ML20211F546
| ML20211F546 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/20/1987 |
| From: | Ellis J Citizens Association for Sound Energy |
| To: | Bloch P, Jordan W, Mccollom K Atomic Safety and Licensing Board Panel |
| References | |
| CON-#187-2582 OL, NUDOCS 8702250127 | |
| Download: ML20211F546 (1) | |
Text
a xas 75224 214/946-9446 U D UJD (CITIZENS ASSN. FOR SOUND ENERGY)
February 20, 1987
'87 FE9 24 P!2:29' Administrative Judge Peter B. Bloch Dr. Kenneth A. McCollom U. S. Nuclear Regulatory Commission 1107 West Knapp Street Atomic Safety & Licensing Board Stillwater, 0).lahoma 74075 Washington, D.C.
20555 Dr. Walter H. Jordan 881 W. Outer Drive Oak Ridge, Tennessee 37830
Dear Administrative Judges:
Subject:
In the Matter of Texas Utilities Electric Company, et al.
Application for an Operating License Comanche Peak Steam Electric Station Units 1 and 2 Docket Nos. 50-445 and 50-446 "O b 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 with such items on 1/29/87.
It is our intention to periodically continue to provide these SDAR's unless the Board indicates otherwise.
Respectfully submitted, CASE (Citizens Association for Sound Energy) b$0 /
( rs.) Juanita Ellis President cc:
Service List Attachments 0702250127 070220 PDH ADOCK 0500 5
3 3 50
i Log # TXX-6248 File # 10110 903.9 Re:10CFR50.55(e)
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nlELECTRIC January 30, 1987 w m,- c. c wi imwan ne ernac,,,
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 CABLE TRAY HANGER DESIGN SDAR: CP-85-35 (INTERIM REPORT)
Gentlemen:
On October 21, 1986, we notified you by our letter logged TXX-6048 of a deficiency involving the design and construction activities of the cable tray support program which we deemed reportable under the provisions of 10CFR50.55(e). This is an interim report submitted to status corrective action implemented to date.
The cable tray support testing and verification programs are continuing. The testing program and evaluation of test results are currently scheduled for completion by June 12, 1987.
Our next report on this issue will be submitted no later than July 6,1987.
Very truly yours, hY n L By:
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G. S. Keeley
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e Manager,Nucleart.yensing DAR:lw c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV
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400 North Olne Street I..H. 81 Dallas. Texas 75201
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g Log # TXX-6278 File # 10110 P9 903.10
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February 12, 1987 c.c. wn, u, a,,+,,
O. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 g~
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SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
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1' DOCKET NOS. 50-445 AND 50-446 s
EQUIPMENT C0f!DUIT INTERFACE SDAR: CP-85-39 (INTERIM REPORT) x Gintlemen:
0$ September 18, 1986, we verbally notified your Mr. T. F. Westerman of a 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-6165, dated December 15, 1986.
As previously reported, the program to evaluate this condition consists of the following three issues:
?
1
- 1) Cable slack adequacy.
2)
Conduit-to-equipment interfaces outside the vendoi approved area.
3)
Conduit orientation within the vendor approved ehtry area.
Thd cable slack. adequacy-issue has. utilized a sampling approach to evaluate as-built cable slack.
The field verification effort ahd engineering m
evaluation areicomplete. All of the sample transition ~s were qualified and found to be adequate.' Evaluation of the sample results adequacy to the entire cable population is currently in progress and expected to be completed by February 27, 1987.
~
Engineering has also completed! evaluation of 60% of the class IE equipment in
-Unit I for the conduit-to-equip ~ ment interface issue. The field verification procedure required for the Unit 2 equipment evaluation is currently in the approval process,.
The completi$n of these activities and subsequent review of the data is required before the evaluation of this issue is completed and its effect on the safety of plant operations is known.
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TXX-6278 February 12, 1987 Page 2 of 2 As previously reported, the conduit orientation issue has been completed (see TXX-6165).
We anticipate submitting our next report by May 15, 1987.
