ML20236C279
| ML20236C279 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/19/1987 |
| From: | Ellis J Citizens Association for Sound Energy |
| To: | Bloch P, Jordan W, Mccollom K Atomic Safety and Licensing Board Panel |
| References | |
| CON-#487-4628 OL, NUDOCS 8710270082 | |
| Download: ML20236C279 (62) | |
Text
-
YbA b!
c., 'A S E
f pp}IEp CORRESP,0NDEN.CK C
214/946-94L6 (CITIZENS ASSN. FOR SOUND ENERGY)
W OCT 22 A7s3
]
October 19, 1987 3
0FFICE OF shat 14gy l
BGCMETinG & SERvicr' SRANCH Administrative Judge Peter B. Bloch Dr. Kenneth A. McCollom U. S. Nuclear Regulatory Commission 1107 West Knapp Street Atomic Safety & Licensing Board Stillwater, Oklahoma 74075 Washington, D.C.
20555 l
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.
j Application for an Operating License Comanche Peak Steam Electric Station Units 1 and 2 Docket Nos. 50-445 and 50-446 - 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 October 1, 1987.
It is our intention to periodically continue to provide these SDAR's unle.ss the Board indicates otherwise.
Respectfully submitted, CASE (Citizens. Association for Sound Energy) 4-tt >
MO dw)
P v(Mrs.) Juanita Ellis President cc:
Service List, with Attachments 8710270082 871019 PDR ADOCK 05000445 s { ()
o PDR.
,)
t-M Loa # TXX-6799 lllllll'll' ':llllllll FiIe # 10110
~
903.I1 3
3 Ref.
TUELECTRIC September 28, 1987 William G. (,ounu.l Execunve Vnce Freuden U. 5. Iluclear Pegolatory Commission A fift :
Document Control Oest Washington, D.C.
20555
SUBJECT:
COMAf1CHE PEAK STEAM ELECTRIC STATION (CP5E5)
DOCKET N05. 50 da5 afl0 Sn.aa6 0UALICIE0 EQUIPMErli OUTSIDE CONTAINMErlT SDAR:
C-84-1; (INTERif t REPORT)
Gentlemen:
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 e potentially reportable item under provisions of 10CFR50.55(e).
Our latest interim report, logged Txx-6588, was submitted on July 28, 1987.
The evaluation of this issue with regard to safety of plant operations is continuing.
We will submit our next report no later than November 30, 1987.
Very truly yours,
'l ll$}
W. G. Counsil BSD/amb c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) j.
l i
1 500 North Olive S: rect LB SI Da!Ln. Teus 75.'01 L
o e
.c
- J i
- ~
Log # TXX-6806 F
File # 10110 903.11
=
=
Ref # 10CFR50.55(e) l 1UELECTRIC October 9, 1987 William G. Counsli Emutne Vwe Persnient 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 CONDUIT SUPPORT SPANS SDAR:
CP-85-19 (FINAL REPORT) 4 Gentlemen:
On October 21, 1986, we notified you by our letter logged TXX-6046 of a defici'ency regarding the use of a nonrepresentative sample in determining typical conduit span calculations which we deemed reportable under the provisions of 10CFR50.55(e). Our last interim report was logged TXX-6625, dated August 12, 1987.
In our last report we described an alternative approach concerning yield stress values and thread section properties used to calculate conduit stress.
We have taken this alternative approach to calculate conduit stress using the lowest published yield stress (Fy) of commercially available steel and a revised thread section property to obtain revised design criteria for the conduit support spans.
We have completed our evaluation of conduit support span installations utilizing the revised design criteria and identified no overstressed conduit spans.
Based upon the results of this evaluation and the design criteria document revisions previously completed, we have concluded l
that no-further corrective actions or physical rework is required.
j Please note, the cumulative effects of all conduit supports design construction and quality issues are being reported under the reportable i
deficiency, logged SDAR: CP-85-34, " Conduit Support Design."
{
This.is our final report on this issue.
Supporting documentation is available at the CPSES site for your Inspector's review.
l Very truly yours, l
V W. G. Counsil DAR/gj i
c - Mr. R. D. Martin, Region IV l
Resident Inspectors, CPSES (3) 4 1
a nao, oine streer ta si canu. reus moi
f; W3 es M
Log # TXX-6771 F9 File # 10110 908.3
_r
=
Ref # 10CFR50.55(e) illELECTRIC l
September 30, 1987 4
William G. Counsil Execuene he Pernkar U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
SUBJECT:
. COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N0S.' 50-445 AND 50-446 CABLE TRAY TEE FITTINGS SDAR:
CP-85-50 (FINAL REPORT)
Gentlemen:
On December 6,1985, we verbally notified your Mr. H. S. Phillips of a deficiency involving the use of improper welding processes in the I
manufacturing of cable tray tee fittings which could affect the seismic qualification of the cable tray system.
We have concluded that this deficiency is reportable under the provisions of 10CFR50.55(e) and the required information follows.
DESCRIPTION OF PROBLEM During an engineering review, damaged cable tray " Tee" fittings were noted in a lay-down area.
Upon reviewing the " Tee" fitting design documents to establish corrective action repair procedures, welding was observed which was not in accordance with the supplier (T. J. Cope) drawings. Although approved drawings required crossmembers to be welded at the top and bottom at the siderail connection, some members were welded on the top only.
Our evaluation of these conditions determined that inadequate information l
provided in the Vendor drawings for weld symbols, weld length and location, and members to be joined, was the root cause for the deviating welded joints.
1 The inadequate information was primarily due to the use of notes instead of 1
detailed weld symbols (AWS A2.4) to provide the necessary welding information j
to the installer and/or fabricator. These deficiencies have been confined to the cable tray connections associated with the subject vendor drawings 1
manufactured by the specific supplier.
i t
In order to evaluate the deficiencies and eliminate the possible adverse 1
)
effects of these conditions on the seismic qualification of the tray system, a corrective action program was initiated.
Using " Tees" with minimum weld (worst case) configurations, weld requirements have been established which are applied to installed components through an engineering field verification
- program, i
400 Nonh Ohve Street LB 88 Dallas. Texas 73201
g[ *5 -
- Pag #e 2:0f 3 September' 30,:1987J j
~
t lbl 2
f s
i SAFETY IMPLICATIONS This deficiency, had it remained uncorrected, may have prevented the cable tray system from performing intended design safety functions 'and resulted in an inability of associated safety-related systems to perform as required for
.' safe.. operation and shutdown.
CORRECTIVE ACTION To' establish and demonstrate minimum weld requirements and to determine that the installed components'are acceptable, we have initiated the following:
a) The minimum weld that is acceptable, based on calculations, for each
" lee" fitting configuration (size) has been identified.
~b) A' field survey conducted per TE-FVM-CS-050, "T. J. Cope Flat Ladder Tee Fitting-Selected Attributes Data Collection," to determine weld conditions to " Minimum Weld Requirements" has been completed'for both units.
A-design' change (DCA-41204) was issued for generic modification of installed fittings by adding bottom welds at " channel to stringer" joints.
.c) Representative " Tee" fittings, with existing minimum weld conditions and modified per the DCA, were subjected to static tests to confirm
. acceptability. ' Corporate Consulting & Development Co. (CCL) performed the required test with results documented per CCL Test Report No. CCL-A-742-
.87, dated May'1, 1987.
c d) " Tee" fittings installed in the field, which are found to have deficiencies with respect to to tested " Tees", are being repaired as l
dispositioned by NCRs on a case. by case basis.
" Tee" fittings that are-stored in lay-down areas will be verified for acceptance prior to installation.
The results of our actions to date indicate that there are a total of Ltwo hundred fourteen (214) " Tee" fittings in Unit 1 and one hundred sixteen (116)
" Tee" fittings in Unit 2, which are affected by this issue.
A fraction of the fittings in Unit 1 were covered by thermolag which has been removed to permit access for inspection and repair of welds as necessary.
Modification work of the installed trays has not been completed.
To date,
.approximately two hundred (200) have been modified in Unit 1.
In Unit 2, approximately ninety (90) have been modified.
i t
1
September 30, 1987 Page 3 Of 3 e-w r
The modification work described above will be completed by March 1, 1983.
Supporting documentation will be available onsite for your Inspector's review after March 31, 1988.
1 Very truly yours, l
.b.'~LY [.hMneb W. G.
uns g
By: h W.
l G. S. Keeley v'
RSB:tgj Manager Nuclear Lice /ising 1
c-Mr. R. D. Martin, Region IV Resident Inspectors (3) 1
'0 r
gFM Log -# TXX-6835 i-y File d 10110 j
=-
=
903.8 i
Ref # 10CFR50.55(e)
')
M/ELECTR/C wm am c. counsh October 5, 1987 i
a mu,,,, na pre,aen U. 5. 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 PROXIMITY. PLACEMENT - RICHMOND INSERTS TO EMBEDDED i
PLATES, WELDED ATTACHMENTS TO EMBEDDED PLATES, AND ALL CONCRETE ATTACHMENTS j
SDAR:
CP-86-04 (INTERIM REPORT)
'(
.Gentleran:
-On February 13, 1987, we notified you by our letter logged TXX-6260, of a
-deficiency involving the' placement of Richmond. inserts in the proximity of loaded embedded plates-which could compromise the integrity of adjacent shear This is an interim report of a deficiency which is reportable under cones.
the provisions of 10CFR50.55(e). Our last interim report was logged TXX-6613 dated August 3, 1987.
Our-implementation of corrective actions is continuing.
We anticipate submitting _our next report no later than December 4, 1987.
Very truly yours, (4 M 5 d W. G un il By:
J. 5. Marshall Supervisor, Generic Licensing l
CBC/mgt c - Mr. R. D. Martin, Region IV
'l Resident inspectors, CPSES (3) l 1
}
I 400 Nonh Olne Street LB 81 Dallas. Texas 75201 E_
s
MF 9-Log # TXX-6797 Fi1e # 10110 1
=
=
909.2 MIELECTRIC Ref #10CFR50.55(e) e t
1 Wilsiam G. Cournli r-I emm,n va ernaru.
Septepber 30, 1987 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555 l
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05, 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 i
System which we deemed reportable under the provisions of 10CFR50.55(e).10ur latest interim report, logged TXX-6566,'was submitted on July 15, 1987.
Our implementation of the corrective actions are continuing.
The next report i
on.this issue will be submitted no later than December,1, 1987.
j Very tr.uly yours, W. G. Counsil a
l By:
/
G. 5. Keeley Manager, Nuclear O u/i DAR/gj T
ng c - Mr. R. D. Martin, Region IV-Resident Inspectors, CPSES (3)
L l
1 l
L l
l 400 Nonh Olne Street LB 88 Dallas. Texas 73201 a-
g.
4 M
~
- - 9 Log # TXX-6811 File # 10110
=
=
903.9 Ref # 10U R50.55(e) 7UELECTR/C wmi.m c. counsu October 2, 1987 Esecutove We PersAent
)
U. S. Nuclear Regulatory Commission
-ATTN:
Document Control Desk Washington, D.C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05, 50-445 AND 50-446 MOTOR OPERATORS FOR MANUAL VALVES SDAR:
CP-86-35 (INTERIM REPORT)
Gentlemen:
On June 2,1986, we notified you by letter logged TXX-4840 of a reportable item involving the motor operators for several valves in the main steam system. Our last report was logged TXX-6622, dated August 4, 1987.
This is an interim report suamitted to status corrective actions implemented to date.
The Unit 1 Design Modification package (DM-86-106) has been issued and the im)1ementation has begun.
The valves needed to complete the installation are scleduled to be delivered in October, 1987.
This delivery date will support a December 1987 completion of the Unit 1 modification.
The engineering effort on Unit 2 is continuing.
Our next report will address the Unit 2 completion schedule and will be submitted no later than January 13, 1988.
Very truly yours, b
W. G. Counsil JDS/mgt c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3)
I l
l 400 North Olese Street LB 81 Dallas. Tew 75201
i.}
a,.
t o
j
.d. j y
b q
r
'* 'p' g
?
MM Log # TXX-6820 I'5
'J
[ {
N File # 10110
., J P J}. b u
903,10 illELECTRIC "Y # IO?0*
(*)
4i
\\
's
?h i
\\
l wmim c. cmmsa Octof t'r 5,'
1987 l
va er,m 1
,3 -
)o
, k,.
f enaa.a s
i L
)
U. S. Nuclear Regulatory Commission Document Control Desk i
'p Attu:
Washington, DC 20555 l
t
SUBJECT:
COMANCHEPEAKSTEAMELECTRICSTATIbN(CPSES) l DOCKET N05. 50-445 AND 50-446 TRACEABILITY OF lE PIGTAIL EXTENSIONS 3
SDAR: 'CP-86-38 (INTERIM REPORT)
Gentlemene
,q On May 27, 1986 we verbally notified your Mr. T. F. Westerman of deficiency 4,g j
involving the_ failure of project procedures to adequately address the, i h
4 i
-installation and inspection criteria for cable runs used arldevicWg)gtaiP.}
extensionJ. This is an interim report of a-pot 6 diel,1y reportable item under the provisions ~of 10CFR50.55(e). Our late.s.O ictdf& report, logged TXX-6455, was submitted on May 20, 1987.
f
-(,
\\
The evaluation of the as-built data for Unit 1 obtanled through the field validation program and our assenhient of the potential safety. significance of this data is continui7.g.,
1
's Our field verificat' ion program for Unit 2 is scheduled to commence as Unitl1 activities in support of fuel load are..completrd.
