ML20238D074
| ML20238D074 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/30/1987 |
| From: | Edgar G NEWMAN & HOLTZINGER, TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| References | |
| CON-#188-5242 OL, NUDOCS 8801040085 | |
| Download: ML20238D074 (32) | |
Text
_ _ _ _ _ _ _ _ _
5241 rw:prq p m-
~n
,u -
.L 4
i
'[
Filed:
December 30, 1987 DOCKETED 054RC
'87 003 30 P3 :28 UNITED STATES OF AMERICA
~
NUCLEAR REGULATORY COMMISSION OFFICE CF SECi t lM f 00CKETitiG A SUtvlCE BRANCH before the ATOMIC SAFETY AND LICENSING BOARD
)
In the Matter of
)
)
TEXAS UTILITIES ELECTRIC
)
Docket Nos. 50-445-OL COMPANY et al.
)
50-446-OL
)
(Comanche Peak Steam Electric
)
(Application for an Station, Units 1 and 2)
)
Operating License)
)
APPLICANTS' NINTH PROGRESS REPORT Pursuant to the Board's " Memorandum and Order (Progress j
i Report and Notice of Available Documents)" entered June 6, 1986, j
the Applicants submit herewith their ninth " Progress Report".
\\
This Progress Report covers the period October 26, 1987 through j
December 25, 1987.
1.
CPRT Procress The Senior Review Team ("SRT") has approved and pub-lished Results Reports for 46 of the applicable 47 Issue Specific Action Plans, and for all three of the Discipline Specific Action Plans.
The only Result Report yet to be approved by the SRT is VII.a.9, Receipt and Storage of Purchase Material and Equipment 8801040095 071230 PDR ADOCK 05000445 G
paa 0503
Paga No. 2 Receiving Inspection.
This Results Report is expected to be published in January 1988.
The SRT has approved and will shortly published the Collective Evaluation Report.
The notice to CASE of the availability of the Working Files for all but two of the published ISAP and DSAP Results Reports has been made.
These notices will go out as soon as the files have been ossembled.
Responses to the Board's 14 questions have been provided for all but 7 of the published Results Reports and preparation of these responses is in process.
2.
Corrective Action Procram Five Project Status Reports (PSRs) have been issued.
The Notice of Availability of the reports and documents relied on in ea'ch of the following Project Status Reports was filed on December 18,.1987:
Large Bore Piping and Pipe Supports Small Bore Piping and Pipe Supports Cable Tray and Cable Tray Hangers Conduit Supports Trains A and B, and Train C Large than 2 Inch Diameter Conduit Supports Train C 2 Inch Diameter and Less The following PSRs are expected to be issued in January, 1988:
Pcga No. 3 I,
Mechanical l
Systems Interaction Fire Protection Civil / Structural Electrical Instrumentation and Control Heating, Ventilation and Air Conditioning (HVAC)
Equipment Qualification On November 25, 1987, via TXX-6961, TU Electric pro-vided further clarification to earlier description of the CPSES Corrective Action Program.
Several public meetings related to the Comanche Peak Steam Electric Station were held during this reporting period as follows:
November 12, 1987 - Technical meeting on FSAR review item on jet impingement December 9, 1987 - Public meeting on Project Status December 17-18, 1987 - Technical meeting between TU Electric and CASE As noted in prior Progress Reports, the foregoing information is provided with certain caveats.
The schedules 1,dentified are not the sort of firm schedules the Board may have had in mind when it issued its memorandum; such schedules do not exist and will not be created for the CPRT Programs. Some of these dates may slip for a number of reasons including some conscious decisions.
. t.
(,
s Pago No. 4 s
s The next Progress Report will be issued Spbruary 29,
, \\,
4 1988.
- ,i l
N (,
s i < %,.
TEXAS UTILITIES ELhth2IC COMPANY For The Owners of Cli3ES t
' George L! Edgar U f
Newman & Holtzinger, P. C.
1615 L. Street, N.*W.
Washington, D.C.
20036 (202) 955-6644 Attorneys for TEXAS UT'O,ITI,H ELECTRIC COMPANY s,
r.
T s
\\
r; i
s s4 1
1 g
\\
ag s,
i i
t i
(
w
\\
k
(
I l
I l
L i
+
[
'g lj i
r '
s 4
if t
l p
l\\
s 4
l.
I 4
s
-i.
i 9
-t e
i,
~ *
. s ;..
t 4
1
.i i
'1 r
/
1.
&,N N O T A T E D
' P.,* I B L I O G R A P H L,E ji Pursuant to the Board's Order of June 6, 1986, Applicants submit the attached Annotated Bibliographies of documents for the.., time period of October 26, 1987 thru December 25, 1967.
The princir
/
ples that were utilized, the documents that are annota*:ed and the /
document sources are consistent with che guidelines and procr.
/
dures that were used by Applicants in previous Annotated Bibli-
'i ographies.
i
.\\
,I ie t
/5 s
t
~,
i 1
1
_ _ _ _. _. _ _.__._----_-.- - -._ m_A
1y
- \\
- l k
10 CFR 50.55 fe) l
^
y
~]
l During the period of Cetober 26, 1987 to December 25, 1987, Applicants issued 91 letters to the NRC concerning items identi-fled as potentially reportable under the provisions of 10 CFR 50.55 (e).