,Very truly yours, (J G Q W.G.Cgunsil By:
D. R. Woodlan Supervisor, Docket Licensing JCH/mlh c - Mr. E. H. Johnson, Region IV Mr. D. L. Xelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 9
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Log # TXX-6246 File # 10110 Re: 100 b55(e) 4
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lilELECTRIC u. c.co a emm, n, msa,,,
January 30, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk
' Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SEISMIC CATEGORY II PLATFORMS SDAR: CP-85-53 (INTERIM REPORT)
Gentlemen:
5 On December 20, 1985, we verbally notified your Mr. R. Hall of a deficiency involving Seismic Category II platforms. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our last interim report, logged TXX-5042, was submitted September 26, 1986.
Development of the action plans for the subject platforms is essentially complete. The plan will require reinspection and subsequent engineering evaluation of the inspection results. Our evaluation of this deficiency, with regards to the safety of plant operations, will be based upon the review of these inspection results.
Our next report on this issue will be submitted no later than April 22, 1987.
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Very truly yours, bh W. G.
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By: I.
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G. S. Keeley
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Manager, Nuclear}fensing JCH/mlh c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 1
f 400 North Olise Street l.. H. M i Dallas. Texas 75201 l
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L y U' MEE Log # TXX-6260
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% Mem G.(oumil Lm usow $ k e Preudens U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 PR0XIMITY PLACEMENT - RICHMOND INSERTS TO EMBEDDED PLATES AND WELDED ATTACHMENTS TO EMBEDDED PLATES SDAR: CP-86-04 (INTERIM REPORT) j Gentlemen:
i On January 13, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency regarding the placement of Richmond inserts in the proximity,of loaded embedded plates which could compromise the structural integrity of adjacent shear cones.
Our last interim report was logged TXX-6031, dated October 20, 1986.
On June 5,1986, we verbally notified your Mr. I. Barnes of a deficiency i
j involving the design / construction requirements for minimum separation of welded attachments to embedded strip plates which were not properly reflected in inspection procedures.
Previous responses to this item have been reported under SDAR CP-86-44, " WELDED ATTACHMENTS TO EMBEDDED STRIP PLATES" under the provisions of 10CFR50.55(e).
Our last interim report for SDAR CP-86-44 was lodged TXX-6035, dated October 20, 1986. The scope of SDAR CP-86-04 has been expanded to include evaluation of SDAR CP-86-44. All subsequent reports on these issues (SDAR CP-86-04 and SDAR CP-86-44)~concerning reportability under the provisions of 10CFR50.55(e) will be reported via SDAR CP-86-04.
We have concluded that the deficiencies identified above are reportable under the provision of 10CFR50.55(e), and the required information follows:
DESCRIPTION OF PROBLEM 1
A review of the issues has identified four deficiencies:
1.
Quality Instruction QI-QP-11.23-2, " Inspection of Completed Installations i
for Separation / Spacing", and other discipline procedures, (i.e., QI-QP-11.10-1, " Inspection of Seismic Electrical Support and Restraint Systems",
QI-QP-ll.10-2, " Cable Tray Hanger Inspection", and QI-QP-11.8-5,
" Inspection of Instrument Tubing Fabrication, Installation and Instrument Installation"), do not require inspection to or in accordance with CCP-45/SS-30, " Permanent and Temporary Attachments to Embedded Weld Plates / Structural Embedments", for minimum separation requirements for welded attachments to embedded steel plates.
400 North Olne Street LH Ml Dallas. Teus 75201 I
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m TXX-6260 February 13, 1987 Page 2 of 3 1
2.
Prior to March 3,1986, design and installation documents did not identify minimum spacing criteria between loaded Richmond inserts and loaded embedded plates. The use of a Richmond insert in proximity to a loaded embedded plate could compromise the structural integrity of adjacent shear Cones.
3.
Existing design and installation documents do not adequately identify minimum spacing criteria between Hilti bolt installations and loaded embedded plates.
The placement of a Hilti bolt in proximity to a loaded embedded plate could compromise the structural integrity of adjacent shear Cones.
4.
Existing quality instructions do not delineate the separation criteria between welded attachments to embedded plates and existing Hilti bolts.
