing with our evaluation which includes revising the design documents as indicated above. Unit 2 calculations are scheduled for completion by April 30, 1987. Upon completion of the engineering evaluations, an assessment of this issue can be completed.

A DEVESION OF TEXAS LTILITIES ELECTRIC COAIPANY

,.-,e

_.-,m _ . _ , _ _ ._- ,,- ._ -. . - -_. -

--... ,. ,.- ~,- __. _ - _ . . _ , - _ - _ . , _ - .-,.-m_---_ -

TXX-6158 D:ce:b:r 12, 1986 Page 2

~e We anticipate submitting our next report no later than May 20, 1987.

Very truly yours, hh- rnff W. G. Counsil By: .Mi / 4 M$nge sing GLB/gj b_rY" c - Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 1

Log # TXX-6090

-File # 10110 909.5 TEXAS UTILITIES GENERATING COMPANY isMYW AY TOWER . 400 NORTH OLIVE STREET. LB. SB . DALLAS. TEXAS 75203 November 17, 1986 UW37.LB.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 DIESEL GENERATOR LUBE OIL SUMP TANK FOOT VALVES SDAR: CP-86-31 (INTERIM REPORT)

Dear Mr. Johnson:

- On August 22, 1986 we no'thfied you of a reportable item involving the possible failure of the rubber facing on foot valves mounted in the diesel generator lube oil sump tank (see TXX-4975). This is a follow-up interim report on a reportable item under the provisions of 10CFR50.55(e) and is provided to status the implementation of corrective actions.

New Viton liners have been purchased and received at the CPSES. site. Unit I work orders have been issued and installation is expected to be complete by December 5, 1986.

Unit 2 replacement liners are scheduled for installation after lube oil flush of the diesel generator system i ich is tentatively scheduled for completion by March 1, 1987.

We will submit our next status report no later than March 27, 1987.

Very truly yours,

,1 1M W. G. Counsil l

RWH/mlh c - NRC Region IV (0 + 1 copy) i Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i

A Dit'I.%l0% OF TEXAS LTILITIL5 ELECTRIC CO% IPA %Y L

Log # TXX-6105 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SETWAY TOWER e est NORT98 OLIVE STREET.1.5. SI . DALLAS. TEXAS flatt November 2'1, 1986 7.M'". hff.1"2, 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 NO. 50-445 AND 50-446 THRU WALL EMBEDDED CONDUIT SLEEVES SDAR: CP-86-32 (INTERIM REPORT)

Dear *fr. Johnson:

On April 21, 1986, we ver. bally notified your Mr. T. F. Westerman of a deficiency involving thru wall embedded conduit sleeves which have not been --

identified by number and may be overfilled. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4790, TXX-4935, and TXX-5030, dated May 9, 1986, July 24, 1986, and September 19, 1986, respectively.

A field verification procedure (TNE-FVM-EE-023) has been issued to obtain as-built data whereby a technical evaluation of the significance of these conditions can be assessed. The schedule for completing the field verification is April 1,1987. The schedule for completing the technical evaluation will be determined at a later time.

We anticipate submitting our next response by April 24, 1987.

Very truly yours, j L W. G. Counsil RSB/amb l

j c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission.

Washington, D. C. 20555 a onmon or rzxas unuruss utscrnic couranr

Log # TXX-6117 File # 10110

. 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 480 f* ORTH OLIVE STREE"r, LB. 85 e DALLAS. TEXAS 75201 November 25, 1986 E"#1".h*.U,0L 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)

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). We have submitted interim reports logged TXX-4958, TXX-5033 and TXX-6044, dated August 13, 1986, September 26, 1986, and October 17, 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 January 8, 1987.

Very truly yours, L

W. G. Counsil BSD/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington,. D.C. 20555 A DIVES 10% of TE.% AS LTELITIES ELECTRIC ContFAW .

9

s >

TXX-6117 N:verber 25, 1986 Page 1 of 1 ATTACHMENT LARGE BORE PIPE SUPPORT MODIFICATIONS

' Number of Unit Cateaory Modifications

• 1 Prudent 873 Recent Industry Practice 1143 Adjustment 198 Cumulative Effects 705 2 Prudent 1271 Recent Industry Practice 310 Adjustment 186 Cumulative Effects 509 Changes in these figures from the last report represent not only identification 4 of further modifications but a reclassification and/or recategorization of certain supports.