1 Our neyt report on this issue will bV submitted no later than December, 16, 1987.
g Very truly yours, p
&.{ (o tsM d W. G ounsil
{
By:.
J. S. Marshahl 1
Superv,i sor Generic Lice,rnsing y
,,1 RSB/grr
/-
s.
c - Mr. R. D. Mar N Region-IV h
1 Resident In3pectors, CPS?$ (3) 3, 3
u, q
Q'
+
'g
\\.
/
'.(
l-I l
400 North Olne Street LB 81 Dallas. Tetas 720I t
.y.
l u --
-- a
i J
i g
'I
=M Log #.TXX-6855 i
d File # 10110
_=
.=
903.8 Ref # 10CFR50.55(e)-
781 ELECTRIC l
WilHam G.' Counsil smo,,, r.
w,i*o, October 9, 1987 i
U. S.. Nuclear. Regulatory Commission Attn: Document Control Desk i
Washington, D. C.
20555 l
SUBJECT:
. COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 POLAR CRANE SUPPORT STRUCTURE' i
SDAR:.CP-86-62 (SUPPLEMENTAL REPORT)
Gentlemen:
j l0n October 3,1986, we notified you by our letter, logged TXX-6011, of a s.~iciency' involving a misinterpretation of the polar crane load cases, which
--we deemed, reportable.under the provisions of 10CFR50.55(e). Our. most recent report submitted to status the implementation of corrective action was logged 1
TXX-676_4 dated September 25' 198;'.
l In our report TXX-6764 we-indicated the installation of additional polar crane rail hold down clips-was complete for Unit 1 and was in progress for Unit 2.
Our original completion date of _0ctober 9,1987 for installation of the Unit 2 rail hold down~ clips'was not met due to scheduling concerns.
, 7" The Unit 2 rail hold down clips are now scheduled to be installed by January 19,-1988.
i n
Very truly yours, b
.-fi W. G. Counsil P
,4 CBC/gj L
L
--c.- Mr. R. D' Martin, Region IV L
Resident Inspectors,-CPSES (3) figg
. c.
l-Jtv Nestth Olne Street I.R MI Usilas Tet.n 7.4:01 l
cJr i
M EElIEEE Log # TXX-6822 File # 10110 908.3 7UELECTRIC Ref # 10CFR50.55(e)
Wmiam G. Counsu cium,,, va a,*'"
October 2, 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 DEVIATIONS IN G0ULD BATTERY RACK OIMENSIONS SDAR:
CP-86-76 (INTERIM REPORT) r
' Gentlemen -
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).
Our most recent interim report was logged TXX-6636, dated August 7, 1987.
Y We are continuing our evaluation.and anticipate submitting our next report by December 7, 1987.
Very truly yours, 7p7
/
W. G. Counsil RWH/gj c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 1 400 North Olive Street LB 81 Dallas, Teus 73:01
lL
'~
si H
Log
- TXX-6842' y9 File 9 10110-r
.908.3
- =
=
Ref 4 10CFR50.55(e)
TUELECTRIC October-9,.1987 William G. Counsil.
Esecunse Vrt Pronktur
.U.-S. Nuclear Regulatory Commission Attn:: Document Control Desk-Washington, 0~ C.'20555-
SUBJECT:
. COMANCHE PEAK STEAM ELECTRIC STATION-(CPSES)
DOCKET NO. 50-445 DEFECTIVE CIRCUIT CARDS IN BATTERY. CHARGERS ~
SDAR:
CP-87 Gentlemen::
On May 13,1987,. wefverbally' notified your Mr. I. Barnes of failures experienced in station battery charger circuit. cards' manufactured by Power Conversion. Products,;Inc. This.is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Our latest interim' report was. logged TXX-6646, dated August 14, 1987.
. Additional time is. required to-assess the safety significance of this condition.
Our evaluations will include:
1.
Discussions-with the manufacturer regarding generic implications.
-2.. ReviewJof design requirements, including loading calculations.
3.
Survey of the history of failures of the chargers from other plants.
Upon ' completion of these activities we will be able to determine the i
deportability of this deficiency under the provisions of 10CFR50.55(e).
l 1
1 N O.N4 Ellfl 0$l\\ C blfLYl
{0 bh Od$$d%, fC1d1 4'0h e
r, _
TXX-6842' l
October 9,-1987 Page 2 of 2 -
'Our next report-on this" issue will be submitted no later than December 18, 11987..
Very truly yours, W. G. Counsil
)
.WJH tgj c-Mr.iR. D.-Martin,-Region IV
~
Resident Inspectors, CPSES (3) 4 l
1 j
1 i
e i
4 9'
j
- A i' M
=M Log
- TXX-6839 File d 10110
=
=
907
' # 10 0 0'
1EIELECTRIC William G. Coumil e mn., v,u erm,,,,,
October 5, 1987 U. S. Nuclear Regulatory Commission Attn: Document Control Desk
)
Washington, D. C.
20555 l
i
{
SUBJECT:
. COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) i DOCKET.N05. 50-445 AND 50-446 LIMIT. SWITCH WIRING
'SDAR:
CP-87-16 (INTERIM. REPORT)
{
i Gentlemen:
On' June'1, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency
. involving conduit and cable which feed safety related valve limit switches and which'were not installed in accordance with the wiring drawings.
This is an interim report of a potentially reportable item under the provisions.of j
10CFR50.55(e). Our most recent interim report was logged TXX-6632, dated l
' August 7, 1986.
4 We are continuing our evaluation and anticipate submitting our next report by December 11, 1987.
Very truly yours, h.(, b n' W. G. Counsil Byv l
~. S. Marshall J
i Supervisor, Generic Licensing JCH/gj c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) 400 North Ohse Street LB SI Dallas, Tetas 75 OI L
l i-L _ __. __ -
rm 4
l :. -
m
==
Log # TXX-6813 i
d File # 10110
=
=
910.4.
~!
Ref # 10CFR50.55(e) 711ELECTR/C wnu.m c. counsa October 7, 1987' Execuerve %ce Presubem 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 AUXILIARY FEEDWATER PUMP MOTOR FANS SDAR:
CP-87-33.(INTERIM REPORT)
. Gentlemen:
On July 8,1987, we. verbally notified your Mr. R. F. Warnick of a deficiency involving the ' rotational direction of the Auxiliary Feedwater (AFW) Pump Motor Cooling Fans for Units 1 and 2.
This.is an interim report of a potentially recortable item under the provisions of 10CFR50.55(e).
Our latest report on-this issue was logged TXX-6629' dated August 7, 1987.
Our evaluation of the impact of those conditions on the safe operation of the plant is continuing. We will submit our next report on this issue no later
'than December.2, 1987.
Ver truly yours,.
(A/r[. be n A W. G. Counsil By:,
- J. S. Marshall Supervisor, Generic Licensing MCP/mgt c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l
.IDO Nonh Olne Street LB Bl Dallas. Texas 73201
=M M
Log # TXX-6853 E.
J i
Fi1e M10110' E
907.2 1UELECTRIC
# IOC' 00*
('}
wmiam G. Coumil s.u,, v,, er,,w,.
October 9, 1987 V. S. Nuclear Regulatory Commission Attn:. Document Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 NSSS CONTROL CABINETS OPTICAL ISOLATOR CHIPS SDAR: -CP-87-39 (INTERIM REPORT)
Gentlemen:
=0n July 15, 1987, we verbally notified your Mr. I Barnes of a deficiency involving the optical isolator chips used in NSSS control cabinets furnished to CPSES by Westinghouse which have experienced an apparently.high failure This is an interim report of a potentially_ reportable item under the rate.
provisiens of 10CFR50.55(e).
Our latect report on tSis issue was logged
'TXX-6640, dated August 13, 1987.
We are continuing our evaluation of this issue and will submit our next report by December.1, 1987.,
Very truly yours, l'71Gt W. G. Counsil CBC/grr c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 400 Nonh Ohve Street LB 8I Dallas. Texas 73:08 d_____._____________.__
I
g.
q 4.s Myh 1
M Log # TXX-6731 L
5 File # 10110
,_=
=
903.9 7UELECTRIC Ref.#10CFR50.55(e)
.{
l September 30, 1987 William G. Counsil Emutne Vwe Preuer,t V. S. Nuclear Regulatory Commission Attn: DocumerL Control Desk Washington, D. C. 20555 1
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS:
50-445 AND.50-446
't CLASS 5 PIPE SUPPORTS SDAR:
CP-87-62 (FINAL REPORT)-
Gentlemen:
l On August 24, 1987, we verbally notified your Mr. H. S. Phillips of design deficiencies identified in the use of nomographs to design seismically supported Class 5 piping systems.
A written report was'due on September 23, 1987. On September 23, 1987, we verbally requested and received an extension from your Mr.-R. F. Warnick until September 30, 1987._ This issue was identified during third party inspections and is addressed in Corrective Action Request (CAR)87-057.
A validation. program has been enacted to assure the adequacy of the Seismic Category II large bore pipe supports; however, extensive engineering effort would be required to determine if the existing-configuration, if left unchanged, would have precluded damaging interaction with seismic Category..I components.
Lacking these analyses, we have conservatively deemed this issue reportable under the provisions of 10CFR50.55(e).
DESCRIPTION-Some Class 5 piping has been seismically qualified using a nomograph method.
In some cases, this approach resulted in inadequate analysis documentation to support the design basis for Seismic Category 11_ pipe supports and generation-of support loads, and insuf ficient methods for isolating the seismically
. supported piping from the effects of interconnected non-seismic piping.
1 The root cause of this condition has been determined to be inadequate engineering requirements in specification 2323-MS-46B, " Piping Haagers (Non-Nuc lear). "
Specifically the specification did not provide adequate guidelines on proper use,of the nomograph for Seismic Category II large bore pipe supports.
400 Nonh Olhe Street LB 81 Dallas. Teus 73201 a--______-______.
TXX-6731 September 30, 1987 Page 2 of 3 The deficiencies identified are generic for the total population of Seismic i
Category 11 large bore pipe supports and associated Class 5 piping that are not rigorously analyzed as part of the SWEC requalification effort (e.g., high energy piping and extensions to ASME stress problems).
SAFETY IMPLICATI0t4S As noted in the description of this deficiency, the methods employed in the design of Seismic Category II large bore pipe supports for Class 5 piping could result in failure of these systems during a seismic event.
These conditions, if uncorrected, could adversely interact with and affect the operation or functions of safety class systems.
I CORRECTIVE ACTION The following measures will be implemented to correct the deficiency.
i a) Specification 2323-MS-46B will be revised to include appropriate criteria for the use of nomographs.
b) A hardware validation program is being implemented via Field Verification Method CPE-SWEC-FVM-PS-082, " Validation of Seismic Category II Large Bore Pipe Support Designs," to assure the adequacy of the existing Seismic Category II large bore pipe supports for the systems involved in this issue.
The program incorporates the following actions.
- 1) Performance of an engineering walkdown to evaluate the actual configurations for compliance with piping and pipe support drawings, and identify any additional design concerns resulting from the previous seismic criteria implementation.
- 2) Engineering evaluation, analysis, and resolution of design concerns using an acceptable Category 11 over I criteria utilizing standard design checklists to assure that Class 5 piping would not damage safety related components.
In addition, required modifications will be identified and issued to assure technical adequacy.
- 3) Documentation for the completed evaluation to establish the design basis for the technical adequacy of the seismically supported piping.
As preventive action, the following measures have been established:
a) Products of the hardware validation program will be documented and controlled by procedure ECE 2.13, " Retention and Control of Engineering Documents," to provide traceability of the design basis.
b) Procedure ECE 5.05, " Drawing Control," will be issued to assure that configuration (consistent with the design documentation) is maintained.
g.,
q TXX-6731 September 30, 1987
.Page 3 of 3-c) Design Basis Document DBD-CS-068, "Non-ASME Piping and Support Design,"
and procedures ECS 5.03-05, "Non-ASME Pipe Stress Analysis," and ECS 5.03-06, "Non-ASME Pipe Support Design," will be issued to assure Seismic Category 11 large bore pipe supports and the associated Class 5 piping are designed to acceptable and approved engineering criteria.
COMPLETION OATE The completion schedule for the field verification activities will be commensurate with the schedule for the Post Construction Hardware Validation Program (PCHVP).
The PCHVP will be conducted in support of the plant completion plan and scheduled to bring the plant to a fuel load status.
The target schedule to be ready for the Unit 1 fuel load is March 1, 1988.
All applicable specifications and procedures will be revised and/or issued by January 1, 1988.
Records documenting the completion of the above actions will be available for your review at the CPSES site upon completion of the PCHVP.
Very truly yours,
.b M
W. G. Counsil By:
/
G: S. Keeley M: nager, Nuclea G cenfing CBC:tgj i
j c-R. D. Martin, Region IV Resident Inspectors, CPSES (3) j i
~ _
MFE Log # TXX-6735 File # 10110
~
r
=
903.8 WELECTRIC Ref # 10CFR50.55(e) wnum c. coumn October 2, 1987 Escurtise We Presnknt U. 5. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555 i
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 i
HILTI BOLT INADEQUACIES SDAR:
CP-87-68 (INTERIM REPORT)
Gentlemen:
On August 24, 1987, we verbally notified your Mr. H. S. Phillips of several deficiencies involving concrete expansion anchors supplied by Hilti.