Deficiencies 1 and 4 resulted because the Quality Control procedures governing the inspection of embedded plates were not developed in accordance with the requirements of CP-QP-6.0, " Preparation of Quality Procedures and Instructions".
Procedure CP-QP-6.0 states that the requirements of QC instructions and procedures be derived from engineering / construction requirements in design documents.
Deficiencies 2 and 3 were the result of inadequate engineering review of the design specification (2323-SS-30) and related construction / quality control procedures pertaining to embedded plates (i.e., CEI-20, " Field Installation of Hilti Bolts", CCP-45, QI-QP-11.10-1, QI-QP-11.10-2, QI-QP-11.8.5 and QI-QP-11.23-2).
SAFETY IMPLICATION The lack of proper acceptance criteria in the quality instructions and procedures could have resulted in unacceptable embedded plate, Richmond insert and/or Hilti bolt installations which may have adversely affected the safety of the plant during accident conditions.
a Also the appropriate design criteria for spacing between loaded embedjed plates and loaded Richmond inserts or Hilti bolts were not adequately specified in the applicable design documents. These deficiencies represent a significant breakdown in the QA Program required by 10CFR50 Appendix B (Criteria 3 and 5).
CORRECTIVE ACTION To prevent recurrence of deficiencies 1 and 4, all personnel responsible for the development of quality control procedures for embedded plates will be reinstructed in the requirements of CP-QP-6.0.
To prevent recurrence of deficiencies 2 and 3, Engineering Assurance will be instructed to review and revise, if necessary, the appropriate engineering procedures to ensure proper engineering review of all revisions to existing and future design specifications and inter-disciplinary review of construction and quality control procedures.
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d TXX-6260 February 13, 1987 Page 3 of 3 As previously reported, the design specification and related construction / quality control procedures pertaining to embedded plates are being revised.
The procedure revisions, scheduled for completion by late February, will ensure the proper control of attachments to embedded plates.
Quality Control Procedure QI-QP-11.14-13, " Separation Verification of Attachments to Loaded Embedded Plates", has been developed to address the inspection of attachments to embedded plates and spacing requirements for welded attachments, Hilti bolts, and loaded Richmond inserts.
Unit 1 field verification efforts are scheduled to start in early March. Non-conforming conditions identified by the field verification effort will be evaluated by engir.aering.
The schedule for the Unit 2 corrective and preventative actions will be provided in our next report.
We will submit our next report no later than April 29, 1987.
Very truly yours, M&a W. G. Counsil BSD:lw c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV
Log # TXX-6251 File # 10110 909.2 Re:10CFR50.55(e)
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1UELECTRIC January 30, 1987 y,m,,
Lm uine 6 n r Premlem U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SERVICE WATER SYSTEM LEAKAGE SDAR: CP-86-07 (INTERIM REPORT)
Gentlemen:
On April 11, 1986, we notified you by our letter logged TXX-4762 of a deficiency involving weld failure and coating degradation in the Service Water System which we deemed reportable under the provisions of 10 CFR 50.55(e).
This is an interim report submitted to status corrective actions implemented to date. Our latest interim report, logged TXX-5026, was submitted on September 19, 1986.
Currently, pipeline coating inspections are underway for Unit 1 installations.
Repairs will be implemented as required. A similar inspection and repair program is planned for Unit 2.
Our next report involving this issue will be submitted no later than March 27, 1987.
Very truly yours, b b,',
By:
L/
G. S. Keeley
/
e Manager,Nuclearyensing DAR:lw c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV bb 400 North Olne Street i.11 81 Dall.n. Ieus 75201 l
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- TXX-6266 File # 10110
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February 6,1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 COMPONENT COOLING WATER PUMP IMPELLER LINEAR INDICATIONS SDAR: CP-86-11 (INTERIM REPORT)
Gentlemen:
On June 23, 1986, we notified you by our letter logged TXX-4871 of a deficiency involving the linear indication on impellers for the Component Cooling Water (CCW) pumps which we deemed reportable under the provisions of 10CFR50.55(e).