4 L

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k Log # TXX-6169 File # 10110 908.3 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 488 NORTH OLIVE STREET. LB. 88 . DALLAS. TEXAS 75381 December 17, 1986 En%".hfff.ML 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 CLASS IE BATTERY CHARGER COMPONENTS SDAR: CP-86-37 (INTERIM REPORT)

Dear Mr. Johnson:

On May 14, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving firing board assemblies and amplifier boards used in. Class IE battery chargers that do not conform to vendor assembly drawings. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4855, TXX-4914, TXX-4995, and TXX-6023, dated June 13, 1986, July 16, 1986, September 10, 1986, and October 15, 1986, respectively. ,

Our evaluation of this issue ~ includes review of the procurement processes which result in the purchase of non-Class IE parts for Class IE application, and a technical evaluation of the adequacy of the hardware. These efforts are scheduled for completion January 27, 1987. i We are continuing February 13, 1987. our evaluation and anticipate submitting our next report by Very tr ly yours, Y' . 0Y W. G. Counsil By: '

G. S. Keeley fensing Manager, Nucl _ea WJH/gj c - NRC Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

, U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A DEVESNMt OF TEMAS LT1LITEL5 ELECTRIC COh,94W I

Log # TXX-6123 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH OLIVE STREEF.1.B. OS DA11AS. TEXA5 TMDt November 26, 1986 C#35iff.YE, 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 CABLE TRAY C-TYPE CLAMP SHIM DIMENSIONS SDAR: CP-86-39 (INTERIM REPORT)

Dear Mr. Johnson:

On May 27, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving dimensional tolerances of the shims used in conjunction with C-Type clamps on cable trays. This is an interim report of a potentially reportable -

item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4874 and TXX-6056, dated June 26, 1986, and October 21, 1986,

, respectively.

< The testing program described in TXX-6056 has not yet been completed. Our current schedule for completing these tests is January 15, 1987. Our evaluation of the test data and an assessment of the effects of the deficiency on the safety of plant operations are scheduled to be completed by March 31, 1987.

We anticipate submitting our next report by April 21, 1987.

! Very truly yours, f.. i l W. G. Counsil JCH/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission i Washington, D.C. 20555 i

A DIV15 DOM OF TEXAS LTELETIE.S ELECTRIC COM9ANY

, _ . - . _ _ ~ . _ . _ - - , _ - - - . _ _ ..- . , - - _--.-__ -.

Log # TXX-6121 File # 10110 903.7 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWEA . ee9 NORTH OLIVE STREET, La et . DALLAS. TEX.AS 78308 December 3, 1986

.* 3,*". Lh.E'S 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 N05. 50-445 AND 50-446 SEISMIC CATEGORY II SYSTEMS AND COMPONENTS SDAR: CP-86-45 (INTERIM REPORT)

Dear Mr. Johnson:

On June 6,1986, we verbally notified your Mr. T. F. Westerman of a possible deficiency involving the interaction of non-seismic Category I structures and components with seismic Category I structures. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

We are presently evaluating this concern to identify if the present plant design is consistent with the FSAR and NUREG-1030. This evaluation is scheduled for completion by January 16, 1987.

We will submit our next report by February 6, 1987.

Very truly yours,

(

W. G. Counsil By: '

G. S. Keeley _ /

Manager, Nuclear u sing JDS/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Comission Washington, D.C. 20555

. A Di>1SKYi Of TE%As LTILITIES ELECiniC COMPANY

. t

Log # TXX 5101 File # 10110 908.1 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER 400 NORTH OLIVE STREET. I.B. 98 . DAI.1AS. TEXAS 7S303 November 17, 1986 ,

EM3".iff.U:n, 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 CONAX ADAPTOR MODULES AND ELECTRICAL PENETRATIONS SDAR: CP-86-49 (INTERIM REPORT) ,

Dear Mr. Johnson:

On October 10, 1986, we botified you of a reportable deficiency involving the effects of polar-organic solvents on the sealants of Conax adaptor modules and electrical penetrations. This is a follow-up interim report of a reportable item under the provisions of 10CFR50.55(e)..

Applicable construction procedures and the coating engineering verification program were modtfied to include provisions which ensure solvents, that affect end sealants, do not contact the sealants during the application of coatings.

Procurement and replacement of the affected modules is continuing.

We anticipate submitting our next report by January 30, 1987.

Very truly yours,

{YM W. G. Counsil JDS/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIVI 5 KEN OF TE%AM LTILititA ELECTRIC CnAirAAy

____ _.__r . _ . - _ . . .

Log # TXX-6093 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY November 14, 1986 U.'".ifEUM, Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects V. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

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)

Dear Mr. Johnson:

On July 17, 1986, we verbally notified your Mr. I. 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-5032, dated September 19, 1986.

The vendor (Hilti) has recently issued revised average ultimate tensile values for 1/2-inch diameter anchor bolts. The tensile load values for the other sizes of Hilti anchors remain unchanged. Based on the information received from Hilti, we will review and revise the appropriate technical documents as required and begin an evaluation of existing 1/2-inch diameter anchor installations.

We anticipate submitting our next report by January 30, 1987.

Very truly yours, b .Q in b W. G. Counsil By: . .