The letters are categorized as follows:
A.
61 letterp - Inte::im ReDort - Evaluation to determine I
deportability is continuing.
l l
(No listing provided) l B.
15 letters - Interim ReDort - Item determined to be
,s reportable and evaluation / corrective action is continuing.
Date Letter No.
SDAR Not Subiect s
11/10/87 TXX-fi828 CP-85-13 Undetectable Failure in Engineered Safety Features Actuation System
- t. This letter trr.asmitted a report on the status of the implemen-tation of corrective actions associated with the subject defi-ciency previously reported under the provisions of 10 CFR 50.55te).-
p_gli Eq11gr No.
SDAR No.
Subiect i
10/26/87 TXX-6886 CP-87-108 Auxiliary Feedwater Pump Low Suction Pressure Trip i
This letter transmitted the results of an engineering evaluation
-concerning the spuricus actuation of the Auxiliary Feedwater Pump suction pressure switches.
This condition was determined to be rep (rtable under the provisions of 10 CFR 50.55(e).
A description of the condition and its safety implications is prov ided.
Evaluation to determine corrective action is con-tinuing.
t T
Datt kg h ; No.
SDAR No.
Subiect 10/21/87 TXX-6893 CP-87-52 Cable Tray Splices / Connections and Field Drilled Cable Tray Holes
/
e -
f This letter transmitted a report which provided the status of corrective action associated with a condition previously reported under the provisions of 10 CFR 50.55 (e).
Date Letter No.
SDAR No.
Subiect 11/10/87
~ TXX-6922 CP-82-09 Solid State Detection System Undetectable Failure This letter provided a supplemental report to status corrective actions concerning an item previously identified as reportable under the provisions of 10 CFR 50.55(e).
Date Letter No.
SDAR No.
Subiect 11/5/87 TXX-6928 CP-85-36 Train "C" Conduit Support This letter transmitted the results of on engineering evaluation concerning the installation of non-safety related conduit less than 2 inch in diameter and required to met seismic qualifi-cations.
This condition was determined to be reportable under the provisions of 10 CFR 50.55(e).
The transmitted report included a description of the condition and its safety impli-cation.
The current status of the implementation of corrective actions was provided and a final report is to follow the com-pletion of their implementation.
I QA11 Letter No.
SDAR No.
Subiect 11/20/87 TXX-6944 CP-87-03 6.9KV Switchgear Installation This letter provided an update of the schedule for implementation of corrective actions associated with a condition previous reported under the provision of 10 CFR 50.55(e).
Ratt Letter No.
EDAR No.
Subiect 11/16/87 TXX-6951 CP-87-58 Computer Modeling Error:
RELAP-3 l
L This letter transmitted the results of an engineering evaluation regarding an error in the calculation of pipe rupture blowdown by the RELAP-3 computer code.
This condition was determined to be reportable under the provisions of 10 CFR 50.55(e).
A l,
description of the condition and safety implications was pro-vided.
An additional response will be provided to document corrective actions.
l Q3j;,g Letter No.
SDABA Subiect 12/1/87 TXX-6955 CP-87-100 Containment Piping l
Penetrations This letter transmitted the results of an engineering evaluation concerning the lack of over pressure protection on three contain-ment piping penetrations.
This condition was determined to be reportable under the provisions of 10 CFR 50.55(e).
A description of the problem, its safety implications and correc-tive actions are included in the report.
A final report will be submitted to provide the schedule of for implementation of corrective actions.
Date Letter No.
SDAR No.
Subiect 11/16/87 TXX-6968 CP-85-35 Cable Tray Hanger Design This report was submitted to provide the status of the implemen-tation of corrective actions for an item previously reported under the provisions of 10 CFR 50.55(e).
Date Letter No.
SDAR No.
Subiect 11/24/87 TXX-6970 CP-85-36 Train "C" Conduit Supports This report concerning an item previously reported under the provisions of 10 CFR 50.55(e) was submitted to provide a clarifi-cation to ensure the NRC Staff's understanding that the report-able conditions associated with Train "C" conduit supports are limited to "two-inch and under" conduit sizes.
Date Letter No.
SDAR No.
Subiect 12/2/87 TXX-6992 CP-87-28 Condensate Storage Tank Over-pressurization This letter transmitted the results of an engineering evaluation concerning the potential for overfilling and subsequent over-pressurization of the Condensate Storage Tank.
This condition was determined to be reportable under the provisions of 10.CFR
_4-
.8 50.55(e).
A description of the condition and its safety impli-cation in provided.
A final report describing the corrective action and. implementation schedule will be submitted.
Egtg Letter No.
SDAR No.
Subiect 12/14/87 TXX-7031 CP-86-46 Gould Battery Racks CP-86-76
'This letter transmitted the results of an engineering evaluation concerning design changes to the Gould battery racks which had not been evaluated by the vendor.
This. condition was determined to be reportable under the provisions of 10 CFR 50.55(e).