This is an interim report submitted to status corrective action implemented to date. Our last interim report was logged TXX-6137, dated December 5, 1986.
Inspection and repair.of the Unit 1, Train A, CCW pump impeller has been completed.
Due to construction rework involving an' outage of all Unit 1, Train A, 6.9 kV switchgear, inspection of the Unit 1, Train B, CCW pump impeller has been deferred until after June 23, 1987.
Vendor repair of th,q re' placement " spare" impeller is continuing. We will l
submit our next report no later than September 4,1987.
Very truly yours, PQY W. G. Counsil By:
G. S. Keeley Manager,NuclearLicen[ing GLB:lw c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV
~37 OM YF 400 North Olne Street i H Ml Dallas lesas 75201
Log # TXX-6276 E
File # 10110 P9 908.3 Ref # 10CFR50.55(e) 1UELECTRIC February 11, 1987 d
lm urosv ine PreuJem V. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 CLASS 1E BATTERY CHARGER COMP 0NENTS SDAR:
CP-86-37 (INTERIM REPORT)
Gentlemen:
On May 14, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving firing board assemblies and amplifier boards u' sed in Class 1E battery chargers that do not conform to vendor assembly drawings. 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-6169, dat.ed December 17, 1986.
We are continuing our review of the procurement processes which resulted in the purchase of non-Class IE parts for Class 1E application and also the technical evaluation of the adequacy of the hardware. Results of these reviews are required to determine the impact of this issue upon the safety of plant operations.
We expect to submit our next report by May 8, 1987.
Very truly yours, h
W. G. Counsil
/
By:
G. S. Keeley
/
c Manager,NuclearLQensing WJH/dl c - Mr. Eric H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV p(RQC) gDL/-R -
tm North Olne Mreet i H kl Dallas. Tem ?$201
M Log # TXX-6256 F "--
File # 10110 908.3 r
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Ref # 10CFR50.55(e) 1UELECTRIC
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February 4, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 TRACEABILITY OF 1E PIGTAIL EXTENSIONS SDAR: CP-86-38 (INTERIM REPORT)
Gentlemen:
On May 27, 1985, 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 provisions of 10CFR50.55(e). Our latest interim report, logged TXX-6166, was submitted on December 16, 1986.
The field verification effort to obtain cable and splice data is continuing.
As-built data obtained from this effort is under evaluation in preparation of our assessment of the impact of this isiue on the safety of plant operations.
Our next report on this issue will be submitted no later than May 21, 1987.
Very truly yours, b
W. G. Counsil 4
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i G. S. Kee rex Manager,Nuclea[ Licensing RSB:lw c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV Q")C99bWOl(pb
&O North Olne Street I il Ml D nl1.u. Tets ?.520t
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Log # TXX-6261
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File # 10110 903.8 3
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February 13, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 WELDED ATTACHMENTS TO EMBEDDED STRIP PLATES SDAR:
CP-86-44 (FINAL REPORT)
Gentlemen:
On June 5,1986, we verbally notified your Mr. I. Barnes of a deficiency involving the design / construction requirements for minimum separation of welded attachments to embedded strip plates which were not properly reflected in inspection procedures. We have concluded that this deficiency is reportable under the provision of 10CFR50.55(e). Our last interim report was logged TXX-6035, dated October 20, 1986.
The scope of SDAR CP-86-04, " PROXIMITY PLACEMENT - RICHMOND INSERTS TO EMBEDDED PLATES" has been expanded to include the deficiency identified in SDAR CP-86-44, " WELDED ATTACHMENTS TO EMBEDDED STRIP PLATES". See TXX-6260 dated February 13, 1987, for the required information pertaining to SDAR CP-86-44. All subsequent reports of this issue, concerning the status of implementation of corrective actions under the provisions of 10CFR50.55(e),
will be reported via SDAR CP-86-04.
i Very truly yours, h7 W. G. Counsil BSD/lw c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV l
Mr. H. S. Phillips, RI - Region IV i
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- M North Olne Nreet
- 1. H hl Dallas. lesas 75201
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9 Log NT$I4265 File # 10110 903.7
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Ref. : 10CFR50.55(e) nlELECTRIC wn c.c a
February 6, 1987 Emunw he hemient U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SEISMIC CATEGORY II SYSTEMS AND COMPONENTS SDAR: CP-86-45 (INTERIM REPORT)
Gentlemen:
On June 6,1986, we verbally notified your Mr. T. F. Westerman of a possible deficiency involving the interaction of Category II 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). Our latest report was logged TXX-6121 dated December 3, 1986.