The specific issues include bottomed-out nuts and unacceptable torque for bolts in general, improper application for bolts installed on rotating equipment, and lack of installation documentation for bolts that are inaccessible due to grout. These deficiencies were discovered during third-party investigations and are addressed in Corrective Action Request CAR 87-052.
A written report was due on September 23, 1987. On September 23, 1987, we verbally requested and received an extension from your Mr. R. F. Warnick until October 2,1987.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Hilti bolts used to install rotating equipment have been found with bottomed-out nuts.
Hilti bolts are designed to be installed such that the threads on the bolt shank extend below the concrete surface.
As the nut is tightened, expansion wedges below the concrete surface exert pressure on the wells of the hole in the concrete.
A bottomed-out nut could occur if an unthreaded portion of the bolt shank extends above the concrete surface creating a potential for the nut to be tightened against the unthreaded portion of the bolt shank.
This condition could lead to incorrect torque being applied to the bolt.
A preliminary analysis has also concluded that Hilti bolts may be unsuitable for rotating equi this deficiency, pment installations, in order to assess the significance of all rotating equipment anchored with Hilti bolts will be analyzed considering the vibration frequency of each piece of equipment.
The results of this analysis will determine the acceptability or requirement to replace the anchor.
Design Basis Document CS-015 will be revised to provide engineering criteria necessary for this evaluation.
Specification 2323-MS-101, " Mechanical Erection Specification," will be revised to prohibit further use of Hilti bolts in this application.
4DO North Oluse Street LB 81 Dallas. Tetas 7201
__s____
- - - ^ - - - - - - - - - - - - - - - - - - - ' -
.g. L l
I TXX-6735 October 2, 1987 Page 2 of 2 l
For Hilti bolt torque and bottomed-out nuts, Specification 2323-S5-30 was revised to include torque ver'fication and inspection frequency requirements.
Torquing requirements will be field validated in accordance with EC 9.04,
" Post Construction Hardware Validation Program" using revised requirements j
noted per Specification 2323-55-30 " Structural Embedments." The significance j
of these conditions will be determined upon evaluation of the verification results.
For inaccessible Hilti bolts for which no installation documents are available, we have determined that the inspection requirements at the time of installation, according to 01-QP-11.3-13, required torque inspection of a minimum of ten bolts per shift and only unsatisfactory inspections be documented.
Therefore, no deficiency is associated with this item.
We are continuing our evaluation.
Our next report on this issue will be submitted no later than November 18, 1987.
Very truly yours, i
WCu W. G. Counsil CBC/gj c - Mr. R. D.
Martin, Region IV Resident inspectors, CPSES (3) l t_____________.__..__...____.
M M=
l Log # TXX-6740 j
File # 10110 i
E
~
903.8 1UELECTRIC
" # ** # 0*'00 mm.m o, counm.
October 2, 1987 i
Emstove he Presstent 1
U. S. Nuclear Regulatory Commission I
Attn:
Document Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 INACCURATE METHODS OF WELD MEASUREMENTS
{
SDAR:
CP-87-74 (FINAL REPORT)
Gentlemen:
On August 24, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving inadequate. measurement of weld size (throat area) in joints of structural tube steel.
The initial written report was due on September 23, 1987. On September 23, 1987, we verbally requested and received an extension from your Mr. R. F. Warnick until October 2, 1987.
These weld conditions are addressed in Corrective Action Request CAR-087.
This is the final report of a potentially reportable item under the provisions of 10CFR50,55(e).
Specifically, the effective throat for welds in the joints of structural tube steel was not properly defined in the design requirements, resulting in construction and inspection procedures which overestimated the effective weld throat'erea.
In order to evaluate these conditions, we have initiated a drawing review of tubular structural steel installations segregated by technical discipline.
i Although a number of welds with the potential for insufficient effective throats have been identified, all welds for which the analysis has been completed meet the design requirements.
Our evaluation of this issue is being implemented and documented in accordance
-with Specific Technical Issue Report STIR-SWEC-S-015.
Please note that
.similar deficiencies involving welding have been identified by SDAR CP-87-72, "lMPROPERLY DEFINED WELD LENGTHS," as potentially reportable under the provisions of 10CFR50.55(e). As the deficiencies noted in this report and SDAR CP-87-72 are being evaluated in the same Specific Technical. Issue Report STIR-SWEC-5-015, all future reports regarding these deficiencies will be submitted per SDAR CP-87-72.
Very tr y yours, f118L CBC/gj
. G. Counsil c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) 400 Nonh Obve Street LB 81 Dallas. Tetas 7201 JL--
E::I ": 3 Log
- TxX-6779 File # 10110 nr 908.3 Ref
TUELECTRC September 28, 1987 U. 5. Nuclear Reculatory Commission Attn:
Document Control' Dest Washington, D. C. 20555 i
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
{
DOCKET N05.
50 445 AtlD 50-446 i
CABLE AND RACEWAi DATA 3YSTEMS (CARD 31 CALCULATION 5 SDAP:
CP-87 70 (INTEPIM PEPOPT)
Gentlemen:
On August 28, 1987, we verbally notified your Mr. R. F. Warnick of a deficiency involving cable installations which have been completed using processes which may be inconsistent with the manner in which the Cable and Raceway Data System (CARDS) calculates percent fill and cable weight loading for cable trays.
This issue was discovered during a CARDS report analysis and was confirmed during a field investigation.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(c).
We e,re continuing our evaluation of the impact of this issue on the safety of plant operations.
We will submit our next report on this issue no later than December 4, 1987.
i Very truly yours,
.)
i
/
/
W. G. Counsil i
l WJH:tgj c-Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3)
SiO N Oitse D.liia t 1 c us 'fNI i
p v
i N;
e je e
M
=M Log # TXX-6782 h
i File # 10110
=
=
908.3 Ref #10CFR50.55(e) 7UELECTRIC Wmiam G. CounsH nuo,,4 n, e**a' September 30, 1987 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D. C. 20555 j
i
-SVBJECT: COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 FUSE SIZING SDAR:
CP-87-80 (INTERIM REPORT)
Gentlemen:
j t
OnAugust 31, 1987, we verbally. notified your Mr. H. S. Phillips of a j
deficiency involving inconsistencies which have been observed in the design and installation of fuses.
This deficiency was discovered during third-party investigations addressed ih Corrective Action Request (CAR)87-037.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Specifically, two instances of installation of improper fuse sizes have been identified.
In both cases, the current rating of the fuse installed was less than the required current rating.
The two circuits which contained the j
incorrect fuses are associated with safety related shunt trip devices which are normally de-energized. However, during a loss of Off-site Power, these I
circuits are required to "shed" emergency bus loads from service when the emergency diesel generators are starting.
The subject fuses provide short-circuit and overcurrent protection for the cables and devices in the circuits.
1 Since the fuses' current ratings are smaller than required, passing the maximum design current through the fuses could de-energize the circuit.
y j
l
- # N"O
'D "
N
-d TXX-6782 September 30, 1987 Page 2 of 2 Our evaluation of the safety significance of this condition is continuing.
Our next report on this issue will be submitted no later than January 29, 1988.
Very truly yours, h-
'-wg W. G. Counsil
\\
/
By: /-
G. S. Keeley Manager, Nucle icy ing WJH:tgj c-Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) l
.i
.b s
.L M
Log' # TXX-6781 MM File # 10110 h
3 908.3
=
=
Ref # 10CFR50.55(e)'
KIELECTRIC wini.m c. couin Sep_tember 29, 1987 Derwne %ce Present U..S. Nuclear Reg'ulatory Commission
. Attn:
Document Control Desk Washington, D.'C. 20555'-
SUBJECT:
' COMANCHE PEAK STEAM ELECTRIC STATION (CPSES).
DOCKET NOS. 50-445 AND 50-446 WEIDMULLER TERMINAL BLOCK CONNECTIONS SDAR:
CP-87-81 (INTERIM REPORT)
Gentlemen:
-On August 31,1987, we' verbally notified your Mr. H. S. Phillips of a deficiency. involving apparent inadequacies in the installation and inspection procedures'which have resulted in unacceptably loose' wire. connections at Weidmuller-terminal blocks.
This deficiency was discovered'during third-party investigations:and is. addressed in Corrective Action Request (CAR)87-039.
['
This is an' interim report of a potentially reportable item under the provisions of.10CFR50.55(e).
The' scope of this issue is limited to Weidmuller terminal blocks installed in field junction boxes and vendor supplied equipment.
' As a result of this deficiency, field validations will be performed in accordance with EC-9.04, " Post Construction Hardware Validation Program," for Weidmuller terminal blocks installed in junction boxes and vendor supplied equipment.
Installation procedure EEI-8, " Class IE and Non-Class.1E Cable Terminations," and inspection procedure QI-QP-11.03-28, " Class IE Cable Terminations," have been revised to prescribe appropriate requirements for these terminal blocks.
The completion schedule for these activities will be commensurate with the schedule for.the Post Construction Hardware Validation. Program. Our
' assessment of the potential safety significance of. this issue will be completed based ~upon the results of the' field validations.
JW %rth U!nc.htrec
!.fi 81 Dallas. Tctas ?.<NI
___________.._____________________________.________J
TXX-6781 September 29, 1987-Page 2 Our next report on this issue will be submitted no later than January 8,1988.
Very truly yours, W. G. Cou sil By: A A
j G. S. Keeley e-L j
Manager, Nuclear Licensing
/
WJH:tgj c Mr. R. D. Martin, Region IV Resident Inspectors,-CPSES (3) l
M 9
=M Log
~
File # 909.5 10110
" # '0" U' 0(*}
1UELECTRIC
- .wim m c. couasil September 30, 1987 Esecuene %ce Proulent U. S. Nuclear. Regulatory Commission Attn
- ' Document Control Desk Washington, DC 20555 i
SUBJECT:
- COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 FIRE DETECTION CONTROL PANELS SDAR: CP-87-82 (INTERIM REPORT) i Gentlemen:
On August 31, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency invo.lving discrepancies which have been observed-in the fire detection control panels.
This deficiency was discovered by Startup during prerequisite. testing and is addressed in Corrective Action Request (CAR)87-061.
This-is an interim re provisions of.10CFR50.55(e) port of a potentially reportable item under the Specifically, during prerequisite testing in accordance with XCP-EE-25. " Fire
. Detectors Zone Continuity and Calibration Check," deviations have been observed. involving the specification, design drawings, vendor drawings and'the installed par,els.
These discrepancies involve termination panels, terminal board. positions / locations and printed circuit (PC) board identification.
We are continuing our evaluation and our next report on this issue will be submitted no later than November 24, 1987.
Very truly yours, W. G. Counsil JDS/mgt By:
f/-
./
G. S. Keeley.
~
Manager, Nuclear O qsj/
ng c - Mr. R. D. Martin, Region IV V
Resident inspectors, CPSES (3) 400 North olne Street LB 81 Dallas. Texas 73201
L-M Log # TXX-6800 File # 10110 r
=
903.8 RIELECTRIC Ref # 10CFR50.55(e)
William G. Counsil em,,,, vm, m,*a' October 2, 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 ANALYSIS OF SERVICE WATER DISCHARGE STRUCTURE SDAR:
CP-87-83 (INTERIM REPORT)
Gentlemen:-
On September 2, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency identified during the design validation process involving the Service Water Discharge. Structure.
This is an interim report of a potentially reportable item under.the provisions of 10CFR50.55(e).
Specifically, Seismic Category I discharge piping penetrates the Service Water Discharge Structure.
The Service Water Discharge Structure was designed as a l
Non-Nuclear Safety (NNS) structure and failure of the structure during a seismic event could cause an adverse interaction with the discharge' piping and the structure, l
I We~are continuing our evaluation and our next report on this issue will be submitted no later than December 2,1987.
Very truly yours, I
W. G. Counsil CBC/gj t
c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3)
)
i' l
t 400 North Oltre Street LB 8I Dallas. Tetas 73201
4 M
M=
Log # TXX-6786 h
j File # 10110
=
=
908.3 Ref # 10CFR50.55(e) 7tfELECTRIC October 2, 1987 William G. Coumit Esecunve Vwe Preswne V. S. Nuclear. Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555.
)
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
I DOCKET NOS. 50-445 AND 50-446 i
DG SECONDARY METER AND RELAY CT CIRCUIT CABLE LEADS SDAR:
CP-87-84 (INTERIM REPORT)
Gentlemen:
On September 3, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving long electric cable leads in the secondary meter and relay Current Transformer (CT) circuits for the Emergency Diesel Generator (DG) which could result in inoperability of the protective relays in the This is an interim report of a potentially reportable item under' the
{
circuit.
provisions of 10CFR50.55(e).
ANSI Standard C57.13 requires a percent ratio error not exceeding 10% in CT secondary circuits.
During the preparation of calculation 16345-EE(B)-0?3-13G-0, the error for these circuits was found to be 28.57%.
i i
We are continuing our evaluation of the impact of this issue upon the safety J
of plant operations. Our next report on this issue will be submitted-not i
later than December 18, 1987.