The letter provided a description of the condition, its safety implications and corrective actions.
A further report will be submitted to provide the schedule for implementation of correc-tive actions.
Date Letter No.
SDAR No.
Subiect 12/2/87 TXX-7032 CP-87-23 Loose Conduit Unions This letter provided a new schedule for implementation of correc-tive action associated with the subject condition previously reported under the provisions of 10 CFR 50.55(e).
QAtg Letter No.
SOAR No.
Subiect 12/8/87 TXX-7046 CP-87-55 Containment Spray Pump Recirculating Piping This letter transmitted the results of an engineering evaluation of containment spray recirculation piping designed and installed as seismic class 5 as opposed to ASME Code Class 2.
This con-dition was determined to be reportable under the provisions of 10 CFR 50.55(e).
The report provided a description of the problem, its safety implication and corrective actions.
A further report will be submitted to provide a schedule for the implementation of corre,ctive actions.
Date Letter No.
SDAR No.
Subiect 12/11/87 TXX-7081 CP-87-29 Component Cooling Water (CCW) Isolation Following Reactor Coolant Pump (RCP)
Thermal Barrier Rupture - _ _ _ - _ _ _ - - - _ _ _ _
9 This letter provided the results of an engineering evaluation regrading the use of non-class lE instrumentation and controls for the initiation of CCW isolation following a RCP thermal barrier rupture.
This condition was determined to be reportable under the provisions of 10 CFR 50.55(e).
This report provided a description of the problem, its safety implications and cor-rective actions.
The schedule for the implementation of cor-rective actions will be submitted.
C.
13 letters - Final Reoort - Deficiency is not reportable.
(See listing as follows)
Date Letter No.
SDAR No.
Subiect 10/27/87 TXX-6883 CP-87-86 ll8VAC Circuit Breaker Sizing This is a final report of a deficiency involving the sizing of three branch circuit breakers located in Class 1E ll8VAC instru-mentation distribution panels.
The subject circuit breakers are class lE circuit breakers in series with non-class lE breakers feeding a non-class lE load.
Class lE breaker sizing includes a factor to avoid nuisance tripping of vital loads.
This factor was inadvertently omitted on these three breakers.
- However, since these three breakers are feeding non-class lE loads and, as presently sized, are adequate to assure that a fault or overload on the non-class lE system will not degrade the class 1E system.
Therefore, it was determined that this condition is not report-able under the provisions of 10 CFR 50.55(e).
Date Letter No.
SDAR No.
Subiect 10/27/87 TXX-6887 CP-87-107 Auxiliary Feedwater Design Pressure This letter transmitted a final report concerning a condition identified during the design validation process.
It was found that the design pressure of the motor driven auxiliary feedwater pumps and their bypass breakdown orifices was less than the calculated maximum system pressure by an amount of 13.1 psig.
However, the pump manufacture confirmed that these components could sustain the calculated over pressure without damage; therefore, this condition was determined to be not reportable under the provision of 10 CFR 50.55(e). l
t Qatt Letter H2A SDAR No.
Subiect 10/27/87 TXX-6908 CP-87-22 Liner Attachment Material. Requirements:
Impact' Testing This letter transmitted the results of an engineering fatigue / fracture analysis performed to detecmine if a postulated crack in the containment liner attachments would impair the integrity of the containment linear.
The analysis of postulated cracks in the heat affected zone of the fillet welds between the linear.and attachment plates shows that the liner integrity would not be compromised even if the attachment plate had a lower toughness than the linear.
Based on this analysis, it has been determined that this condition is not reportable under the provisions of 10 CFR 50.55(e).
Qatt Letter No.
SDAR No.
Subiect 11/6/87 TXX-6927 CP-87-18 Component Cooling Water (CCW) Heat Exchanger Seismic Qualification This letter transmitted a report of the results of an engineering i
reanalyzes of Unit 1 and Unit 2 CCW heat exchangers utilizing the as-built piping nozzle loads.
Calculations for both unit's CCW heat exchangers demonstrate that they are acceptable under the as-built loading without modification.
The engineering evalu-i I
ation of this condition concluded that it is not reportable under the provisions of 10 CFR 50.55(e).
Qaig Letter No.
SDAR No.
Subiect 11/13/87 TXX-6963 CP-87-01 Static Computer Modeling for the Safeguards Building This letter transmitted the results of an engineering evaluation concerning a error in the finite element computer model for the Safeguards Building..This condition was determined to be not reportable under the provisions of 10 CFR 50.55(e).
Data Letter No.
SDAR No.
Subiect 11/24/87-TXX-6967 CP-87-42 Qualification of Incore Thermocouple i
This letter transmitted the results of an engineering evaluation concerning a question regrading the environmental qualification of the incore thermocouple.
This item was determined to be not reportable under the provisions of the 10 CFR 50.55(e).
EAlg Letter No.
SDAR No.
Subiect 11/24/87 TXX-6981 CP-87-27 Galvanic Corrosion in Service Water System This letter transmitted the results of an engineering evaluation concerning the use of dissimilar materials in the Service Water System.
This condition was determined to be not reportable under the provisions of 10 CFR 50.55(e).