An Engineering evaluation will be completed to verify that seismic Category II components are seismically anchored and designed such that they will not fail and interact with Category I components and structures in a manner that would prevent the' safe operation of the Category I components and structures.
Each component requiring Category II classification will be evaluated in the field by engineering (and documented) to verify proper seismic installation.
This study is expected to be complete by August, 1987.
Our next report will 14 submitted by September 11, 1987.
Very truly yours, b
n W. G. Counsil By: -
G. S. Keeley h
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Manager, Nuclear L{c'ensing JDS/mlh c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV gg Mr. H. S. phillips, RI - Region IV
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400 North Olne Street I li %l Dall.n. km 73201
Log # TXX-6254 File # 10110 Re: 100 b55(e) j lllll=ll' =
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E 1UELECTRIC II.NNA.
January 30, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555
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)
Gentlemen:
On October 10, 1986, we notified you by our letter logged TXX-6018 of a deficiency involving the effects of polar-organic solvents on the sealants of Conax adaptor modules and electrical penetrations which we deemcd reportable under the provisions of 10CFR50.55(e).
This is an interim report submitted to status corrective action implemented to date. Our most recent interim report was logged TXX-6101 dated November 17, 1986.
Procurement and replacement of the affected modules is continuing.
Replacement of all affected modules is currently scheduled for May 31, 1987. Our next report will be submitted on this issue no later than June 19, 1987.
i Very truly yours, h
By:
G. S. Keeley Manager, Nu ea icensing JDS/mlh c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV i
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400 Nonh Olne Street LH Mt Dallas. Tenas 75201
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Log # TXX-6283
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lilELECTRIC IISIi1N,4, February 13, 1987 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555
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)
Gentlemen:
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-6181 dated December 18, 1986.
Preliminary review results have not indicated a reportable condition.
However, a review of the associated calculations is not complete. Our next report on this issue will be submitted no later than May 6,1987.
Very truly yours, 3
t-W. G. Counsil RWH/dl c - Mr. Eric H. Johnson, Region IV Mr. D. L. Kelley - RI, Region IV Mr. H. S. Phillips - RI, Region IV l
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440 North Olne Mreet i H 41 Dalla. Tese 75201 I
Log # TXX-6260 File # 10110 903.9
==
1UELECTRIC February 2, 1987 ises utow 5 n e i+rmient U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 PIPE SUPPORT INSTALLATIONS SDAR: CP-86-63 (INTERIM REPORT)
Gentlemen:
By letter logged TXX-6027, dated October 16, 1986, we notified you of a reportable item involving pipe support construction deficiencies. This is a follow-up interim report on a reportable item under provisions of 10CFR50.55(e).
Currently, the requirements for the Hardware Validation Program (HVP) have been incorporated into the applicable quality inspection procedures and personnel training has been performed to assure consistency and accuracy in the implementation of this program.
Unit 1 inspections are currently underway with an estimated completion date of September 1,1987.
Unit 2 inspections will be performed as part of the final inspections required for support certification. We anticipate submitting our first quarterly status report by April 20, 1987.
Very trul yours,
$Y W. G. Counsil i
BSD:amb c - Mr. Eric H. Johnson, Region IV i
Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 7Q DNMDf/3 l
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February 6, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 C0ATINGS FOR UNIT 2 DIESEL FUEL OIL TANKS SDAR:
CP-86-64 (INTERIM REPORT)
Gentlemen:
On Septeniber 4,1986, we verbally notified your Mr. I. Barnes of a deficiency involving the protective coatings for the Unit 2 diesel fuel oil storage tanks. We have submitted an interim report, logged TXX-6013, dated October 3, 1986.