//

Man ger i lear sing.

GLB/gj \/

c - flRC Region IV (Original + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission a Washington, D. C. 20555 A U8%i%I0% OF 1EA 4v LTil.lTlin iLit*TNIC tintPA%Y

Log # TXX-6150 File # 10110 903.11 TEXAS LTrlLITIES GENERATING COMPANY SKYWAY TOwth . ese NORTH OLIVE STREET. L2. 88 . DALLAS, TEXAS 78308 December 12, 1986 MYT.hff.US, 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 CABLE TRAY SPLICES / CONNECTIONS SDAR: CP-86-52 (INTERIM REPORT)

Dear Mr. Johnson:

On July 25, 1986, we verbally. notifled you Mr. I. Barnes of a deficiency involving the splices / connections used for cable trays in Units 1 and 2. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest interim report logged TXX-6053 was submitted October 21, 1986.

The procuss of gathering information on Unit 2 installations was initiated in September,1986, by expanding the verification procedure to include tray

splice connections. Presently, additional details of deviations in Unit 2 from approved splice patterns are being assessed to determine if Unit I data should also be incorporated. Upon completion of this assessment, a sample will be developed and included in the testing program. This program will provide identification of the locations and types of all accessible splice plates.

Our testing program has been expanded to include splice plates that deviate from generic types approved for use on CPSES. We have revised our estimated completion date for evaluation of all test results to March 31, 1987.

1 Our next report will be submitted no later than April 28, 1987.

1 Very truly yours, l'7422 W. G. Counsil RSB/m15 c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A OtVis00M 09 TEXAS L71LITIK.E ELECTRIC C0ht94%Y 8 .

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

Log # TXX-6146 File # 10110 903.10 TEXAS UTILITIES GENERATING COMPANY SEYWAY TOWER 400 NORT,4 OLIVE STREET.1.5. el e D45J.AS. TEXA5 78301 December 10, 1986

, i E"LL . 0*i

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects 4

U. S. Nuclear Regulatory Commission i 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

SUBJECT:

COMANCHE PEAX STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 8.ND 50-446 SEISMIC DESIGN OF Coh0VIT SDAR: CP-86-53 (INTERIM REPORT) .

Dear Mr. Johnson:

On October 21, 1986, we notified you of a reportable deficiency involving the seismic design of conduit under the provisions of 10CFR50.55(e) via our letter logged TXX-6054. This is an interim report submitted to status corrective action implemented to date.

In our last report, we indicated a testing program had been scheduled to evaluate the ability of adhesives or clamps, applied to conduit couplings j after installation, to resist torsional moments. Using the test results, corrective actions would be specified. Currently, scheduling delays have

, precluded the performance of these tests.

Completion of these activities are currently scheduled for January 30, 1987.

We anticipate submitting our next report February 20, 1987.

1 Very truly yours, W. G. ounsil ,

/ ,

By: .-

G. S. Keeley O /

W

Manager, Nuclear liegnsing RSB/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i

4 Dfl18N)4 OF TE.445 LTfLITIE.S ELECTRIC COMPANY i

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Lcg # TXX-6091 File # 10110 903.7 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH OLIVE STREET, LB. Al . DAl.LAS. TEXA5 THet November 14, 1986 MATO Sff.U'n, 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 ORIGINAL DESIGN OF CONTROL ROOM CEILING SDAR: CP-86-54 (INTERIM REPORT)

Dear Mr. Johnson:

On October 3,1986, we not'ified you of a reportable item involving the design and installation of the control room ceiling (see TXX-6007). This is a follow-up interim report on a reportable item under the provisions of 10CFR50.55(e) and is provided to status the implementation of corrective actions.

The physical construction of the new ceiling is complete with the one remaining activity being quality control verification. This is tentatively scheduled for completion by November 28, 1986.

We will submit our next status report no later than December 19, 1986.

Very truly yours, W. G. Couns,il

/

By: , M G. S. Keeley Manager, Nuclea icensing JCH/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 l .< orsi. stow or Tv%<s LTIUTirs sucraic cours%s

Log # TXX-6107 File # 10110

. 903.7 TEXAS UTILITIES GENERATING COMPANY SEYwAY Towsa e 4 0 NORTit OLIVE STREET, t.5. 85 DALLAS. TEXAS 76M8 November 21, 1986

.T.Y1". *,cfMOL 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 SEISMIC AIR GAP DESIGN ADEQUACY SDAR: CP-86-55 (INTERIM REPORT)

Dear Mr. Johnson:

On August 14, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving the seismic air gap design adequacy between the Auxiliary Building ~

and Units 1 and 2 Containment Buildings. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). Our last interim report was logged TXX-50ll, dated September 12, 1986.