Very truly yours, W. G. Counsil
- WJH:tgj c-Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) i i
400 North Olive Street LB 88 Dallas, Texas 75201
___._______m.
F=---
lll ll" =
Log
- TXX-6805 File
- 10110
_=
=
907
" " 10CER50.55(c)
TUELECTRIC William G. Cournil c.uun c w e ern a m October 5, 1987 U. S. fluclear Regulatory Commission Atto: Document Control Desk Washington, D. C.
20555 i
I
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATI0ft (CPSES) i DOCKET fl0S. 50-445 Afl0 50-446 DEGRADAT10fl 0F CLASS lE CIRCUITS I
SDAR:
CP-87-85 (INTERIM REPORT)*
Gentlemen:
On September 3,1987, we verbally notified vour Mr. H. S. Phillips of a deficiency involving Safety Systems inoperable Indication (SSit) panel.
These concerns were identified during investigations of third party inspection findings.
This is an interim report of a potentially reportable item under l
the provisions of 10CFR50.55(e).
Specifically, the non-Class IE SS!! panel is directly connected to Class lE
\\
i circuits without isolation.
Additional analysis is being performed to assure l
that the non-Class 1E panel will not degrade the Class 1E circuit and a fault in the panel will not affect the operability of other Class IE equipment.
flo j
documentation is available which qualifies these cables to Class IE standards.
I We are continuing our evaluation of the impact of this issue upon the safety l
of plant operations.
Our next report on this issue will be submitted no later than December 11, 1987.
Very truly yours, h
ba. n ; o b W. G. counsil l
b Dy:_
Gu J. S. Mar'shall Supervisor, Generic Licensing VIP /gj c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) a sorin aine screet La si ostis,. reu.13:01 m_______
1 e.
M MM Log d TXX-6802 i
j File # 10110 3
908.3 I
Ref # 10CFR50.55(e) l 1UELECTRIC October 5, 1987 William G. Counil h escuene \\ ne Prevaent U. S.. Nuclear Regulatory Commission Attn: -Document Control Desk Washington, D. C. 20555 i
1
SUBJECT:
COMANCHE PEAK STtAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 118 VAC CIRCUIT BREAKER SIZING SDAR:
CP-87-86 (INTERIM REPORT)
Gentlemen:
On September 3,1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving potentially undersized circuit breakers in Class IE 118 VAC distribution panels.
During the design validation program, a calculation has been' completed which indicates three branch circuit breakers in the Class lE 118 VAC instrument bus distribution panels may be undersized.
l This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
- Our evaluation of this issue is continuing to determine the effects of these conditions, specifically, involving inadvertent trips of Class IE circuits and the operability of Class lE equipment.
We expect to submit our next report by January 15, 1988.
Very truly yours, j s:/
i t {')
(kTA W. G. Counsil WJH:tgj i
c-Mr. R. D. Martin, Region IV i
Resident Inspectors, CPSES (3)
I l
i i
400 Nonh Oltse Street LB 8I Dallas. Tetas ?!201 f-L 1
M Log # Txx-6793 FE File # 10110 909.3
=
=
Ref # 10CFR50.55(e)
TilELECTRIC l
October 5, 1987 William G. Coumil E ateutnt hr Preudent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 CVCS RELIEF VALVE PIPING SDAR:
CP-87-87 (INTERIM REPORT)
Gentlemen:
On September 3, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency-involving the Chemical Volume and Control System (CVCS) relief valve piping.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Specifically, as disclosed in'an evaluation by Westinghouse, the CVCS letdown relief valve (1-8117) inlet piping is not properly designed to accommodate the design basis flow resulting from simultaneously opening all three (3) letdown isolation valves.
This scenario could result in overpressurization of the associated letdown piping under some plant conditions and is attributed to a design that failed to properly consider the effects associated with relief i
valve. accumulation, inlet piping losses and differences in elevation.
The Westinghouse study also reviewed the relief valve associated with excess letdown and Reactor Coolant Pump No. I seal leakoff (1-8121).
Further investigation by Westinghouse has concluded that this installation is acceptable, however, confirmation will be completed concurrently with the f
review of valve 1-8117.
j Our evaluation is continuing to determine the impact of these conditions on I
the safety of plant operations.
4 Our next report on this issue will be submitted no later than I
November 30, 1987.
Very truly yours, R1k W. G. Counsil MCP/gj c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 400 Nonh Olne Street LB 81 Dallas. Teus 73201
_____._._-___--)
.x M
MM Log
- TXX-6796 3,
d File # 10110
=
r 908.3 l
78/ ELECTRIC Ref # 10CFR50.55(e)
October 5, 1987 William G. Counsil becuene V ce Preswem U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D. C. 20555 l
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 6.9 KV CONTROL CIRCUIT VOLTAGE DROPS SDAR:
CP-87-88 (INTERIM REPORT)
Gentlemen:
On September 3,1987, we verbally notified your Mr. H. S..Phillips of a deficiency involving certain 6.9 kV switchgear control circuits which appear to produce an excessive voltage drop.
These conditions were observed during the design validation program.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Specifically, a previous calculation (lV-16) identified 16 control circuits for the 6.9 kV switchgear in which the voltage drop through the control cables produces a voltage at the device being controlled which is lower than the minimum voltage rating of the device.
This undervoltage condition could cause a malfunction of the Class 1E equipment by preventing control circuits from operating _ properly.
Additional calculations are being performed to substantiate this condition and to determine the extent of the deficiency.
Completion of those calculations is required to assess the imaact of this condition on the safe operations of the plant and to determine tie deportability of this issue under the provisions of 10CFR50.55(e).
Our next report on this issue will be submitted no later than January 15, 1988.
Very truly yours, V1(44 W. G. Counsil
.WJH:tgj c-Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) 400 North Olne Street LB 8l Dallas. Tem 7$201 w
_ __ = _______- _ ___._-__ _ _ _ _
I s
J
~
1 1
.M I
- l 1:::
Log
& TXX16801 3:.
.:3 File # 10110 908.3
' nlELECTRIC R
- IOCYR0005{')
j October 5, 1987 Wilham G. counsil '
Emutne Vwe Prendent V
i..
.$4 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk 4
Washington, D. C. 20555 o
i
SUBJECT:
-COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 125 VDC TO SUPS VOLTAGE DROP SDAR: CP-87-89-(INTERIM REPORT)
Gentlemen:
On. September l3,1957, we verbally notified your Mr. H. S. Phillips of a deficiency involving the voltage drop between,the Class 1E batteries and the Station Uninterruptib'le Pcuer Supply (SUPS). 3 specifically, documentation is not available which indicates the voltage drop,between the Class 1E battery terminals and the SUPS was considered in the baitery sizing calculations.
This is an interim report of c 'potentially reportable item under the provisions of~10CFR50.55(e).
s Our evaluation of this issue is continuing to determine the impact of this deficiency on the design of the 125 VDC~ system.
We expect to submit our next report by January 15, 1988.
1
\\
Very truly yours, tt4L W. G. Counsil-WJH:tgj c-Mr. R. D. Martin, Region IV i.
Resident Inspectors, CPSES'(3) 1 l
l 400 North Oltve Street LB 8l Dallas. Teus ?$C0t
.)
t(w;.
= - -
i.;
.Q
~
.W L
FE.
Log ~ # TXX-6834 Fi1e'# 10110' r.
=
905.4 Ref # 10CFR50.55(e) 7UELECTRIC
- e i
'.O wmiam c. coumn October 5,.1987
' Esecuuve Vwe Pressdent U.;S; Nuclear [ Regulatory Commission
. ATTN:- Document Control Desk 1
Washington, 0.C.
20555
SUBJECT:
-COMANCHE. PEAK STEAM ELECTRIC STATION (CPSES)'
-DOCKET N05. 50-445 AtlD 50-446 RHR REL'IEF' VALVE PIPING SDAR: -CP-87-90 (IN_TERIM. REPORT)
Gentlemen:
On September 3,s 1987, we verbally notified your Mr. H. S. Phillips of a
.possible design deficiency regarding relief valve piping connecting to the
. Residual ~ Heat: Removal (RHR) Pump suction piping.
This is an interim report-under the provisions of 10CFR50.55(e).
We are co'ntinuing our evaluation of the impact of this issue on~the safety-of plant operations. Our next report on this i.ssue will be submitted by November 20,?1987.
Very truly yours, b.[. b u s Ih W. G. Counsil By:
J. S. Marshall Supervisor, Generic Licensing 4
.CBC/mgt Ic' !Mr. R. D. Martin, Region IV Resident: Inspectors, CPSES (3)
--1 1
I J00 North othe 5treet = LB Kl Dall.ss. Texas 73:01
)
f ~3;
^,.l V
>y l
g
,7
-j y<
.i l
MM Log # TXX-6787
,'A-2 File # J0110 l
(
1
=
=
908.3-l 7t/ ELECTRIC Ref y10CFR50.55(e) j Optober 5,\\ 1987 WlHiam G. Counsu
)
t becutne Voce Pressdent Y
3 t.
g g!
\\' g \\ [\\
I M
j U. S. Nuclear Regulatory Comuission I
\\
\\
Attn:
Document Control Desk 3-l i
Washington, D. C. 20555,
i s
,'i COMANCHEN'4K5;EAM6LECTRIC.S'ATION(CPSES)l f
SUBJECT:
- .00CKET N0S'.?50-445 AMD 50-446 -
sSTARTUP TRANSFORMER OVERLOAD ".
J(.
l31 s
CP'87-91(INTERIMREPOR1%
/
SDAR:
1 y'
,),
e c
Gentlemen:
j,<
f l
s On September 3,1987, we verbally-potified.youiNr. H. S. Phillips of a i
deficiency involving the overload capaci,ty of 'tha'startu trr9s formers.
This
/
deficiency was discovered during preparation cf the Desi n Basis Document i
f i
(DBD-EE-038) for,the startup transformers.
Specifically1 ; discrepancy was i
42323-ES-2A and 28), which indidates,that the loading condIVio o
startup transformers may exceed their overlo,ad capacity.: Thiu is an interim i
r,eport of a potentially reportable litem vpder the1 provisions of 1GCFR50.55(e).
l Our evaluation of this issue ii continuing to determine the impact of this discrepancy on plant design. We expect to submit our next report by January 8, 1988.
'y,
\\l 3
l a
.r Very truly yours,
?
(
k
//)
i y,
G I
r W. G. Counsil -
f..
s
.O
- [
WJH:tgj
/ ' 't*
.G y
l m
c-Mr. R. ' D. Martin, 9egion IV t.
ResidentInqpect(es,'CPSES(3) t il s
et
(
(<,
h f 1
\\
400 %tth Olsve Street LB 81 Dallas. Ter.u 73201 ky a.
i
pw
.w
~
M MM 5: - *-
Log # TXX-6791.
j File # 10110 j
J'
~
=
r.
907 l
TUELECTRlC Ref # 10CFR50.55(e) l
. William G. Counsil f
cmw~ w, er,wey October 2, 1987 l
j V. S. Nuclear Regulatory Commission Attn: Document Control Desk
{
Washington, D. C.
20555 i
1
'l'
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 INSTRUMENT PANEL CABLE SEPARATION SDAR:
CP-87-92 (INTERIM REPORT)
Gentlemen:
On September 3, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving separation of Class 1E and non-Class 1E cables in some 118 VAC instrument bus distribution panels which may not be adequate.
l This is i
an interim report of. a potentially reportable item under the provisions of 10CFR50.55(e).
l lx
, Specifically, in four instrument distribution panels non-Class 1E cables cross f
Class 1E cables to reach assigned circuit breakers.
This arrangement does not achieve the maximum practical separation of the cables required per the FSAR E
Section 8.3.1.2.1.7C.
7G 4
l y
s1 We are continuing our evaluation of-these conditions for the possible adverse l
affects or degradation of the Class 1E cables.
Our next report on this issue will be submitted no later than December 11, 1987.
very truly yours, 7%
i W. G. Counsil l
l VIP /gj w
c - Mr.-R. D. Martin, Region IV Resident inspectors, CPSES (3) f,
{
400 North Ohve Street LB 8I Dallas. Texas 75201 e
_ ~
h I
l-F E' Log
- TXX-6788 File # 10110 l.
~r
=
908.3 ft/ ELECTRIC Ref #.10CFR50.55(e)'
October 5, 1987 William G, Counsil Esecuene he Premient r
V. S. Nuclear Regulatory Commission Attn: -Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 MCC STARTER COILS SDAR:
CP-87-93 (INTERIM REPORT)
Gentlemen:
On September 3,1987, we verbally notified your Mr. H. S. Ph.illips of a deficiency involving MCC starter coils whi:h may not pick up at minimum bus voltage.
This is an interim report of a potentially reportable item under!the provisions'.of10CFR50.55(e).
Specifically, a calculation (16345-EE(B)-007-XXX-13H,RO) has. determined that
- l the starter coils in 11 circuits may not pick up at minimum bus voltage as a result of excessive circuit length.
Failure of.any-of these starter circuits j
to function could result in failure of a Class IE device to operate properly, i
Further technical evaluation is required to assess the safety significance of this condition.
Our next report on this issue will be submitted no later than January 8, 1988.
l Very truly yours,
/
i W. G. Counsil i
l WJH:tgj i
c-Mr. R. D. Martin, Region IV f
Resident inspectors, CPSES (3) i 1
l l
1 400 Nonh Olne Street LB 81 Dallas. Tetas 73201 l
____-____n
3 M
~!