On February 5, 1987, per a telecon with your Mr. Ian Barnes, we requested and received an extension in submitting this response until February 6, 1987.
We are continuing our evaluation of this issue with regard to the safety of plant operations. Although we believe this issue to be non-reportable, we are currently assessing the impact of Nuclear. Regulatory Commission Information Notice 87-04 on this issue. We will submit our next report on this issue no later than March 26, 1987.
Very truly yours,
/Y, hund W. G. Counsil b
L. %l?/l(Y:lft/.
By:
G. S. Keeley
- c. _ /
llanager, Nuclear L,i1 censing RWH:lw c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV y]1D(byg _
40 %rth Olne Sit teet i H Ml Dallas. leus 73201
Log # TXX-6271
_y9 File # 10110 907.6
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Ref # 10CFR50.55(e) 1tlELECTRIC
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February 6, 1987 U. S. Nuclear Regulatory Commissio..
Attn: Document Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 B0P SAFETY RELATED INSTRUMENT SET POINTS SDAR: CP-86-81 (INTERIM REPORT)
Gentlemen:
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 in Reg.
Guide 1.105, Rev. 1.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest interim report logged was TXX-6142 dated December 5, 1986.
Evaluation of this issue is being conducted by Stone & Webster Engineering Corporation under the Corrective Action Program. The Instrumentation and Control Generic Issues Report will document this evaluation and is scheduled for completion by June 30, 1987, at which time our assessment of reportability will be established.
c We anticipate submi,ttirig our next report by July 29, 1987.
Very truly yours, l
if!AL W. G. Counsil RDD/gj c - Mr. Eric H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. I. Barnes, - Region IV p.) h M i
400 North Olne Street l..H 81 Dalla. Team 75201
Log # TXX-6281 File # 10110
""" 9 908.3 9
5 Re:
10CFR50.55(e) nlELECTRIC m,%
February 13, 1987 1
cmuna na era, arm l
l U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555 i
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SEPARATION BARRIER MATERIAL ON POWER CABLES AND POWER RACEWAYS SDAR:
CP-86-83 (INTERIM REPORT) j Gentlemen:
i j
On December 8,1986, we verbally notified your Mr. Ian Barnes of a deficiency involving the use of Separation Barrier Material (SBM) on power cables and power raceways.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-6195, dated January 5, 1987.
i We are continuing to evaluate the possibility that the conductor temperature of some power cables may have exceeded the insulation temperature rating.
Currently, the evaluation is scheduled for completion by February 28, 1987.
The results of this evaluation are required to determine the impact of this issue upon the safety of plant operations.
i We expect to submit our next report on this issue by March 23, 1987.
+
Very truly yours, f
'lb W. G. Counsil l
WJH/dl c - Mr. Eric H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV l
Mr. H. S. Phillips, RI - Region IV
$WMNb3Gb%
400 North Olne Street
- 1. H Mi Dallas. Teus 75201
a Log # TXX-6249 File # 10110 Re: 10C b55(e)
==
L 2
E E
lilELECTRIC D 7,[*"",,,
January 30, 1987 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 STATIC COMPUTER MODEL FOR THE SAFEGUARDS BUILDING SDAR: CP-87-01 (INTERIM REPORT)
Gentlemen:
On January 14, 1987, we verbally notified your Mr. Ian Barnes of a deficiency involving an error in the finite element computer model for the Safeguards Building. The error involves a fixed support point at the roof elevation where no such support exists. This condition produces an incorrect load distribution in the computer model, which wil*3 require a reevaluation of the structural members in the building.
We are continuing our evaluation as a part of the Design Basis Consolidation Program and anticipate submitting our next report by July 29, 1987.
Very truly yours,
/jk,(
b EC W. G. Counsil l /// /
By:
U' Y Ch:$
/
G. S. Keeley C
Manager, Nuclear Licensing MCP/mlh c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV g.9C32@/ OT.25K 4m %rth Olne Street i.it Mi Dallas, lemas 75201