The specific deficiency involved recent calculations which indicated that a separation gap dimension should be greater than the existing design dimension during extreme high temperature conditions. Using more realistic data, this calculation was refined to demonstrate that the present gap is acceptable.

Review and evaluation of the refined calculations are scheduled for completion by February 20, 1987.

We anticipate submitting our next report no later than March 13, 1987.

Very truly yours, N

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 instRKPt OF TEXAS LTTELITIES ELECTRIC COMPANY

c e 0 File # 10110 903.0 }

TEXAS UTILITIES GENERATING COMPANY SEYWAY TOWER 458 NORTH OLIVE STREET.1.5. 88 . DALLAS. TEJLAS flatt November 24, 1986 72 %".h #.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)

DOCKETS NOS. 50-445 AND 50-446 SUPPORT INSTALLATIONS - SPACING VIOLATIONS SDAR: CP-86-59 (INTERIM REPORT)

Dear Mr. Johnson:

On August 29, 1986, we verbally notified your Mr. T. Westerman of a deficiency involving support installations with concrete attachments in violation of applicable CPSES design specifications. Our latest interim report logged TXX-5052 was submitted on September 29, 1986. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). This issue is applicable to both Units 1 and 2.

Engineering Evaluation Separation Violation (EESV) forms are used to document and track support spacing design problems which require engineering resolution. Any modification to a support design resulting from the engineering resolution requires the initiation of the appropriate design change documents to effect the change.

Our initial evaluation has determined the following:

1. EESV forms have been issued for support installations without the required design change documents and that these installations have been accepted by Quality Control based on technical data outlined on the EESV form.

2. Some engineering disciplines have not controlled the issuance / distribution of EESVs such that documented multi-discipline evaluation of all areas of the design and installation was not assured.

3. Existing EESV procedural control criteria are inadequate.

4. Quality inspection procedures have been identified which erroneously allow the acceptance of spacing violations based on EESVs without appropriate design change documentation.

A procedure will be written to effectively control, transmit and document spacing violations. Affected quality inspection procedures have been identified and are being revised to require the use of the appropriate design change documents prior A Dl%1.sION of TEXAS LTIL!TILs ELECT 9tC CintFA%Y

m to Quality Control acceptance. EESVs are no longer accepted as approved design change documents.

A review of EESVs and associated design documents will be performed to identify and evaluate support installations with inadequate documentation, and where necessary, the appropriate design change documentation will be generated. Our determination of reportability under the requirements of 10CFR50.55(e) is pending until all results of this review are assembled.

We anticipate submitting our next report by May 15, 1987.

Very truly yours, I

1. C&d W. G. Counsil BSD/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Log # TXX-6092 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER ese NORTH OLIVE STREET. LB, SB . DALLAS. TEXAS 7&304 November 17, 1986 Eh0".h&.U'1 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 POLAR CRANE RESTRAINTS SDAR: CP-86-61 (FINAL REPORT)

Dear Mr. Johnson:

On September 41986, we verbally notified your Mr. I. Barnes of a deficiency involving the restraints for the polar crane rail. Specifically, three rail to rail ground wires have'been found broken, two shims have partially dislodged from under the rail, and two cadwelds connecting the ground wire to the rail have been broken. This indicates that movement occurred in the Unit 1 polar crane rail assembly.

Operating experience with the polar crane has shown that the rails tend to creep axially and displace radially during revolution of the crane. The axial creep is cumulative and the rail gaps tend to decrease at some locations and increase at others. Radial and/or axial rail movements are allowed by the existing rail clips. Dislodging of shims under the rail, broken ground wires, and broken cadwelds are directly attributed to the radial and/or axial movements of the rails.

The rail movement and associated loss of ground wires and dislodging of shims might have necessitated minor maintenance or repair. However, they do not affect the aspects of polar crane performance, safety, or reliability that are required for its intended safety function. Consequently, this issue would not have adversely affected the safety of operation of the plant had it remained uncorrected. This issue is not reportable pursuant to 10CFR50.55(e). Records documenting our position are available for your inspector's review at the CPSES jobsite.

Very truly yours, O

W. G. Counsil RWH/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A I)IVi%It,4 UF TEk 4% LTillTit3 ELECTRIC CintV4%9 o

Log # TXX-6136 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SEYWAY N e 450 980ST98 Ot.IVE N. L5. 88 . DAIJ.A& TEMAS test December 5,1986 E.Y#?.tf?ME Mr. Eric H. Johnson, Director

! Division of Reactor Safety and Projects i U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N05. 50-445 AND 50-446 NON-CONTACT LAP SPLICES IN THE AUXILIARY BUILDING SDAR: CP-86-66 (INTERIM REPORT)

Dear Mr. Johnson:

On September 26, 1986, we verbally notified your Mr. I. Barnes of a deficiency regarding vertical rebar exposed during the inspection of core bores in the Auxiliary Building that apparently do not satisfy the criteria of a code 4

defined lap splice. This is an interim report of a potentially reportable i

item under the provisions of 10CFR50.55(e). We have submitted an interim 3

report logged TXX-6061, dated October 27, 1986.