MM Log # TXX-6795' i
7,,,
d File # 10110 i
,,=
=
908.3-1 filELECTRIC
" 'AUC'RSU'55(')
l
'h wmi m c. counsa Etautoe kwe Prentent U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D. C. 20555 l
1
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 UNINTERRUPTIBLE POWER SDAR:
CP-87-94 (INTERIM REPORT)
' Gentlemen:
I
..On September 3,1987,,we verbally notified your Mr. H. S. Phillips of a deficiency involving the Station Uninterruptible Power Supply (SUPS) inverter IV'1PC3.
Specifically, this SUPS inverter is designed to maintain the proper output current when loaded between 2/3 and full designed load.
However, we j
l have determined that this inverter will be loaded to only approximately 56% of full capacity, thus not ensuring that proper output will be maintained.
This i
is an interim report of a.potentially reportable item under the provisions of 1
Our evaluation of this' issue is continuing.. We have requested the manufacturer verify, by calculation, that the inverter will function correctly j
at the reduced load.
1
' January 8,1988.
We expect to submit our next report on this issue by l
Very truly yours, 47LO W. G. Counsil WJH:tgj c-Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) l 1
l i
400 North Olne Street LB 81 Dallas, Texas 73:01
h i'
M MM Log # TXX-6794 I
d File # 10110.
=
=
908.3-7UELECTRIC Ref.# 10CFR50.55(e)
October 5, 1987 j
Wilham G, Counsil imutne b,cr Prruarrtt k
U. S. Nuclear Regulatory Commission Attn:
Document Control Desk i
Washington, D. C. 20555 t
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 UNINTERRUPTIBLE POWER SUPPLY SDAR:
CP-87-95 (INTERIM REPORT) t Gentlemen:
On September 3, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving the input voltage to the Station Uninterruptible Power Supply inverter IV 1PC3.
This is an interim report of a potentially
[
reportable item under the provisions of 10CFR50.55(e).
~!
Specifically, the minimum input voltage required by the inverter is 105 VDC, which is the associated Class 1E battery's minimum output by design.
The voltage drop (due to line loss) between the battery and the inverter has not 3
been considered and may reduce the input voltage at the inverter to less than 105 VOC.
i Our evaluation of this issue is continuing. We expect to submit our next report by January 8,1988.
Very truly yours,
'f T
W. G. Counsil WJH:tgj c-Mr. R. D. Martin, Region, IV Resident Inspectors, CPSES (3) 400 Nonh Olive Street LB 89 Dallas. Texas 7201 l
d 6
'O
==
-Log
- TXX-6804 File # 10110 E
E 907 1UELECTRIC
# IU '
U'
('
N$,I, I,'c, eNm l
October 2,1987 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 CABLE SHIELDING TERMINATION INSPECTIONS SDAR:
CP-87-96 (INTERIM REPORT)
.h Gentlemen:
On September 8,1987, we verbally notified your Mr. Ian Barnes of a. deficiency involving inspection reports which may not, in all cases, accurately reflect the status of the actual field condition of cable shielding.
This issue is i
also addressed in Corrective Action Request CAR 87-106.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
{
Specifically, in some instances the inspection records which state how cable l
shielding is terminated may.be inconsistent with the method used to register the status.
I Further technical evaluation is required to assess the possible impact of these conditions on the safety of plant operations.
Our next report on this issue will be submitted no later than December 18, 1987.
Very truly yours, 4 k
U W. G. Counsil VIP /gj c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 400 North Olave Street LB 8!
Dallas. Texas 73201
m.<
M.
I ^*
MM
' Log-'# TXX-6833
' _ _, - 3 Fi1e #-10110 L
=
=
903.9-Ref #10CFR50.55(e)
MIELECTRIC 1
wim.m c. counsu October 8, 1987 causs,a v,ce errant j
U. S.. Nuclear Regulatory Commission -
I ATTN: Document Control Desk-Washington, D.C.
20555 i
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)'
t DOCKET N05. 50-445 AND 50-446 FLEXIBLE CONOVIT INSPECTIONS SDAR:
CP-87-97 (INTERIM REPORT)
{
Gentlemen:
On September 8, 1987, we verbally notified'your Mr. Ian Barnes'of a deficiency l
involving-QC' inspection records.
Specifically, Class 1E flaxible conduits attached between electrical equipment, mechanical equipment, and junction j!
boxes have not been inspected by mechanical or electrical QC inspectors for
. minimum and maximum flex length in accordance with applicable procedures and l
. design drawings.- These. conditions are identified by Corrective Action Request
{
CAR-075.
This is an interim report of a potentially reportable item under the.
j
-provisions of 10CFR50.55(e).
4 i
We are continuing our. evaluation of this issue and anticipate submitting our
.next report no later than December 16', 1987, a
Very truly yours, l
W. d D u.n s E b 1
W. G. Counsil A a I M__-
By:
1
~
W. 5. Marshall Supervisor, Generic Licensing CBC/mgt c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3)
I l
'i 400 North Oluse Street LB 81 Dallas, Texas 75201
M E E.
Log # TXX-6836 Fi1e 6 r
=
908.3 7UELECTRIC Ref 1
- 10CFR50.55(e)
Wmlam G, Courud eran,,,,a va presasar,e October 9, 1987 I
U. S. Nuclear Regulatory Commission Attn:
Document Control Oesk Washington, D.C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) 4 DOCKET NOS. 50-445 AND 50-446 CABLE RACEWAY FILL CALCULATIONS:
CP-87-98 (INTERIM REPORT) CABLE OUTSIDE DIAMET SDAR:
l Gentlemen:
On September 9,1987, we verbally notified your Mr. H. S. Phillips deficiency involving review-of the cable and raceway data syste indicates that the wrong cable ~ diameter may have been used in c which Specifically, CARDS 2323-El-1700 and 2323-E2-1700 use the no ons.
maximum) cable diameter for calculating raceway fill.
rsus identified during investigations initiated under the Corrective A ti This issue was 4
(CAP).
This is an interim re provisions of 10CFR50.55(e). port of a potentially reportable item under theon Program c
Currently, we are developing our evaluation to assess the impact of I
application of nominal as opposed to the maximum allowed cable ou e
diameter.
Our next report on this issue will be submitted no later than November 20, 1987.
i Very truly yours, I
g W. G. Counsil WJH/mgt
-c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 400 North Oh>e Street LB 81 Dallas. Tem 73.'01.;
L___-__--_-.-
=
4
_q
' Log' # TXX-6843 ym File # 10110-908.3
.=
=
Ref # 10CFR50.55(e) i 1UELECTRIC October 9,-1987 William G. Counsil Emutive he Presnient
~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 t
CABLE OUTSIDE DIAMETER REQUIREMENT
.SDAR:
CP-87-99 Gentlemen:
On September'9,1987, we verbally notified your Mr. H. S. _ Phillips of a potential deficiency' involving cable which exceeds the maximum allowable outside diameter prescribed in the cable specification.
This condition was discovered as a result of activities initiated under the Corrective Action Program (CAP). This is an interim report of a'potentially reportable item under the provisions of 10CFR50.55(e).
Specifically, our evaluation of a nonconformance report has revealed that approximately 100 reels.of cable (types W-065, W-165, W-265 and W-765) have exceeded,the maximum specified outside diameter.
Further evaluation'is j
required to assess the possible safety significance of these conditions.
j Our next report on this issue will be submitted no later than December 18, 1987.
)
Very truly yours, W. G. Counsil Wjh:tgj c-Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3)
'r i
400 North Olese Street LB 81 Dallas. Teus 7201 LL_ -__ _._- _ _
l
h 1
MEE Log # TXX-6850 Fi1e # 10110
=
=
906.2 filELECTRIC Ref # 10CFR50.55(e)
I October 8, 1987
\\
William G. Counsil Esecutsve Vwe Presutent i
U. S. Nuclear Regulatory Commission l
Attn: Document Control Desk Washington, D. C.
20555
{
i l
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) d i
00CKET N05. 50-445 AND 50-446 CONTAINMENT PENETRATION OVERPRESSURE PROTECTION SDAR: CP-87-100 (INTERIM REPORT)
Gentlemen:
i On September 10, 1987, we verbally notified your Mr. I. Barnes of a deficiency
}
involving three containment isolation penetrations that may lack relief j
protection.
Specifically, the design validation process has revealed that one Safety Injection System containment penetration and two Primary Sampling
~
1 System containment penetrations, which are water solid and isolable, may lack overpressure protection.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
I We are continuing our evaluation and anticipated submitting our next report by
)
December 11, 1987.
j Very truly yours, id. 6,. Lounsl $
W. G. Counsil By i
A
/J. S. Marshall Supervisor, Generic, Licensing CBC/grr c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 400 North Olive Street LB Bl Dallas. Texas 75201
,1 4
k.
1.
M
. Log # TXX-6840 a
1 MM File a 10110.
L d
908.3
,_,=
=-
Ref.~#.10CFR50.55(e)'
j 1UELECTRIC
-October 9, 1987; William 'G. Chunsil '
IJ.SNffII$EearRegulatoryCommission l
2 Attn:. Document Control Desk
-Washington, D. C. 20555-1
SUBJECT:
COMANCHE PEAK' STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND.50-446 CLASS 1E CABLE ARRANGEMENT SDAR: CP-87-101-(INTERIM REPORT) s Gentlemen:
i
~
On September 10, 1987, we verbally notified-your Mr. H. S. Phillips of a deficiency involving-Class 1E electrical circuits with multiple conductor per
. phase feeders which may have the potential to-overheat.
This is an' interim g
treport of a potentially ieportable item under the provisions of.10CFR50.55(e).
l-Specifically, while preparing Revision 3 of Electrical -Specification 2323-ES-s 100, " Electrical Erection Specification," a possible -deficiency was noted in
.l,
- the arrangement of multiple conductor per phase feeders in cable trays.
The current in multiple condu'ctor. per phase feeders is affected by the cable arrangement in the cable trays.
If the conductor current is not divided equally, cable overload and subsequent overheating may result.
L We are continuing our evaluation of the impact of this issue upon the safety of plant operations.
Our next report on this issue will'be submitted no later than' December 11, 1987.
1 Very truly yours, I
T4 W. G. Counsil WJH:tgj c-Mr. R. D. Martin, Region IV i
Resident Inspectors, CPSES (3) 1
.in, s..,en, >rn e w. co t1 si s >.11.n. reun :L's>
2-__-___=_____--_~.-
' _ _, 5 File # 10110
=
=
908.3 Ref # 10CFR50.55(e)-
MtELECTRIC wn m c. coumu October 8, 1987 Esecuene Voce Presnient 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 CABLE TRAY SEPARATION CRITERIA SDAR:
CP-87-102 (INTERIM REPORT)
-Gentlemen:
On September 11, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving a potential conflict between cable tray installations and the design requirements for cable tray separation. Specifically, the minimum separation design criteria for vertical trays and conduit for open ladder trays may have been violated although the inspection findings were not rejected by QC personnel.
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 December 11, 1987.
Very truly yours, Q. ( Co v es W. G. Counsil
?
k By:
J. S. Marshall Supervisor, Generic Licensing DAR/grr l
1 c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) l 400 North Olive Street LB 81 Dallas. Texas 7201 L__-_----------------------------
i M
y""" E Log # TXX-6851 o-i.
File # 10110
.=
=
903.9 7tlELECTRIC Ref # 10CFR50.55(e)
October 8, 1987 WiHiam G. CounsU Enocunve Voce Pressden, U. S. Nuclear Regulatory Commission l
' Attn: Document Control Desk l
Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 1
CRACKED GEARS IN VALVE OPERATORS SDAR: CP-87-103 (INTERIM REPORT)
Gentlemen:
1 On September 11, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving cracked gears in valve operators.
Specifically, cast bronze sector gears, used in Limitorque HBC-3 valve drives, were discovered to have visible defects and cracks in the web area where they bolt to the drive sleeves. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
We are continuing our evaluation and anticipated submitting our next report by December 11, 1987.
Very truly yours, Lt). }
.... ~.t ]
W. G. Counsil r/
8y a
J. S. Marshall Supervisor, Generic, Licensing j
C8C/grr I
c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) l i
I 400 North Olive Street LB 81 Dallas. Tens 73201 w.__-.__-_.
g*
W g-bI f
M Log
- TXX-6852 l
--h j
File # 10110 l
=
=
907.2 1
- 1UELECTR/C Ref # 10CFR50.55(e) wuu,n c. counsu October 14, 1987 Executsve Vice Ptssutent U. S. Nucl' ear, Regulatory Commission Attn: Document Control Desk
' Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SAFETY SYSTEM SETPOINT CALCULATION ERROR l
SDAR: CP-87-104 (INTERIM REPORT)
I Gentlemen-On September 14, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving possible errors in protection actuation setpoint calculations for NSSS systems.
This is an interim re reportable item under the provisions of 10CFR50.55(e) port of a potentially Specifically, during the preparation of the protection actuation setpoint calculations for the NSSS Systems, no allowance for calibration inaccuracies was included in the calculations.
These conditions were apparently due to an
. assumption made by the equipment supplier (Westinghouse) that the accuracy of the measuring and test equipment (M & TE) would be greater than the. accuracy of the equipment being calibrated by a factor of ten.