Qatt Letter No.
SDAR No.
Subiect 11/24/87 TXX-6989 CP-87-63 Pipe Weld Inspection Criteria This letter transmitted the results of an engineering evaluation concerning a condition involving inspection attributes which were added to the Mechanical Erection Specification and which were not applied to existing weld installations.
It was determined that this condition is not reportable under the provisions of 10 CFR 50.55(e).
Date Letter No.
SDAR No.
Subiect 12/8/87 TXX-7045 CP-87-24 Containment Liner Nelson Stud Bending This letter transmitted the results of an engineering evaluation which established that the bending of Nelson stud anchors attached to the containment linear would not cause stresses in adjacent anchors or in the linear plates to exceed allowable stress limits.
This condition was determined to be not report-able under the provisions of 10 CFR 50.55(e).
Date Letter No.
SDAR No.
Subiect
,12/14/87 TXX-7054 CP-87-ll8 Steam Generator Blowdown Isolation This letter transmitted the results of an engineering evaluation regarding the use of non-nuclear safety detection instrumentation and controls to isolate the steam generator blowdown lines.
This condition was determined to be not reportable under the pro-visions of 10 CFR 50.55(e)..
s Date Letter No.
SDAR No.
Subiect l
12/9/87 TXX-7056 CP-87-73 Unsound Concrete Mortar This letter transmitted the results of an engineering evaluation concerning the use of unsound concrete mortar at construction joints.
This condition was determined to be not reportable under the provisions of 10 CFR 50.55(e).
Date Letter No.
SDAR No.
Subiect 12/14/87 TXX-7063 CP-87-33 Auxiliary Feedwater Pump Motor Fans This letter transmitted the results of an engineering evaluation concerning the incorrect rotation direction for the auxiliary feedwater pump motor fans. This condition was determined to be j
not reportable under the provisions of 10 CFR 50.55(e).
Date Letter No.
SDAR No.
Subiect 12/14/87 TXX-7082 CP-87-87 CVCS Relief Valve Piping This letter transmitted the results of an engineering evaluation concerning the potential for over-pressurization of the CVCS letdown line due to the piping configuration of CVCS relief valves.
This condition was determined to be not reportable under the provisions of 10 CFR 50.55(e).
D.
2 letters - Final ReDort - Deficiency is reportable and i
corrective action taken.
(See listing as follows)
EAig Letter No.
SDAR No.
Subiect 11/13/07 TXX-6954 CP-87-50 Turbine Driven Auxiliary Feedwater Pump Bearing Temperature This letter transmitted the results on an engineering evaluation of abnormally high thrust bearing temperatures on the turbine driven auxiliary Feedwater Pump.
This condition was determined to be reportable under the provisions of 10 CFR 50.55(e).
A description of the problem, its safety implications and cor-i rective actions are included in the report. I
Date Letter No.
SDAR No.
Subiect 11/13/87 TXX-6966 CP-86-53
' Seismic Design of Conduit This letter transmitted the corrective actions and an implemen-tation schedule for a condition previously reported under the provisions of 10 CFR 50.55(e).
9 I
l
\\
i._ _ _-
n
8 RESPONSES TO NRC INSPECTION REPORT NOTICE OF VIOLATION / NOTICE OF DEVIATION The following correspondence was issued by Applicants to the NRC concerning inspection reports, during the period of October 26, 1987 to December 25, 1987:
Date Letter Subiect 10/23/87 TXX-6753 Request for Additional Information Regarding Inspection Report 50-445/86-26 and 50-446/86-22 This letter transmitted a revised response to NOV and NOD Items B and C attached to the subject inspection report.
Date Letter Subiect 11/2/87 TXX-6888 Revised Date of Full Compliance for Notice of Violation Item A (445/8416-V-01)
This letter transmitted a revised date for the completion of corrective action rework activities on cable tray hangers.
EAtg Lettgr Subiect 11/6/87 TXX-6895 Request for Additional Information Regarding Inspection Report:
50-445/84-32 and 50-446/84-11 This 1.vtter transmitted a response to the NRC staff's request for addit! Gt.1 information concerning TU Electric's initial response to NOV Items 1 and 2 attached to the subject inspection report.
Date Letter 3,ubiect 10/30/87 TXX-6899 Enforcement Action (EA) Number 86-09 Appendix B, Item 1.b.2 This letter transmitted a revision to TU Electric's original response to the subject enforcement action item.
]
f Date Letter Subiect 11/6/87 TXX-6917 Response to Inspection Report Nos.
50-445/87-13 and 50-446/87-10 -
i This letter transmitted the response to the Notice of Violation attached to the subject inspection report.
Date Letter Subiect 11/23/87 TXX-6937 Response to NRC Inspection Report Nos. 40-445/87-16 and 50-446/87-13 This letter transmitted TU Electric's response to the Notica of Violation and Deviation attached to the subject inspection report.
Date Letter Subiect 11/13/87 TXX-6938 Revised Date of Full Compliance for Notice of Violation (NOV) Item B (50-445/86-22-V-04)
This letter transmitted a revised completion date for corrective actions associated with the subject Notice of Violation.