Previous calculations and quality documentation are currently under review to evaluate the structural adequacy of the wall identified in this deficiency.

This review will precede formal calculations required to assess the effects of i this condition on the safety of plant operations. These activities are scheduled for completion January 28, 1987.

Our next report will be submitted no later than February 18, 1987.

Very truly yours, if W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)  !

\

Director, Inspection & Enforcement (15 copies) ,

U. S. Nuclear Regulatory Commission l i Washington, D. C. 20555 I

{ 4 stV3mppv OF 75248 LTILf7153 512C738C COMPANY d

Log # TXX-6124 File # 10110 908.3

. TEXAS UTILITIES GENERATING COMPANY SEYwAY TOWBA 400 PeORTH OLIVE STREET. 8.2. 48 e DALLAS TEXA4 flapt November 26, 1986

.i.Y#".Ef?.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. 50-445 AND 50-446 WEATHER PROTECTION FOR CLASS lE 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 provision of 10CFR50.55(e). We have submitted an interim report logged TXX-6081, dated October 31, 1986.

We are continuing our evaluation and anticipate submitting our next report by January 30, 1987.

Very truly yours, 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 DinsN)N UV TEXAS LTilfTIE.1 ELECTRIC COMPANY

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

j es Log # TXX-6081 File # 10110 '

TEXAS UTILITIES GENERATING COMPANY 908.3 SKYWAY TOWER . 4ee NORTH OLIVE ETREET. L.B. 88 . DAIAAS TEXAM 75201 October 31, 1986

, !"#1".h#.UE ,

- Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission '

'i 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 '

s

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 '

WEATHER PROTECTION FOR CLASS 1E COMPONENTS 4 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 1E components used in '

outdoor installations. This is an interim report of a potentially reportable '

item under the provisions of 10CFR50.55(e).

4 The specific deficiency involves rust and water observed inside exposed (outdoor) Class IE terminal boxes as documented by two (2) non,-conformance reports (NCR's). Our evaluation of these conditions has determined that the Electrical Erection Specification (2323-ES-100) did not clearly 'specify all areas where liquid tight connections were required. This lack of clarityN resulted in omission of liquid-tight fittings in outdoor pull / junction boxes '-

located on conduit installations with Class IE terminal boxes. Water could leak into the pull / junction boxes and drain into the terminal' boxes. A design change will be issued for the specification to providetspecifictrequirements for outdoor installations. The design change will'resdf t in ' additional inspections and corrective measures, if required. ,

Although our preliminary review for the two instances of' deficiencies indicates that, if remaining uncorrected, the safety of plant operations would not have been adversely affected, the programatic review of these conclusions is not yet complete. 1 i

A DI%1SDON OF 1EKAS CT1LITIES ELECTRIC COMPA.%Y

~

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m

, ) .* e$r TXX-6081 -

October 31, 1986 Page 2

.:[

We will submit our next report on this issue no later than November 26, 1986.

Js Very truly yours, I

W. G. Counsil

. By: -

G. S. Keele & / --

, Manager,Nuclearpcensing WJH/gj c - Region IV (Original + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 s

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r 1 Log # TXX-6125 File # 10110 908.3 TEXAS UTILITIES GENERATING COMPANY i eEYWAY TOWER . 60 NORTH OUVE STRErr. LB. el . DAU.AS, TEXAS 75291 j November 26, 1986 Eh'1".hff.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 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 CABLE PULLING TENSION SDAR: CP-86-71 (INTERIM REPORT)

Dear Mr. Johnson:

On October 2,1986, we verbally notified your Mr. Ian Barnes of a deficiency regarding electrical cable pulling. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted an interim report logged TXX-6065, dated October 31, 1986.

Concerns exist involving the possibility of some cables being damaged because cable installation procedures do not address tension limits for vertical cable pulls and subsequent pulls into conduits with previously pulled cables.

Evaluation activities noted in our previous response have proceeded to the point that changes in the construction procedures are required. Our evaluation has not progressed, however, to the extent an assessment of the effects of this deficiency on the safety of plant operations can be completed.

This phase of the evaluation should be completed by February 2,1987.

We anticipate submitting our next report by February 25, 1987.