This assumption was based on SAMA Standard PMC-20-1-1973 entitled " Process Management and Control Terminology." Section 4.2 of the SAMA standard states that if the accuracy of the M & TE is ten times greater than the equipment being calibrated, inaccuracies of H & TE do not need to be considered.
j Unless the " ten times" accuracy factor for M & TE is followed or an allowance for M & TE inaccuracies is included in the calculations, a reduction in the Limiting Safety System setpoint margin could result.
This condition would affect the following setpoints:
1.
Containment Pressure Hi-1, Hi-2, Hi-3 2.
Pressurizer Pressure Low SI 3.
RWST Low Level 4.
N-16 Overtemperature The M & TE utilized during the actual calibration had an accuracy equal to or greater than the equipment being calibrated.
l 400 Nonh Olive Street LB 81 Dallas. Texas 73201 w
[s, g p
~,.
4,
'A TXX-6852 October 14, 1987 Page 2 of-2
- .c,
In order to evaluate the safety significance of this condition, the~effect of'
-the. actual M & TE inaccuracies on the calculated safety margin of these I
.setpoints will.be determined.
~
i Our next report on this issue will be submitted no later than January 18, 1988.
l Very truly yours,
$4 W. G. Counsil VIP /grr
'c - Mr. R. D. Martin, Region IV
[
Resident Inspectors, CPSES (3) 1 I
f 1
i
- t.
s-4
,;j.
b 4
'i 1
6
's
.c f
}e-
['
'i :c 5b W-
w iV j
M
=M Log # TXX-6841 h
j File # 10110
=
=
908.3 MtELECTRIC Ref. # 10CFR50.55(e) i October 14, 1987 Wiluem G. Counsil Esecuene Vice Presutent 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 CONDUCTOR LUG TERMINATIONS SDAR: CP-87-105 (INTERIM REPORT)
Gentlemen:
On September 14, 1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving cable termination. inspections which indicate that multiple cable termination deviations may exist in a safety related component.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Specifically, conductor lug terminations for hydrogen purge containment isolation valve CP2-VADPEC-01 may be inadequate due to improper crimping of the lug barrels.
We are continuing our evaluation of the imaact of this issue u)on the safety of plant operations.
Our next report on t11s issue will be su)mitted no later than January 19, 1988.
I Very truly yours, W. G. Counsil
]
WJH:tgj c-Mr. R. D. Martin, Region IV I
Resident Inspectors, CPSES (3) 1 l-O e NMf LB II ANS. Teus U.Mt G
w mm e
m
.1 SDAR INDEX-10-01 yn
-No; SUBJECT DETEHM.
STATUS 1975 REACTOR BUILDING EXCAVATION R
. REACTOR CAVITY MAT R
TXX-1198 My Ohhh 1976 UNIT NO. 1 CONTAINMENT BASE MAT R
TXX-1754 -
1976 SSI DAM-FILTER "A" MATERIAL R
TXX-2069 M
. A 1
77-A POLAR CRANE SUPPORT GIRDER dR NONE 77-B FUEL BLDG. DESIGN DISCREPANCY R
TXX-2609 77-C FAILURE OF WESTINGHOUSE AR/ARLA LATCHING RELAYS R
TXX-2465'i
' D POTENTIAL PROBLEM WITH OPERATION OF SAFEGUARDS ACTUATION BLOCK / RESET CIRCUITRY R*
TXX-6381 E SPECIFICATION NONCONFORMANCE WITH THE PSAR NR NONE 77-F-STATOR WINDING DEFECT DELEVAL DG NR NONE 77-1
' FALSIFICATION OF CONCRETE AIR ENTRAINMENT RECORDS NR TXX-2266 77-2 CONCRETE CURING BLANKET FIRE NR TXX-2265 77-3 INSTALLATION OF PIPE WHIP RESTRAINT ANCHOR BOLTS, NUTS.& PLATES NR TXX-2474 77-4 POLAR CRANE SUPPORT BRACKETS R
TXX-2395 77-5 OMISSION OF-BORON RECYCLE EVAPORATOR PACKAGE FOUNDATION ANCHOR BOLTS NR NONE
.77-6 OMISSION OF REINFORCING STEEL FROM CONCRETE POUR-IN RX. BLDG. NO. 1 NR NONE 77-7 POLAR BRANE GIRDER UPLIFT RESTRAINTS NR TXX-2464 77-8 INSTALLATION OF PIPE WHIP REATRAIN-ANCHOR BOLTS, NUTS, & PLATES NR TXX-2474 77-9 3 INCH DIAMETER HOLES DRILLED IN R.B. NO. 1 NR NONE 77 OMISSION OF REINFORCING STEEL FROM R.B.1 & A.B.1 NR NONE 77-11 OMISSION OF REINFORCING STEEL FORM R.B.1 & SG.B.1 NR NONE 77-12 ORIENTATION OF CADWELD SLEEVES NR TXX-2678 1977 CADWELD TEST SPECIMEN REBAR FAILURE NR TXX-2269 ir r k.
78-A DAMAGE TO DELAVAL DIESEL GENERATOR CONTROL PANEL NR NONE i
78-B MISCLASSIFICATION OF SAFETY RELATED EQUIPMENT NR TXX-2867 78-C SERVICE WATER INTAKE PUMP SEISMIC RESTRAINT NR TXX-2905-78-1 SERVICE WATER PUMP SUPPORTS NR NONE J
78-2 CATALYTIC HYDROGEN RECOMBINERS NR NONE,1,Q @ '
78-3 CANCELLED
^
,e i
- 4 ANCHOR BOLTS-MISCLASSIFICATION NR SEE 78-B" M !
78-5 ANCHOR PLATE WASHERS MISCLASSIFICATION NR SEE78-BIf?*
3; 78-6 DEFECTIVE CADWELDING
'NR TXX-2896 7 W 78-7 WELDING ACTIVITIES FOR UNIT 1 RCS LOOP PIPING NR TXX-2926 j
,,n j
j 1975-1978:
8 REPORTABLE SDARS
,p
)
t t s
r h.g.
7 SDAR INDEX-10-01-87.
n, NO.
SUBJECT DETERM. STATUS'
~79-01 EXPANSION JOINT-DECONTAMINATION ROOM NR TXX-2952 79-02
-INSTALLATION OF PIPE ELBOWS IN SG LOOP PIPING NR TXX-2957 79-03 REACTOR VESSEL N0ZZLE BASE METAL DEFECTS-NR TXX-3007 79-04 PIPE SUPPORTS NR TXX-3036 79-05 PIPE WALL THICKNESS R
TXX-3138 %
79A.
PRESSURE TRANSMITTERS NR TXX-3003 79B POSSIBLE COOLING PROBLEM WITH DIESEL GENERATORS NR TXX-3054.
79-06
' ELECTRICAL CABLE TRAY HANGERS-PARTIAL WELDS R
TXX-3067 79-07~
REACTOR CONTAINMENT NR 10/29/79 i
79-08 INSTALLATION OF DRILLED-IN EXPANSION ANCHORS R*
TXX-3125 79-09 WELDED CONDUIT SUPPORTS R
'79-10 CLASS V. PIPING SUPPORTS R
TXX-3195 l
79-11
' REACTOR COOLANT NR 12/29/79' 79-12 FILTER INTERNALS NR F /12/80 79-13 CONCRETE HONEYCOMBING-UNIT 2 SG COMPARTMENT R
TXX-3124 1979: 15 TOTAL SDARS--6 REPORTABLE 80-01 SERVICE WATER PUMPS NR 01/17/80 80-02 SERVICE WATER CONTROL VALVES R
TXX-3114 80-03 CONTROL BOARD WELDING CONNECTIONS R
TXX-3131-80-04 REACTOR VESSEL N0ZZLE SAFE-ENDS NR TXX-3154
.80-05 USE '0F ARCHITECTURAL CONCRETE IN FLOOR SLABS R
TXX-3247 80-06, UPPER INTERNALS ROTO-LOCK INSERT NR TXX-3217 80-07 PLASCITE 7122 COATING
' NR TXX-3229 80-08 THREAD ENGAGEMENT OF SWAY STRUTS NR TXX-3219 80-09 DIESEL GENERATOR PIPE SUPPORTS R
TXX-6711 80-10 HILTI-KWIK CONCRETE ANCHOR BOLTS R
CANCELLED 80-12 PULL-0UT PERFORMANCE OF HILTI-KWIK BOLT ANCHORS NR TXX-3398 1980: 11 TOTAL SDARS--5 REPORTABLE 81-01 PIPE SUPPORT BASEPLATE GROUTING MATERIAL NR TXX-3279 81-02' ELECTRICAL CABLE LUBRICANT NR TXX-3357 i
81-A WESTINGHOUSE GATE VALVES R
TXX-3409 81-B BAHN30N HVAC ANCHOR BOLTS R
TXX-3329 81-03 HVAC COOLING SYSTEM R
TXX-3349 81-04 FAILURE OF 6.9KV CIRCUIT BREAKER NR TXX-3313.
l 81-C VOLINE CONTROL TANK LEVEL CONTROL SYSTEM NR TXX-3311' 81-05 PIPE SPOOL FLANGE MATERIAL NR TXX-33561, 81-06 SEISMIC INSTRUMENT. TUBING SUPPORT R
TXX-33581 M 81-07 ORIFICE PLATES SUPPLIED OUTSIDE OF TOLERANCE -
R TXX-3527i W
. 08 UNDERSPECIFIED A N VALVES NR TXX-3487'.
i, 1981: 11 TOTAL SDARS-5 REPORTABLE l
i
x.
m SDAR INDEX-10-01-87 a-D N0_.
SUBJECT DETERM. STATUS 82-A'
-INSTALLED BORG WARNER VALVES
'R TXX-3495 82-01 MATERIAL PROCURED BY AFC0 STEEL NR TXX-3480 82-02 DESIGN OF HORIZONTAL FIRE DAMPERS R*
TXX-3523 82-03 W RCS WIDE RANGE PRESSURE MEASUREMENTS NR TXX-3571' 82 PACIFIC PtNP MULTI-VANE DIFFUSER CRACKING NR TXX-3634; 1
82-05
-UNIT 2 SG COMPARTMENT WALL-CONCRETE VOID NR TXX-3549 82-06 AUXILIARY SKID UNIT 2 R
TXX-6660 82-07
. DEFECTIVE GOVERNOR DRIVE COUPLINGS-R*
12/29/87-82-08 DEFECTIVE LIMITORQUE PINION KEYS NR TXX-3580 82-09
'SSPS UNDETECTABLE FAILURE-R*
TXX-3589 82-10 REINSPECTION OF CONDUIT SUPPORTS NR TXX-3583 82-11 OVERTORQUING OF-SAFETY RELIEF VALVES NR TXX-3594 82-12. ~ PIPE-WHIP RESTRAINT WELD INDICATIONS NR TXX-3604 82 VOID IN AUX. BLDG. CONCRETE FLOOR SLABS NR TXX-3589 82-14 REACTOR COOLANT PRESSURIZER SURGE LINE NR
'TXX-3592 82-15 DEFECTIVE PISTON SKIRT CASTINGS R
TXX-6657 1982: 16 TOTAL SDARS--6 REPORTABLE 83-01 BORG-WARNER CHECK VALVE MALFUNCTION R
TXX-3623 83-02 EMD VALVE POSITION INDICATION R
TXX-3633-83-03 NON-METALLIC INSULATION NR TXX-3624 83-04 RADIATION MONITORING SYSTEM (RM-23)
NR TXX-3635 83-05
. VOIDED 83-06 VENDOR (BAHNSON) INSTALLED HVAC SYSTEM NR TXX-4016 83-07 NEW FUEL STORAGE RACKS -
R TXX-3677 83-08 CONTROL VALVE BRACKETS WELDING R
01/14/88 83-09 WESTINGHOUSE DS416 REACTOR TRIP SWITCHGEAR R*
W REPORTED 83-10 LETDOWN HEAT EXCHANGER ANCHORS R
TXX-4001 83-11 CCW CLASS V PIPING R*
TXX-3690 83-12 CLASS 1 MATERIAL DEFICIENCIES NR TXX-3691 83-13 STRUT JAbMING DEVICES NR TXX-3692 83-14 WESTINGHOUSE NLP PRINTED CIRCUIT CARDS NR TXX-3693 83-15 CABLE TRAY CLAMPS R*
TXX-4005 83-16 WELDED ATTACHMENTS TO PIPING AFTER HYDROSTATIC TESTING NR TXX-4012 83-17 INADEQUATE OVERPRESSURE PROTECTION FOR SPENT FUEL POOL COOLING HEAT EXCHANGERS CCW RELIEF VALVES R
TXX-4043 83-18 CONTAllefENT BLDG. COOLING R
TXX-4043 83-19 SERVICE WATER SYSTEM VALVES NR TXX-4064 83-20 DEFECTIVE BREAKER SUPPORT BRACKETS R
TXX-4078 83-21 TRANSMITTER CALIBRATIONS R
TXX-4091 X 83-22 CHLORINE DETECTION AND CONTROL ROOM HVAC R
TXX-4098 1983: 21 TOTAL SDARS--13 REPORTABLE L
i L
- k.
SDAR INDEX-10/01/87
- r-
)
_N_0.
SUBJECT.