Date Letter Subiect 12/7/87 TXX-6939 Response to NRC Inspection Report Nos. 50-445/87-18 and 50.446/87-14 This letter transmitted TU Electric's response to the Notice of Violation and Deviation attached to the subject inspection report.
Date Letter Subiect 11/20/87 TXX-6964 Supplemental Information Concerning Base Material Defects Inspection Report 50-445/86-03 and 446/86-02 This letter transmitted, in response to an NRC staff request, the schedule of a verification plan for a representative sample of pipe support welds.
Date Letter Subiect 11/20/87 TXX-6993 Revised Date of Full Compliance for Notice of Violation Item A (445/8622-V-01, 446/8620-V-03)
This letter provided a revised schedule for the completion of corrective actions for the subject Notice of Violation item. --._-_-_
a Date Letter subiect 11/25/87 TXX-6997 Revised Date of Full Compliance for Notice of Deviation Item B (445/86-03-D-18)
This letter transmitted a revised date for completion of cor-rective actions responsive to the subject deviation.
Date Letter Subiect 11/30/87 TXX-7013 Revised Date of Full Compliance for Notice of Violation Item E (445/8607-V-22)
This letter transmitted a revised date for the completion of corrective actions associated with the subject violation.
Date Letter Subiect 11/30/87 TXX-7014 Revised Date of Full Compliance for Notice of Violation (NOV), item C.2 (446/8522-V-07)
This' letter transmitted a revised completion date for the cor-rective actions to the subject Notice of Violation item.
Date Letter Subiect 11/30/87 TXX-7015 Revised Date of Full Compliance for Notice of Violation (NOV), Item A (445/8711-V.02; 446/8709-V-02)
This letter transmitted a revised completion date for the cor-rective actions to the subject Notice of Violation item.
Date Letter Subiect 12/1/87 TXX-7021 Inspection Report NOV Item 445/8607-D-OI Revised Date for Submittal of Updated Response to SDAR CP-83-08 This letter transmitted a revision to previous commitment dates associated with corrective actions taken in response to the subject NOV.
- li' -
CPRT/ CORRECTIVE ACTION PROGRAM The following correspondence was issued by Applicants to the NRC concerning CPRT and/or the Corrective Action Program during the time period of October 26, 1987 - December 25, 1987:
Raig Letter Subiect 10/30/87 TXX-6859 Request for Additional Information on ISAP Results Report II.c This letter transmitted a response to a set of two questions from the NRC regarding statements made in the subject results report.
Raig Letter Subiect 11/5/87 TXX-6926 Project Status Reports Referenced Procedures This letter transmitted to Mrs. J. Ellis, President CASE, with a copy to the NRC, the latest revisions of Field Verification Method procedures, Quality Control Inspection procedures and the erection specification referenced in the Large Bore and Small Bore Piping and Pipe Supports Project Status Reports.
l Haig Letter Subiect 11/18/87 TXX-6952 Transmittal of Project Status Report for Conduit Supports Trains A and B and Train C Larger than 2-inch Diameter l
This letter transmitted the subject report to the US Nuclear Regulatory Commission.
Daig Letter Subiect i
11/25/87 TXX-6961 CPSES Program Descriptions l
Clarification 1
This letter transmitted several clarifications of statements made l
in previous submittals to the US NRC staff which described the PCEVP and the CAP fire protection efforts.
These clarifications were provided by TU Electric to assist the NRC Staff in reviewing the PSR's and other submittals. ________ _________ __________ -___ _-_ _ __________ ______
.s Date Letter Subiect 11/23/87 TXX-6979 Meeting Notice This letter transmitted to the US NRC a notice of meeting between CASE and TU Electric regarding the CAP for Piping and Pipe Supports, Cable Tray Hangers and Conduit and Conduit Supports.
Date Letter Subiect 12/7/87 TXX-7005 CPRT Results Report This letter transmitted the Results Report for ISAP V.b and DSAP VII.
1, CYGNA No correspondence was issued by Applicants concerning CYGNA during the time period of October 26, 1987 - December 25, 1987.
f a
n l
l 1
.i
e INTERNAL AND TECHNICAL AUDITS l
The following internal and technical audit reports of CPSES Engineering and Construction activities were issued in the period from October 26, 1987 through December 25, 1987:
Number:
ATP-87-47 Date:
10/26/87-10/30/87 Report Date:
12/3/87 i
Scope:
This audit was performed at the CPSES site to access the adequacy of Impell design validation activities involving cable tray system and hangers.
Number:
ATP-87-48 Date:
9/14/87-9/18/87 Report Date:
10/29/87 Scope:
This audit was performed at SWEC, Boston to assess the adequacy of design validation activities in the Civil / Structural disciplines.
Number:
ATP-87-49 Date:
11/2/87-11/6/87 Report Date:
12/3/87 Scope:
This audit was performed at Westinghouse, Pittsburgh, PA to assess the adequacy of design validation activi-ties for Class 1 pipe stress analyses.
Number:
ATP-87-51 Date:
9/28/87-10/2/87 Report Date:
10/30/87 Scope:
This audit was performed at Ebasco, New York, to assess the adequacy of their design validation activi-ties for Unit 1 HVAC systems.