Very truly yours, 50 %

W. G. Counsil JCH/mlh c - HRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 l

l A CTVESION OF TEXAS LTTLITIES ELECTRIC COMPANY

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Log # TXX-6065 File # 10110 TEXAS UTILITIES GENERATING COMPANY 908.3 October 31, 1986 EMM.L.*f.EEh Mr. Eric H. Johnson, Director Division o'f Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 CABLE PULLING TENSION SDAR: CP-86-71 (INTERIM REPORT)

Dear Mr. Johnson:

On October 2,1986, we verbally notified your Mr. Ian Barnes of a deficiency regarding electrical cable pulling. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

A concern exists over the possibility of allowable cable tension being exceeded for some cables because cable installation procedures did not address correction factors for vertical cable pulls and co-efficient of friction for cable pulls into conduits with previously pulled cables. Although no specific damage has been identified, an investigation and engineering evaluation will be conducted to determine if the actual cable pulling method used could have caused any damage.

Our investigation and subsequent evaluation will be based on the following plan of action.

1. Review the installation specification, construction procedures and quality assurance procedures on cable pulling to determine the overall adequacy of the program.

2. Interview personnel from Engineering, Construction, Quality Assurance, Start-up and Training to evaluate current installation prictice.

3. Review the calculations associated with the cable pulling charts to determine what margins are included.

4. Review NCRs and Start-up deficiencies for problems associated with cable pulling to determine causes and resolutions of past cable pulling deficiencies.

5. Perform an engineering evaluation of cable installations susceptible to increased pulling tension.

l A DIV1510N OF TEXAS L71LETILS ELECTRIC COMPA*tY

]

m .-.

TXX-6065 October 31, 1986  ;

Page 2 i We will-submit our next report on this issue no later than November 26, 1986.

Very truly yours, 60}/ Caud W. G. Counsil By: '

b G. S. Keeley C ' 2-Manager,NuclearLiMnsing WJH/gj c - NRC Region IV (Original + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555

i-

-4'( *b ~

<. Log # TXX-6120 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH OBJVE STREET. L.B. 88 . DALLAS. TEXAS 78308 November 25, 1986

' MS^4t#.YME, 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)

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 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). We have submitted an interim report logged TXX-6042, dated October 15, 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 January 9, 1987.

Very truly yours, C2 W. G. Counsil BSD/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies) t U. S. Nuclear Regulatory Commission Washington, D.C. 20555 4

A DnT510N Of TEXA5 L'TELETTES ELECTRIC COMI s

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"* TXX-6120 .

~~

N:vember 25, 1986 Page 1 of 1 ,

ATTACHMENT SMALL BORE PIPE SUPPORT MODIFICATIONS Number of Qn11 Cateaory Modifications

• 1 Prudent 25 Recent Industry Practice 57 Adjustment 2**

Cumulative Effects 38 2 Prudent 9 Recent Industry Practice 18 Adjustment 9 Cumulative Effects 82

• Changes in these figures from the last report represent not'only identificat. ion

.of futher modifications but a reclassification and/or recategorization of certain supports.

• • A reduction in this category from the last report reficcts the removal of preliminary information inadvertently included in the previous report.

F 903.9 TEXAS UTILITIES GENERATING COMPANY SIL /WAY TOWER est NORTH OLIVE STREET, L.B. OR DALLAS. TEXAS 75291 November 19, 1986 U %'t". L B.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)

DOCKETS 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).

A drawing review of all ASME snubbers was conducted to verify the adequacy of swing clearances. 1063 snubbers were identified as having attachment brackets with

' attributes which could potentially result in restricted movement and/or binding of the snubber. As a result of field examination, the number of snubbers of concern has been reduced to 165. These remaining snubbers require additional field checks to complete the evaluation.

We are continuing our evaluation of this issue and anticipate submitting our next report by December 23, 1986.

Very truly yours, l.H20v W. G. Counsil BSD/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIVIAIO% OF TE% A% (TILITIF5 FLFCTNil C0%fFA%9

._. _ . , _ . _ . _ ~ _ _ . . . , . _ __.__ __ _ . . _ . - -

Lcg# TXX-6084 I File # 10110 l I

908.3 TEXAS UTILITIES GENERATING COMPANY  !

November 17, 1986 Un' ALE?EL Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ROCKWELL TERMINAL BOXES SDAR: CP-86-74 (INTERIM REPORT)

Dear Mr. Johnson:

On October 21, 1986, we verbally notified your Mr. Ian Barnes of a deficiency regarding internal wiring. discrepancies and rusty close nipples and fittings in terminal boxes for Unit 2 main steam isolation valves supplied by Rockwell.

Our preliminary evaluation indicates this deficiency potentially effects Units 1 and 2. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

A technical evaluation is being performed by Stone and Webster Engineering Corporation. Additional time will be needed for TUGC0 Engineering review of their input. We will submit our next report on this issue no later than December 19, 1986.