DETERM. STATUS 84-01 CABLE TRAY SUPPORT COLUMN (CABLE SPREAD ROOM)
NR TXX-4154 84-02 DIESEL GENERATORS DEFECTIVE PUSH RODS R*
'84-03 INSTRUMENT TUBING NR TXX-4110 84-04 FERRORESONANT TRANSFORMERS R
TXX-4109 '
84 PROTECTIVE C0ATINGS ADHESION TESTER NR TXX-4248 84-06 PIPE SUPPORT DESIGN ERROR NR TXX-4107' 84-07 DEFICIENT LUG CRIMPING R
TXX-4135 84-08 THERMAL EXPANSION OF CURTAIN FIRE DAMPERS R*
01/31/88 84-09 THRUST BEARING LUBRICATION NR TXX-4227-84-A INSPECTOR EYE EXAMINATION RECORDS NR TXX-4204 84-10 RODENT DAMAGE TO CLASS lE CABLES NR TXX-4175 84-11 UNAUTHORIZED THERMOLAG INSULATION NR TXX-4178 84-12 IMPACT OF HELB TEMPERATURES ON QUALIFIED EQUIPMENT OUTSIDE CONTAINMENT P*
11/30/87 84-13 FSAR AND TECHNICAL SPECIFICATION CONSISTENCY NR TXX-4213 84-14 ROCKBESTOS CABLE DEFICIENCY NR TXX-4214 84-15 INDETERMIN. FLORIDE CONTENT-MANVILLE INSULATION 'NR TXX-4221 l
84-16 QUALIFICATION OF MAIN STEAM RELIEF VALVES NR TXX-4330 84-17 FLOODING CONCERNS R*
TXX-4263' 84-18 UNQUALIFIED LIMITORQUE ELECTRIC MOTORS R
TXX-4308 84-19 DG MATERIAL DEFECT (VALVE SPRINGS)
NR TXX-4270
)
84-20 DG MATERIAL DEFECT (DELIVERY VALVE HOLDER)
NR TXX-4309 84-21 UT REQUIREMENTS: CLASS 1 PIPING NR TXX-4292 i
84-22 CCW SYSTEM DESIGN CONCERN NR TXX-4351 84-23 CONAX PENETRATION CONNECTORS NR TXX-4375
-j 84 PREOPERATIONAL TESTING ACTIVITIES NR TXX-4372 1
84-25 AIR-OPERATED DIAPHRAGM VALVES NR TXX-4318 84-26 NSSS AUXILIARY RELAY RACKS NR TXX-4317 84-27 VENTILATION EXHAUST DAMPERS R*
TXX-4409 j
84-28 h0SEMOUNT TRANSMITTERS LEAKAGE R
TXX-6661 84-29 SAFE SHUTDOWN CAPABILITY FOR FIRE-C.R. HVAC R*
{
84-30 SAFETY CLASS DESIGNATION OF INSTRUMENTS LINES NR TXX-4362 84-31 CONTROL ROOM SEPARATION WALL R*
TXX-4349 84-32 CLASS 1E BARTON PRESSURE SWITCHES-PART 21 NR TXX-4363 i
84-33 RELAYS OUTSIDE SPECIFICATION NR TXX-4376 84-34 UNIT 2 STRUCTURAL EMBED WELDING NR TXX-4433 1984: 35 TOTAL SDARS-10 REPORTABLE. 1 POTENTIAL
)
4
't 3
1 1
J t
SDAR INDEX-10/01/87
,N_0.
SUBJECT DETERM. STATUS 85-01 MAIN CONTROL BOARD CABLE SEPARATION VIOLATION NR TXX-4411 85-02 CABLE SPREAD ROOM FIRE PROTECTION-3 HR BARRIER NR TXX-4410 85-03 STEAM GENERATOR UPPER LATERAL SUPPORT BEAMS R*
TXX-4415 85-04 CONTAINMENT SPRAY HEADER ISOLATION VALVES R*
TXX-4437 85-05 DG ENGINE CONTROL PANEL AIR FILTER BOWLS R
TXX-4428 85-06 ERF COMPUTER TERMINATION POINTS NR TXX-4447 85-07 ELECTRICAL CABLE BUTT SPLICES NR TXX-4490 85-08 SUMP ISOLATION VALVE MOTORS NR TXX-4481 85-09 VALVE WEIGHT DISCREPANCIES NR TXX-4473 85-10 RELIANCE CONTROL BOARD EQ DOCUMENTATION NR TXX-4523 i
85-11 INSTRUMENTATION TUBE FITTING LOCATIONS R
TXX-6673 85-12 A W PRESSURE CONTROL-FEED WATER LOW FLOW TO S/G R*
TXX-4456 85-13 UNDETECTED FAILURE IN SAFETY FEATURES ACT.SYS.
R*
TXX-4457 85-14 UNAUTHORIZED SUPPORT REPAIRS R*
TXX-4465 85-15 EQUIPMENT HATCH UNIT 1 UNEVAL. BEARING FORCES NR TXX-4460 85-16 PHOENIX STEEL-PART 21 WALL THICKNESS QUESTION NR TXX-4505 85-17 PART 21-CORE EXIT TEMPERATURE MONITORING ERRORS NR TXX-4485 85-18 SPECIFIC CRITERIA FOR CONCRETE ANCHORS IN THE PROXIMITY OF EMBEDDED ANGLED NOT DEFINED R*
TXX-4492 85-19 CONDUIT SUPPORT SPANS R*
10/09/87 85-20 WHIP INTERACTION POSSIBLE-FW BREAK /CS HEADERS R*
TXX-4516 85-21 DG POTENTIAL CONTROL PANEL OVERHEATING NR TXX-4493 85-22 CONTAINMENT ISOLATION VALVES NR TXX-4575 85-23 CONTAINMENT SPRAY PUMP NR TXX-4563 85-24 TERMINATION OF FIRE DETECTION DETECTORS NR TXX-4533 85-25 SEQUENCING FIRE PROT. COMPONENTS FOR HVAC/CCW NR TXX-4578 85-26 UPPER LATERAL RESTRAINT EMBEDMENT DESIGN NR TXX-6132 85-27 SEISMIC GAP LESS THAN DESIGN-CPRT ITEM II.C R*
TXX-4650 85-28 PIPE SUPPORTS WELD LENGTH ANALYSES NR TXX-4550 85-29 DESIGN OF ARCHITECTURAL FEATURES R*
TXX-4552 85-30 SWITHGEAR CABINET VENDOR TERMINATION NR TXX-4598 85-31 ELECTRICAL RACEWAY SUPPORT SYSTEM DESIGN R*
10/16/87 85-32 FEEDWATER REG VALVE SINGLE POWER SUPPLY NR TXX-4600 85-33 NON-SEISMIC TO SEISMIC INTERACTION NR TXX-4577 85-34 CONDUIT SUPPORT SYSTEM R*
02/01/88 85-35 CABLE TRAY HANGER DESIGN R*
11/19/87 85-36 TRAIN 'C' CONDUIT SUPPORTS P*
02/10/88 85-37 QUALIFICATION / CERTIFICATION OF INSPECTORS R*
TXX-4569 j
85-38 CONTROL BOARD SEPARATION MATERIAL NR TXX-4715 85-39 EQUIPMENT CONDUIT INTERFACE P*
11/13/87 85-40 FLUX MAPPING SEAL TABLE RESTRAINTS R
TXX-6713 85-41 COMPUTER PROGRAM ERRORS NR
~TXX-4716 85-42 CONDUIT LOADING BY THERMOLAG R*
11/11/87 85-43 QUALIFICATION OF PLANT TEMPERATURES R*
TXX-4659 85-44 QUALIFICATION OF 480V SWITCHGEAR NR TXX-4918 85-45 REBAR DAMAGE NR TXX-4761 85-46 DAMAGE STUDY EVAL. OF W ANALYZED PIPING R*
TXX-4658 85-47 USE OF AMPTECTOR IIA RELAYS NR TXX-4682 85-48 DG INTAKE SILENCER INTERNALS NR TXX-4683 85-49 MAIN STEAM LINE FLUID TRANSIENT R*
TXX-4656 85-50 CABLE TRAY TEE FITTINGS R
TXX-6771 85-51 APPLICATION OF LOW SULPHUR CONTENT A588 STEEL NR TXX-4722 85-52 CABLE TRAY HANGER REVERIFICATION PROGRAM R*
TXX-4657 85-53 SEISMIC CATEGORY I PLATFORMS P*
12/20/87 3
85-54 SEISMIC QUALIFICATION OF HVAC SUPPORTS R
TXX-6460 1985: 54 TOTAL SDARS--24 REPORTABLE. 3 POTENTI AL L
1-o-
/.;'
SDAR INDEX-10/01/87
_N_0.
SUliJECT 3
DETERM. STATUS I
s.
86-01 WEIDMULLER TERMINAL BLOCKS NR TXX-4712 k
86-02 TURBINE-DRIVEN A N PUMP PERFORMANCE NR TXX-4723 86-03 CLASS lE INSTRUMENT TECHNIQUES R*
)
86-04 RICHMOND INSERTS TO EMBEDDED PLATE R*
10/05/87 j
86-05 SAFETY CLASS PIPE SUPPORTS MOUNTED TO NSS EMBEDDED PLATE NR TXX-4776 i
86-06 PUMP AND DRIVER DOWELING NR TXX-4704 i
86-07 SERVICE WATER SYSTEM LEAKAGE R*
12/01/87 86-08 SUPER HILTI-KWIK BOLT INSTALLATIONS P*
10/22/87 86-09 DG INLET / EXHAUST VALVE SPRINGS NR TXX-4724 86-10 ELECTRICAL PENETRATION ASSEMBLIES R*
01/29/88 86-11 PUMP IMPELLER LINEAR INDICATIONS R*
11/18/87.
86-12 CO W ODITY INSTALLATIONS AT SEC. WALL DESIGN GAP P*
12/18/87 86-13 JET IMPINGEMENT LOAD REVIEW P*
10/16/87 86-14 6.9KV SWITCHGEAR BREAKER WELD FAILURE R
TXX-6341 86-15 DIESEL GENERATOR CONTROLS NR TXX-6002 86-16 FIRE EFFECTS ON INSTRUMENT TUBING R
TXX-6230 86-17 MINIMUM CONCRETE COVERAGE NR TXX-6180 86-18 SAFETY CHILLED WATER CHILLER UNITS R*
12/18/87 86-19 INSTRUMENTATION INSTALLATIONS R*
12/02/87 86-20 WFI NUCLEAR PRODUCTS NR TXX-4870 86-21 QUALIFICATION OF RAYCHEM KIT NPKS-02-01 NR TXX-5046 86-22 SG'S AREA FAN COOLERS P*
10/21/87 86-23 P-10 PERMISSIVE R*
TXX-4835 86-24 SPACE AND MOTOR HEATERS NR TXX-6083 86-25 BREAKER / FUSE COORDINATION NR TXX-4964 86-26 CONTAINMENT SPRAY SYSTEM PIPING NR TXX-4799 86-27 CCW RADIATION DETECTORS NR TXX-4800 86-28 SERVICE WATER SYSTEM DISCHARGE NR TXX-4801 86-29 ACCEPTANCE TEST OF AIR OPERATED VALVES NR TXX-4802 86-30 UPS INVERTERS NR TXX-4965 86-31 DG LUBE OIL SUMP TANK FOOT VALVES R
TXX-6564 86-32 THRU-WALL EBMEDDED CONDUIT SLEEVES P*
10/30/87 86-33 STIFFNESS VALUES FOR CLASS 1 STRESS ANALYSIS R
TXX-6025 86-34 DEFECTIVE FIRE STOP INSTALLATIONS NR TXX-4966 86-35 MOTOR OPERATORS FOR MANUAL VALVES R*
10/02/87 86-36 LARGE BORE PIPING AND SUPPORTS R*
11/20/87 86-37 CLASS lE BATTERY CHARGER COMPONENTS P*
11/06/87 86-38 TRACEABILITY OF lE PlGTAIL EXTENSIONS P*
10/05/87 86-39 CABLE TRAY "C-TYPE" CLAMP SHIM DIMENSIONS NR TXX-6403 86-40 APPLICATION OF NON-QUALIFIED AGASTAT RELAYS R*
11/20/87 86-41 SMALL LOCA MODE 4 OPERATION P*
02/29/88 86-42 I&C CABINET POWER SUPPLY BREAKERS NR TXX-4993 86-43 ITT BARTON MODEL 580 SERIES SWITCHES NR TXX-5047 86-44 WELDED ATTACHMENTS TO E?fBEDDED STRIP PLATES R
TXX-6261 86-45 SEISMIC CATEGORY II SYSTEMS & COMPONENTS P*
11/11/87 86-46 GOULD BATTERY RACKS TRANSVERSE BRACING R*
12/04/87 86-47 FIRE PENETRATION SEAL DESIGN NR TXX-4996 86-48 ADEQUACY OF NONCONFORMANCE DISPOSITIONS P*
11/20/87 86-49 CONAX ADAPTOR MODULES & ELECTRICAL PENETRATIONS R*
01/20/88 86-50 UNISTRUT SPRING NUTS ON INSTRUMENT SUPPORTS R
TXX-6292 86-51 ANCHOR BOLTS SUPPLIED BY HILTI P*
10/21/87 86-52 CABLE TRAY SPLICES / CONNECTIONS R*
10/23/87 86-53 SEISMIC DESIGN OF CONDUIT R*
11/05/87 86-54 ORIGINAL DESIGN OF CONTROL ROOM CEILING R*
02/08/88 86-55 SEISMIC AIR GAP DESIGN ADEQUACY P*
11/11/87 86-56 DG ENGINE CONNECTING ROD ASSEMBLY NR TXX-5025 86-57 REINFORCING STEEL IN UNIT 1 RX CAVITY WALL NR TXX-6028 86-58 DRILLING / CUTTING OF REINFOR. STEEL IN FUEL BLDG NR TXX-6029 86-59 SUPPORT INSTALLATIONS-SPACING VIOLATIONS R
~ -
.p, SDAR INDEX-10/01/87 jf0.