Number:
ATP-87-52 Date:
10/12/87-10/16/87 Report Date:
11/13/87 Scope:
This audit was performed at Ebasco, New York, to assess the adequacy of their design validation activi-ties in the HVAC-Civil / Structural discipline. _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _
a Number:
ATP-87-53 Date:
10/12/87-10/16/87 Report Date:
11/13/87 Scope:
This audit was performed at Ebasco, New York, to assess the adequacy of their validation activities for Unit 1 conduit system and supports.
Number:
ATP-87-54 Date:
10/12/87-10/16/87 Report Date:
11/13/87 Scope:
This audit was performed at Ebasco, New York, to assess the adequacy of design validation activities for Unit 1 Cable Tray Systems and hangers.
Number:
ATP-87-58 Date:
9/28/87-10/2/87 Report Date:
10/30/87 Scope:
This audit was performed at SWEC, Toronto, Canada, to assess the adequacy of design validation activities for Unit 1 large bore pipe / supports.
Number:
ATP-87-59 j
Date:
10/5/87-10/9/87 Report Date:
11/10/87 Scope:
This audit was performed at SWEC, Cherry Hill, N.
J.,
to assess the adequacy of design validation activities in the Civil / Structural discipline.
j l
Number:
ATP-87-60 l
Date:
10/19/87-10/23/87 Report Date:
11/25/87 Scope:
This audit was performed at SWEC, New York, to assess the adequacy of Unit 1 large bore pipe / support requalification activities.
Number:
ATP-87-61 i
Date:
10/26/87-10/30/87 Report Date:
11/19/87 Scope:
This audit was performed at Impell, Fort Worth, TX, to assess the adequacy of their design validation activi-ties involving Unit 1 Environmental Equipment Qualifi-cation.
I 1
f Number:
ATP-87-69 Date:
11/2/87-11/6/87 Report Date:
11/25/87 Scope:
This audit was performed at CPSES to assess the adequacy of Ebasco design validation activities involving conduit supports.
Number:
ATP-87-521 Date:
8/17/87-9/29/87 Report Date:
10/30/87 Scope:
This audit was performed at CPSES to assess the adequacy of implementation of CPRT recommended cor-rective actions related to flexible conduit and various aspects of electrical separation (ISAP's I.b.1, I.b.2, I.b.3, and I.b.4).
Number:
ATP-87-522 Date:
8/17/87-9/25/87 Report Date:
10/16/87 Scope:
This audit was performed at CPSES to assess the adequacy of implementation of CPRT recommended cor-rective actions related to maintenance of air gap between concrete structures (ISAP II.c).
Number:
ATP-87-523 Date:
8/24/87-10/6/87 Report Date:
11/2/87 Scope:
This audit was performed at CPSES to assess the adequacy of implementation of CPRT recommended cor-rective action related to anchor bolts in steam generator upper lateral supports (ISAP V.b)
Number:
ATP-87-535 Date:
10/26/87-11/4/87 Report Date:
12/3/87 Scope:
This audit was performed at CPSES to assess the adequacy of implementation of CPRT recommended cor-rective actions related to the audit program and auditor qualifications; TUE QA/QC actions (ISAP VII.a.4)..-
4
. Number:
ATP-87-537 Date:
10/19/87-11/4/87 Report Date:
11/25/87 Scope:
This audit was performed at CPSES to assess the adequacy of implementation of CPRT recommended cor-rective action related to Hilti Bolt installation
-(ISAP VII.b.4).
Number:
TCP-87-24 Name:
CPSES Field Verification Method Program (PVM)
Date:
07/22-10/30/87 Report Date:
11/13/87 Scope:
This audit was performed to verify adequacy and implementation of the Field Verification (FVM)
Program.
The performance of the audit consisted of a technical / procedural review of each FVM, a physical re-verification of the "As-Built" data versus actual field conditions, and verification of.
training / qualification of the Lead Contractor's walkdown personnel.
Number:
TCP-87-36 Name:
CPSES Record Management Date:
10/05-16/87 Report Date:
11/02/87 Scope:
This audit was performed to verify the adequacy and implementation of the CPSES Records Management Program.
This review included verification, storage i
control, storage facilities, micrographics, indexing and training of personnel.
Number:
TCP-87-37 Name:
Post Construction Hardware Validation Program (PCHVP) i Date:
10/12-21/87 Report Date:
11/18/87 Scope:
This audit was performed to evaluate the program requirements for the Post Construction Hardware Validation Program (PCHVP).
This audit did not include the implementation of the FVM process.
i 1 1
Number:
TCP-87-38.
Name:
Instrumentation and Control 1Date:
10/19-21/87 Report Date:
10/28/87 Scope:
This audit was performed to verify the implementation of the Instrumentation and Control' Program.
" Additionally included was Stop Work Orders.
This review included verification of-Quality Control Inspectors and Craft personnel training, issuance and control of Stop Work Orders generated by Construction and Quality Assurance, Measurement-and Test Equipment, Pressure Testing, Inspection Reports, and Reporting of Nonconformances.