Very truly yours,

[

W. G. Counsil

!7:I WJH/gj c - Region IV (Original + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A DI%ESION OF TEXAM t.78LETIES ELECTRIC CostPA%Y V

~

Log # TXX-6097 ,

Filo i 1E10 909.4 TEXAS UTILITIES GENERATING COMPANY  !

elevember 20, 1986 wtLLIAM G. COUN$ll fascvwve wCfposeeetwT ,,

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 N05. 50-445 AND 50-446 ASCO SOLENOID VALVES IN PISTON s AIR ACTUATORS OF PAPC0 DAMPERS SDAR: CP-86-75 (INTERIM REPORT) .

Dear Mr. Johnson:

On September 4,1986, we verbally notified your Mr. I. Barnes of a deficiency involving ASCO solenoid valves in piston air actuators of PAPC0 dampers. This is-an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

We are continuing our evaluation and anticipate submitting our next report by February 19, 1987.

Very truly yours, V!. h f W. G. Counsil l By:

J. S. Marshall l Supervisor, Generic Licensing i .

i JDS/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i

A DCVISION Of TEXAS LTILITEU ELECTRIC COM9ANY

Log 5 6AA-0110

, _ , _ , File # 10110

- 2 908.3 TEXAS UTILITIES GENERATING COMPANY November 20, 1986

'"." ".Sf??. 2

, 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 DEVIATIONS IN GOULD BATTERY RACK DIMENSIONS SDAR: CP-86-76 (INTERIM REPORT)

A l

Dear Mr. Johnson:

On October 21, 1986, we verbally notified your Mr.. I. Barnes of a deficiency involving the configuration and dimensions of Gould Battery Racks deviating from drawing requirements. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

! Class 1E battery racks for Trains A and B, which were designed and fabricated by Gould, were found to have configurations and dimensions which deviated from the vendor design drawings. These deviations could result in violation of battery cell spacing requirements for Class 1E batteries. Review has indicated the conditions are applicable to Units I and 2.

We are continuing our evaluation and anticipate submitting our next report by April 22, 1987.,

Very truly yours,

[O, (.

W. Counsil i By .

l "J. S. Marshall Supervisor, Generic Licensing

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RWH/mlh

. c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission

. Washington, D.C. 20555 l

4 omsaw or tras amurms sucme cour4ur

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,. Log # TXX-6103

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. Filo # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SEMTO4FER . 450 P808T5 DLIVE STESET. I.m 88 . DALLAS, TEXAS ,gst November 19, 1986

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.2OT.LUE2%

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)

DOCKETS NOS. 50-445 AND 50-446 INSTRUMENT TUBING MINIMUM WALL THICKNESS SDAR: CP-86-77 (INTERIM REPORT)

Dear Mr. Johnson:

. I -- --

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 allawables required by the ASME B&PV Code,Section III. This.

is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

A review of DCA 13346 to specification 2323-MS-625, " Instrument Tubing and Fittings", and construction procedure ICP-4, " Instrument Tubing Insta11atton 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.

We are continuing our evaluation of this issue and anticipate submitting our next report by January 21, 1987.

Very truly yours, Vc. M W. G. Counsil By: M* I~

d.(/d. Beck

- ~ Vice President Nuclear Engineering BSD/amb x ommov or rua vmma uncrnsc cmann

_ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ 3_ y y_

1. Log # TXX-6139 Filo # 10110 903.9 -

TEXAS UTILITIES GENERATING COMPANY SKYWAY N . 400 ,80STN OLIVE STR5rr. R.B. 88 . DALLAS. TEXA5 70004 December 5, 1986 1

1 e scuTvytwks ee ?

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 l Arlington, TX 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N05. 50-445 AND 50-446 STRUCTURAL STEEL BOLTING CONNECTIONS WITH THREADS IN THE SHEAR PLANE IN THE UNIT 1 CABLE SPREADING R00N SDAR: CP-86-78 (INTERIM REPORT)

Dear Mr. Johnson:

On November 7,1986, we verbally' notified your Mr. Tom Westerman of deviations in the structural steel bolting in the cable spreading room. This is an i interim report of a.potentially reportable item under the provisions of 10CFR50.55(e).

Specifically, the applicable specification states that all field connections

shall be made with high strength steel bolts in bearing type connections with

! threads excluded from shear p anos except where otherwise stated or shown on engineering drawings. Instances of bolted connections with threads in the i shear plane which were.not stated or shown on engineering drawings have been observed in the Unit 1 Cable Spreading Room.

In order to address this deviation, all pertinent standard design criteria

will be reviewed to identify the components where such deviations may occur.

l Structural design calculations for tie Unit 1 Cable Spreading Room framing and typical design calculations for other identified components in both units will be evaluated to determine if such deviations are adverse to the safety of

, plant operations or impact the structural integrity of the frame or

components. If a field verification is necessary, typical shop fabrication drawings will be used to determine if the bolt length can be used as a criterion for determining if a bearing type connection has bolts with threads included in the shear plane. Additionally, we are reviewing the affected inspection procedures to assure they adequately address specification requirements for this attribute.

i a annum or suxAs ununss useme coumr .