SUBJECT DETERM. STATUS f
86-60 POLAR CRANE GIRDER AND GIRDER SUPPORT SHIM GAPS NR TXX-6544 l
86-61 POLAR CRANE RESTRAINTS NR TXX-6092 86-62 POLAR CRANE SUPPORT STRUCTURE R*
12/31/87 86-63 PIPE SUPPORT INSTALLATIONS R*
12/18/87 86-64 COATINGS FOR DIESEL FUEL OIL TANKS NR TXX-6461 86-65 UNCONSOLIDATED CONCRETE:-UNIT 2 RCB EXT. WALL NR TXX-6330 l
86-66 NON-CONTACT LAP SPLICES IN AUX. BLDG.
NR TXX-6282 86-67 PRE-OP VIBRATION TEST CRITERIA R*
10/22/87.
86-68 WEATHER PROTECTION FOR CLASS 1E COMPONENTS P*
10/23/87 86-69 SUPPORT OF CLASS lE WIRING NR TXX-6464 86-70 ELEV. TEMP. EFFECTS ON INSTRUMENT SUPPTS& TUBING R
~TXX-6220 86-71 CABLE PULLING TENSION P*
11/13/87 86-72 SMALL BORE PIPING AND SUPPORTS R*
11/20/87 86-73 ASME SNUBBER ATTACHMENT BRACKETS R
TXX-6751 86-74 ROCKWELL TERMINAL BOXES NR TXX-6372 86-75 ASCO SOLENOID VALVES IN PISTON AIR ACTUATORS OF PAPCO DAMPERS NR TXX-6287 86-76 DEVIATIONS IN GOULD BATTERY RACK DIMENSIONS P*
10/07/87 86-77 INSTRUMENT TUBING MINIMUM WALL REQUIREMENTS R
TXX-6228 86-78 STRUCTURAL STEEL BOLTING IN CABLE SPREAD ROOM P*
12/15/87 86-79 OVERTORQUED WESTINGHOUSE AR RELAYS NT TXX-6533 86-80 TORQUE VALUES FOR J.C. WHITE TUBING RESTRAINTS NR TXX-6140 86-81 BOP INSTRUMENT SETPOINT ERRORS P*
11/20/87 86-82 CTH WELDS USED TO SPLICE CHANNEL SECTIONS R*
11/20/87.
86-83 SBM ON POWER CABLES AND POWER RACEWAYS P*
11/13/87 1986: 83 TOTAL SDARS--31 REPORTABLE. 18 POTENTIAL i
O a
1 i
l l
l' L
SDAR INDEX-10/01/87 g' SUBJECT DETERM. STATUS 87-01 STATIC COMPUTER MODEL FOR SG BLDG P*
11/03/87 87-02 FISHER CONTROL VALVES NR TXX-6316 87-03 6.9 KV SWITCHGEAR INSTALLATIONS R
TXX-6334 87-04 PLUG WELDING ON EMBEDDED CHANNEL R
TXX-6538 87-05 EQ OF CABLE TO POST-LOCA HRRM P*
11/20/87 87-06 SQ OF AS-BUILT 480 VOLT POWER CENTERS P*
10/23/87 87-07 PROCUREMENT OF SPARE PARTS W/0 QUAL.REQTS.
P*
02/19/88 87-08 CAL. ACCURACY OF PRES.STD. DEAD WEIGHT TESTER P*
10/23/87 87-09 TERMINAL STUDS IN PK-2 TEST BLOCKS NR TXX-6619 87-10 CONTROL OF DESIGN MODIFICATIONS P*
10/22/87 87-11 DEFECTIVE CIRCUIT CARDS IN BATTERY CHARGERS P*
10/09/87 87-12 CONTAINMENT P/T ANALYSIS COMPUTER ERROR P*
12/11/87 87-13 CLASS 1E SEPARATION VIOLATIONS P*
02/19/88 87-14 SYSTEM OPERABILITY DURING TESTING NR TXX-6642 87-15 AIR ACCUMULATORS FOR CONTROL VALVES P*
11/18/87 87-16 LIMIT SWITCH WIRING P*
10/07/87 87-17 VALIDYNE 15V POWER SUPPLY NR TXX-6626 87-18 SQ OF CCW HX IN UNIT 1 P*
11/06/87 87-19 AMBIENT TEMPERATURE AFFECTS ON MSIV ACTUATORS P*
12/18/87 87-20 CRACKED PORCELAIN CONNECTORS ON 6.9KV TRNSIMRS R
TXX-6669 87-21 AFFECTS OF THERMOLAG ON DERATING FACTORS P*
10/29/87 87-22 IMPACT TESTING FOR CONTAINMENT LINER ATTACHMENTS P*
10/26/87 87-23 CONDUIT UNIONS R
TXX-6565 87-24 CONTAINMENT LINER NELSON STUD BENDING P*
11/25/87 87-25 DG FUEL OIL TANK VENT MISSILE PROTECTION P*
11/20/87 87-26 DG FUEL OIL TRANSFER PUMP SUCTION LIFT P*
10/26/87 87-27 GALVANIC CORROSION IN CCW AND SW SYSTEMS P*
11/24/87 87-28 CONDENSATE STORAGE TANK OVERPRESSURIZATION P*
11/30/87 87-29 CCW ISOLATION AFTER RCP THERMAL BARRIER RUPTURE P*
11/20/87 87-30 ROLL-AWAY MISSILE SHIELDS (RAMS)
P*
10/16/87 87-31 DIESEL GENERATOR CONTROL AIR REGULATOR NR TXX-6620 87-32 QUALITY CONTROL INSPECTOR QUALIFICATION R*
10/19/87 87-33 AUXILIARY FBEDWATER PUMP MOTOR FANS P*
10/07/87 87-34 EQUIPMENT N0ZZLE LOAD INTERFACES P*
10/30/87 87-35 RAYCIEM MOTOR CONNECTION KITS P*
10/30/87 87-36 EQUIPMENT QUALIFICATION P*
11/23/87 87-37 WESTINGHOUSE VALVES P*
12/09/87 87-38 FIRE DETECTION SYSTEM PC BOARDS P*
10/16/87 87-40 ELECT.ISOL. BARRIER FOR CLASS 18 AND NONIE RMS P*
01/15/88 87-41 DIFFERENTIAL PRESSURE TRANSMITTERS P*
11/23/87 87-42 TIERM0 COUPLE QUALIFICATION P*
11/23/87 87-43 SOLENOID VALVES INSULATION P*
10/16/87 87-44 UNISTRUT TUBING SUPPORT BOLTING P*
10/23/87 87-45 REACTOR COOLANT PUMP MOTOR BACKUP CIRCUITRY P*
11/13/87 87-46 CONTAINMENT SPRAY PUMP MOTOR ROTOR / STATOR GAP P*
10/16/87 87-47 CONSUMABLE MATERIALS REPLACEMENT PROGRAM P*
11/13/87 87-48 CABLE TRAY TRANSVERSE CLAMPS R*
02/06/88 87-49 SSSS INTERNAL WIRING TERMINATION P*
10/23/87 87-50 TURBINE DRIVEN AFV PUMP BEARING TEMPERATURE P*
11/06/97 87-51 480V CONTAIN. ELECTRICAL PENETRATION B/U PROT.
R*
12/18/87 87-52 CLASS lE BATTERY CHARGER CAPABILITIES 87-53 PIPE WHIP RESTRAINT DESIGN METHODOLOGY.
P*
10/30/87 P*
10/30/87 87-54 CLASS lE MOV MOTOR STARTERS P*
11/06/87 87-55 CONTAINMENT SPRAY PUMP RECIRCULATING PIPING P*
11/20/87 87-56 DEFICIENT PIPE WHIP RESTRAINTS P*
11/13/87 87-57 COMPUTER MODELING ERROR: COMPARE MOD 1A P*
11/16/87 87-58 COMPUTER MODELING ERRORS: RELAP-3 P*
11/16/87 87-59 IMPROPER APPLICATION OF CTH CONSTRUCTION AIDS R
[*],,._ _ - _ _ _
SDAR INDEX-10/01/87
!LO.
,, SUBJECT DETERM. STATUS 87-60 INSTALL. CONFIGURATION ON ASCO SOLENOID VALVES NR TXX-6746 87-61 SNUG TIGHT TORQUEING OF STRUCTURAL BOLTS P*
03/15/88 87-62 CLASS 5 PIPE SUPPORTS R
TXX-6731 87-63 PIPE WELD INSPECTION CRITERIA P*
ll/23/87 87-64 DESIGN BASIS TORNADO ANALYSIS FOR SAFETY EQUIP.
P*
12/11/87 87-65 LOCA EFFECTS ON HVAC DUCT INSIDE CONTAINMENT P*
11/30/87 87-66 STRUCTURAL BOLTING IN TENSION P*
03/29/88 87-67 UNDERSIZED BOLTS AND MISSING JAM NUTS P*
04/02/88 87-68 HILTI BOLT INADEQUACIES P*
10/02/87 87-69 DESIGN BASIS TORNADO ANALYSIS FOR HVAC DUCTWORK P*
12/02/87 87-70 PRE-BEND PIPE WALL THICKNESS P*
12/18/87 87-71 MISSING WELDS AND UNDERSIZED MEMBERS P*
02/08/88 87-72 IMPROPERLY DEFINED WELD LENGTHS P*
01/07/88 87-73 UNSOUND CONCRETE MOTAR P*
10/28/87 87-74 INACCURATE METHODS OF WELD MEASUREMENTS P*
10/02/87 87-75 EP0XY GROUT TEMPERATURES P*
11/13/87 87-76 FIELD DRILLED CABLE TRAY HOLES R
TXX-6763 87-77 CABLE TRAY WELD DOCUMENTATION REQUIREMENTS NR TXX-6761 87-78 CABLE TRAY WELDING PROCEDURES P*
12/01/87 87-79 CABLE AND RACEWAY DATA SYSTEMS CALCULATIONS P*
12/04/87 87-80 FUSE SIZING P*
01/29/88 87-81 WEIDMULLER TERMINAL BLOCK CONNECTIONS P*
01/08/88 87-82 FIRE DETECTION CONTROL PANELS P*
11/24/87 87-83 SEISMIC ANALYSIS OF SW DISCHARGE STRUCTURE P*
10/02/87 87-84 DG SECONDARY M&R CT CIRCUIT CABLE LEADS P*
10/05/87 87-85 DEGRADATION OF CLASS lE CIRCUITS P*
10/05/87 87-86 180 VAC CIRCUIT BREAKER SIZING P*
10/05/87 87-87 CVCS RELIEF VALVE PIPING P*
10/05/87 87-88 6.9 KV CONTROL CIRCUIT VOLTAGE DROPS P*
10/05/87 87-89 125 VDC TO SUPS VOLTAGE DROP P*
10/05/87 87-90 RHR RELIEF VALVE PIPING P*
10/05/87 87-91 STARTUP TRANSFORMER OVERLOAD P*
10/05/87 87-92 INSTRUMENT PANEL CABLE SEPARATION P*
10/05/87 87-93 MCC STARTER COILS P*
10/05/87 87-94 UNINTERRUPTABLE POWER SUPPLY LOADING P*
10/05/87 87-95 UNINTERRUPTABLE POWER SUPPLY INPUT SPECIFICATION P*
10/05/87 87-96 CABLE SHIELDING TERMINATION INSPECTIONS P*
10/08/87 87-97 FLEX CONDUIT INSPECTIONS P*
10/08/87 87-98 CABLE RACEWAY FILL CALCS: CABLE OUTSIDE DIAMETER P*
10/09/87 87-99 CABLE OUTSIDE DIAMETER REQUIREMENT P*
10/09/87 87-100 CONTAINMENT PENETRATION OVERPRESSURE PROTECTION P*
10/12/87 87-101 CLASS lE CABLE ARRANGEMENT P*
10/12/87 87-102 CABLE TRAY SEPARATION CRITERIA P*
10/12/87 87-103 CRACKED GEARS IN VALVE OPERATORS P*
10/12/87 87-104 SAFETY SYSTEM SETPOINT CALCULATION ERROR P*
10/14/87 87-105 CONDUCTOR LUG TERMINATIONS P*
10/14/87 87-106 COMPONENT DESIGN SPECIFICATION DISCREPANCY P*
10/23/87 87-107 AUXILIARY FEEDWATER DESIGN PRESSURE P*
10/26/87 87-108 AUXILIARY FEEDWATER PUMP LOW SUCTION TRIP P*
10/26/87 1987: 108 TOTAL SDARS--
7 REPORTABLE. 94 POTENTIAL
_ _ _ _ - _