Number:
TCP-87-39 Name:
Specification Review (SPADU) Program Date:
10/19-27/87 Report Date:
11/23/87 Scope:
This audit was performed to evaluate the Specification Procedure and Drawing Update (SPADU) Program activities being performed by applicable Lead Contractors for the Phase I Installation specifications review and approval.
Number:
TCP-87-40 Name:
_ Engineering Assurance Date:
10/26-28/87 l
Scope:
This audit was performed to verify the CPE -
Engineering Assurance (CPE-EA) surveillance and monitoring of Lead Contractors.
This audit also _
verified the corrective action commitments for audit T1N-86-03 and CAR-86-11 have been adequately implemented by CPE-EA.
l l
t MISCELLANEOUS The following additional correspondence was issued by Applicants to the NRC during the time period of October 26, 1987 - December 25, 1987:
Date Letter Subiect 10/27/87 TXX-6885 Environmental Qualification Program Revision Definition of Mild Envi-ronment at Comanche Peak Steam Electric Station This letter transmitted a revision of a document, submitted for NRC approval, entitled " Implementation of a Mild Environmental Equipment Category at CPSES" and an advanced copy of an FSAR change concerning the CPSES Environmental Qualification Program.
Date Letter Subiect 10/22/87 TXX-6894 Fire Protection Deviation This letter transmitted a deviation to 10 CFR 50 Appendix R Section III.G.2 concerning solenoid valves for the Main Steam Isolation Valve (MSIV) actuators.
Date Letter Subiect 10/28/87 TXX-6896 Transmittal of Licensed Operator Examination Reference Material This letter documented the transmittal of reference material request by the NRC for their use in administering the operator licensing examinations.
Date Letter Subiect 11/20/87 TXX-6909 Inspection of Coated Welds This letter advised the NRC that TU Electric had completed their inspection of coated weld samples and that the results of the inspection are available for NRC review.
J Date Letter Subiect 11/20/87 TXX-6911 Transmittal of FSAR Amendment 65 This letter transmitted the subject FSAR Amendment to the NRC.
Enig Letter Subiect 11/5/87 TXX-6936 Transmittal of Information Associated with WCAP 11331, CPSES Thermal / Hydraulic Analysis of Fire Safe Shutdown Scenario This letter transmitted the subject information in response to a verbal request from the NRC Staff.
Date Letter Subiect 12/3/87 TXX-7004 Response to RFI on Request for Extension of Construction Permit No. CPPR-127 This letter transmitted information requested by the NRC Staff concerning groundwater wells at and around CPSES.
Egig Letter Subiect 12/8/87 TXX-7043 Comments on Proposed Draft Standard Review Plan 3.6.3 " Leak Before Break Evaluation Procedures" This letter transmitted TU Electric's comments on the subject draft Standard Review Plan section.
Egig Letter Subiect 12/14/87 TXX-7092 Transmittal of Revised Emergency Plan Procedures This ' letter transmitted copies of the subject procedures to US Nuclear Regulatory Commission.
I 1 i
___.---_---..-..-_-_-________._-_-__--_a
a OTHER On behalf of TU Electric, R. A. Wooldridge has submitted various documents to the ASLB for their information.
These documents include'the following for the time period of October 26, 1987 -
December 25, 1987:
11/2/87 Notification of transmittal of Project Status Report for "Small Bore Piping and Pipe Supports",
Revision O.
11/2/87 Notification of transmittal of Project Status Report for "Large Bore Piping and Pipe Supports",
Revision 0.
11/6/87 Notification of transmittal of W.G.
Counsil letter to J. Ellis which transmitted the latest revisions of Field Verification Method Procedures, Quality Inspection Procedures and the erection specification referenced in the Large Bore and Small Bore Piping and Pipe Supports PSRs.
11/6/87 Notification of transmittal of
" Cable Tray and Cable Tray Hangers" PSR, Revision O.
11/9/87 Notification of transmittal of approved results reports I.c, II.a and II.d.
11/11/87 Notification of transmittal of
" Conduit Supports Train C 2-inch Diameter and Less" PSR, Revision O.
11/18/87 Notification of transmittal of
" Conduit Supports Trains A and B and Train C Larger than 2-Inch Diameter" PSR, Revision O.
11/23/87 Notification of transmittal of a notice of meeting between TU Electric and CASE to discuss the CAP relative to Piping and Pipe Supports, Cable Tray Hangers, and Conduit and Conduit Supporto.
l l
l lA 12/2/87 Transmittal of additional c
information regarding the 1978 MAC Report.
12/7/87 Notification of transmittal of approved results reports for ISAP l
V.b and DSAP VII.
The following report was issued by the CPRT Overview Quality Team j
(OQT) during the time period of October 26, 1987 - December 25, 1987:
j 11/12/87 Memorandum from J. V. Neeley to J.
W. Beck transmitting the results of followup work, performed during October and November, relative to specific recommendations in the OQT final report.