TXX-6139 December 5, 1986 Page 2 of 2-We anticipate submitting our next report no later than March 11, 1987.

Very truly yours,

? b W. G. Counsil DAR/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

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e

Logt TXX-6141 File # 10110 ,

- 908.3 '

TEXAS UTILITIES GENERATING COMPANY ,

i December 5, 1986

".Y1".LNJE Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects ,

4 U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) 4 DOCKET NOS. 50-445 AND 50-446 OVERTORQUED WESTINGHOUSE AR RELAYS SDAR: CP-86-79 (INTERIM REPORT)

Dear Mr. Johnson:

i 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).

The specific issue involves the tool being used to tighten the terminal screws on the Westinghouse AR relays not being calibrated to the required accuracy.

Overtightening of the screws could possibly result in the deformation of the stationary contact assembly, reducing contact overtravel, which may result in loss of contact continuity.

4 i We are continuing our evaluation and anticipate submitting our next report by January 28, 1987.

J

! Very truly yours, j W. G. Counsil RDD/gj l

l c - NRC Region IV (Original + 1 copy) 1 i Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i

I i

4 m amy or runs enunas sucrase crwr4w 4

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Log # TXX-6140 i File # 10110 l 903.10 1 TEXAS UTILITIES GENERATING COMPANY SEVwAY N . est peOST98 OL8v5 373337. 8.B. St DALLAS, ?SAAS ,eept December 5, 1986

.".'%0 LfMZE, 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 N05. 50-445 AND 50-446 TORQUE VALUES FOR J. C. WHITE TU8ING RESTRAINTS SOAR: CP-86-80 (FINAL REPORT)

Dear Mr. Johnson:

On November 7,1986, we verbally notifled your Mr. Tom Westerman of a deficiency involving the recommended torque values for J. C. White tubing ,

restraints. The torque values for these restraints have not been reflected in the project specifications and procedures or implemented during the installation process.

The intent of the minimum torque requirements for the J. C. White tube restraints has been met when utilized with Hilti bolts, Nelson studs and Unistrut nuts per the current instructions which require tightening to a " snug t tight" condition and "in a secure manner". The J. C. White restraints have been installed with the fasteners tightened either " snug tight", to 8 ft-lbs, or 4.2 ft-lbs. Since " snug tight" is the full effort of a man using an ordinary wrench, the fasteners meet the intent of the recommended torque '

values. While these installations meet project requirements and the I manufacturer's recommended torque requirements, these bolts were not installed .

per the specific torque requirements set forth in the vendor's data sheets for solid tube restraints. Our evaluation has concluded that the vendor's minimum i torque requirements have been met when these bolts were installed per project l specifications.

i

( Project specifications and procedures will be revised to specifically l

implement the manufacturer's requirements. This revision will replace the terms " snug tight" and "in a secure manner" which meet the intent of project requirements, but cannot be verified. A precise torque value will be utilized j

and verified in all cases for future instrumentation and control applications.

I i

l A mnenon or nxrs Litunss sLECTnIC Cohe9ANY

P TXX-6140 December 5, 1986 '

Page 2 of 2 '

We have concluded in the event this issue had remained undetected, no condition adverse to safety would exist. This issue is not reportable under  ;

the provisions of 10CFR50.55(e). Records supporting this conclusion are available for your inspectors to review at tie CPSES project site.

Very truly yours, nd $

W. G. ounsil ,

By: r

• b' G. S. Keeley .- /-

, Manager,Nucleargensing DAR/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 p

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Log # IXX-6142 File # 10110 907.6 TEXAS UTILITIES GENERATING COMPANY DEYWAY TOWER . des P80AT90 OLIVE WFREET. LB. 88 . DALLAS. TE3EAS 76388 December 5, 1986  %

WILLIAnd O. COUNSIL EEricH. 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 BOP SAFETY RELATED INSTRUMENT SET POINTS SDAR: CP-86-81 (INTERIM REPORT)

Dear Mr. Johnson:

I On November 7, 1986, we verbally notified your Mr. T. Westerman of a potentially reportable item involving the calculations for BOP Safety-related instrument setpoints indicating that omissions of required data or use of incorrect information occurred in performing the calculations required per Reg. Guide 1.105, Rev.l. This is an interim report of a potentially reportabic item under the provisions of 10CFR50.55(c).

Evaluation of this issue, which is applicable to Units I and II, is being conducted by Stone & Webster Engineering Corporation. We anticipate submitting our next report by February 6, 1987.

Very truly yours,

///8 p/da W. G. Counsil RDD/gj c - NRC Region IV (Original + 1 copy)

Director,InspectionandEnforcement(15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A DIVEMON UV TERAM L71LITis.t EliCTNIC COMP 4MY i A