4 9 - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _
The following listing represents the consultants' reports received by CPSES Engineering during the time period of October 26, 1987 - December 25, 1987:
Vibration Analysis of Containment Spray Pumps Clarification of SWEC Concerns Regarding SSI Study Nozzle / Equipment Stiffness Values - Final Report Radiological Effluent Monitoring Functional Specification-Final Issue.
Specific Technical Issue Report for Reinspection of Coated Welds Mechanical GIR-Overpressure Protection Final Report for the Auxiliary Electrical Building Design Verification of Floor Response Spectra.
Station Service Water System Corrosion Evaluation 4
e 9
e
. 1 I
L
n---,
l
)
DOLKEILD i
UNITED STATES OF AMERICA U5NRC NUCLEAR REGULATORY COMMISSION
'87 EC 30 P3 :28 befo're the 0FF ICf. Ci set.nr i Ah f ATOMIC SAFETY AND LICENSING BOARD 00CK[ TING & SDMCI.
BRANCH
)
In the Matter of
)
Docket Nos. 50-445-OL
)
50-446-OL TEXAS UTILITIES GENERATING
)
COMPANY et al.
)
)
(Application for an.
(Comanche Peak Steam Electric
)
Operating License)
Station, Units 1 and 2)
)
)
CERTIFICATE OF SERVICE I, Thomas A.
Schmutz, hereby certify that the foregoing Applicants' Ninth Progress Report was served this 30th day of December 1987, by mailing copies thereof (unless otherwise indi-cated), first class mail, postage prepaid, to:
- Peter B.
Bloch, Esq.
Assistant Director for Chairman Inspection Programs U.S. Nuclear Regulatory Comanche Peak Project Division Commission U.S. Nuclear Regulatory Washington, D.C.
20555 Commission P.O.
Box 1029
- Alan S. Rosenthal, Esq.
Granbury, Texas 76048 Chairman Atomic Safety and Licensing
- Juanita Ellis Appeal Panel President, Case U.S.
Nuclear Regulatory 1426 South Polk Street Commission Dallas, Texas 74224 Washington, D.C.
20555 William H. Burchette, Esq.
- B.
Paul Cotter, Jr.,
Esq.
Herron, Burchette, Ruckert, &
Chairman Rothwell Atomic Safety and Licensing Suite 700 Board Panel 1025 Thomas Jefferson Street, U.S.
Nuclear Regulatory N.W.
Commission Washington, D.C.
20007 Washington, D.C.
20555 Asterisk indicates service by hand or overnight courier
~
- _-__- _ - - -_--_,h.
,k
- q '
6 2-A 4
- Mr. William L. Clements Joseph Gallo, Esq. %
Decketing & Service Branch Isham,elincoln & Beale S(
U.S. Nuclear Regulatory 1150 Connecticut Avenue, N.W.
Commission Suite 1100 L"i Washington, D.C.
20555 Washington, D.C.
20036
- Billie Pirner Garde
- Janice E. Moore, Esq.
y Government Accountability Office'of the General
't Project Counsal s
i Midwest Office U.S. Nuc' lear Regulatory
'b 104 E. Wisconsin Avenue - B Commishion Appleton, Wisconsin 54911-4897 Washington, D.C.
20555 Renea Hicks, Esq.
- Anthony Roisman, Esq.
Assistant Attorney General 1401 diew jYork Avenue,h' N.W.
Environment Project Division Suith! 606 Washington, D.C.
(N005 Capitol Station s
P.O.
Box 12548 i
i l
Austin, Texas 78701 Lanny A.g'Sinkin (
Christic Instit, tite j
Robert A. Jablon, Esq.
1324 North Capitd1 Street h
Spiegel & McDiarmid Washington, D.C.
2000*2 4
3 1350 New York Avenue, N.W.
g s
Washington, D.C.
20005'-4798 Nancy Williams
'\\
CYGNA Energy Services, Inc.
- Elizabeth B. Johnson 2121 N. California Boulevard Oak Ridge National Suite 390 Laboratory Walnut Creek,l Calify nia 94596
.}
5 P.O. Box X, Building 3500 4
Oak Ridge, Tennessee 37830 David R. Pigott,.Esq.
Orrick, Herrington & Sutcliffe
- Dr. Walter H. Jordan 600? Montgomery Street c/o Carib Terrace Motel San Francisco, California 94111 522 N. Ocean Boulevardj
),
t Pompano Beach, Florida 33062
- RobePc A. Wooldridge', Esq.
Worsham, Forsythe, Sarocls &
Wooldridge' Robert D. Martin n
Regional Administrator, i
2001 Bryan Tower
\\7 y
?
Regional IV Suite 3200 5
s U.S. Nuclear Regulatory Dallas, Texas 75201 Comrnission 611 Ryan Plaza Drive
- W.G.
Couns'il' Suite 1000 Executive Vice President Arlington, Texas 76011 Texas Utilities Electric -
General Division
- Dr.
Kenneth A. McCollom i
400 N.t0h ve, L.B.
81 Administrative Judge Dallas,V,exas 75201 1107 West Knapp f,\\
Stillwater, Oklahoma 74075 t
/
/
, h!, un t h....b.I.,....l7 Thomas A.
Schmutz Dated:
December 30, 1987
/ A
',s
,u
/)
e
,