ML20034H558
| ML20034H558 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/15/1993 |
| From: | William Cahill, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9303190002 | |
| Download: ML20034H558 (13) | |
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Log #.TXX-93107-
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ME File # 10010 E,
Ref. # 10CFR50.55a r-TUELECTRIC Harch.15, 1993)
Wmiam J. Cahilt, Jr.
Gnwp Yire besident s
U._ S. Nuclear Regulatory _ Commission Attention:
Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAN ELECTRIC STATION (CPSES)
DOCKET NO. 50-445 j
INSERVICE INSPECTION PROGRAM RELIEF RE0 VESTS i
Gentlemen:
la The purpose of this transmittal is to submit relief requests B-4 B-5, B-6, o
C-5, C-6 and C-7 to certain inspection requirements of Section XI of the
'ASME Boiler and Pressure Vessel Code. These requests are included as l
Attachments 1 through 6~,
respectively, to this transmittal.
Please note that relief _ request B-6 was previously submitted to you as
'f relief request B-1 via TXX-9213B dated March 12.'1992.
Originally"a relief' request designated B-1 was submitted to you via TXX-91377 dated ~
l October 16. 1991.
Based on discussions with the NRC Staff. -TU-Electric -
,i believed this first B-1 relief request was 'not' needed and the B-1 designator 1)
.was reused for a second.(different) relief request transmitte'd. to you via l
Subsequently, the first B-1 designated relief request was approved by.NRR letter dated October 1. 1992, In order to correct.the j
resulting duplication. 'the second B-1 relief request has been redesignated B-6 in this transmittal.
-t TU Electric' requests your approval of these relief requests by f
September 30, 1993.
I 1
Sincerely.
.[
William J. Cahill. Jr.
I!
By:
D. R. Woodlan
}gggg Docket Licensing Manager j
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CBC/vid Attachments-j!
ci-Mr..J. L. Milhoan, Region IV Mr. T. A. Bergman, NRR l
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'Mr. G.
.Bynog TDLS i
Resident Inspectors 1(2) j
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Attac5. ment 1 to TU 43107
'Ptg2 l'of 1 Relief Request B-4 Item for which Relief is Requested:
Nozzle inner radii Code Class:
1 Examination Requirement (s):
Table:
IWB-2500-1 Category:
B-D Item No.:
B3.120, B3.140 Table IUB-2500-1, Category B-D, Item Number 3.120 and B3.140 require volumetric examination of the nozzle inside radius section for nozzles associated with the pressurizer and steam generators (primary side).
Basis for Relief:
7 Specialized techniques and nozzle specific calibration blocks are t
required to ensure meaningful results for volumetric examination of the referenced inside radius sections. To determine which nozzles warranted the use of these enhanced techniques, an evaluation of each nozzle was c
performed.
In this evaluation the nozzle stress and usage factor as well as the potential for thermal shock was considered. Of the referenced nozzles only the pressurizer surge and spray nozzles exhibit a potential for thermal shock and only the spray nozzle contains stresses and associated usage factor close to the allowable.
It is therefore concluded that only the pressurizer spray be subjected to the required volumetric examination using enhanced techniques to maximize coverage.
Limited access due to the close proximity of the' pressurizer heater connections and the fact that the nozzle stresses do not approach the allowable limits, indicate that the additional cost and time associated with the enhanced examination methodology is not warranted
+
for the surSe line.
For the remainin5 pressurizer nozzles,-(relief and safeties) as well as the integrally cast primary. side steam generator nozzles, the cost and additional exposure associated with volumetric examination do not produce a corresponding increase in reliability or safe ty.
Alternative Examination (s):
None Safety Impact:
i The referenced evaluation indicates that only the pressurizer spray line experiences conditions under which the integrity of the inner radius t
mi he be compromised. Not performing volumetric examination on the-S remaining nozzles will not introduce any anticipated impact on the overall plant quality and safety.
Radiological Concerns:
Performance of fewer inner radius examinations will result in less exposure.
Also, a significant number of manhours in radiation areas i
will be saved by not installing scaffolding, removing and reinstalling insulation and then removing the scaffolding.
P
m.
Attadhnent 2 to TXX-93107 Page 1 of.3 RELIEF REQUEST B-5 A.
Item for which relief is requested:
TBX-1-4103-1 TBX-1-4202-1 Circumferential Piping Welds B.
Item Code Class:
1 C
Examination requirement from which relief is requested:
ASME Section XI 1986 edition, no addenda.
'Ihe requirement for volumetric examination of 100% of the weld length as described in Table IWB-2500-1, Examination Category B-J. Item No.
B9.11.
D.
Basis for relief:
The specific examination area geometries of these two pipe to. valve welds preclude the. complete ultrasonic examination of the volume required by Fig. IWB-2500-8. Approximately 55% of the exam volume for weld TBX 4103-1 and 11% of the exam volume for weld TBX-1-4202-1 did not receive the full code required coverage.
Best effort examinations consisting of two separate base metal angle shear and longitudinal waves were performed. Full circumferential scan coverage was achieved for both welds. Axial scan coverage was achieved in 1 direction with at least 1 beam angle for 85% of the exam volume of weld TBX-1-4103-1 (see page 2). Axial scan coverage was obtained in 1 direction with 2 beam angles for the entire exam volume of weld TBX-1--
4202-1 (see page 3).
There were no recordable indications identifled by the best effort volumetric exams or by the required surface exams performed.
E.
Substitute examinations:
.None F.
Anticipated impact on the overall level of plant quality and safety:
None
' Attachment 2 to TXX-93107 Page 2 of 3 WESTINGHOUSE NUCLEAR SERVICE DIVISION INSPECTION SERVICES LIMITATION TO EXAMINATION N" ~
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Attcchment 2 to TIZ-93107
?:33 3 of 3 WESTINGHOUSE NUCLEAR SERVICE DIVISION INSPECTION SERVICES LIMITATION TO EXAMINATION coxAM/F MAf uNur Ngl
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EX AMIN E R DATE
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PROVIDE GENEFtAL INFORMATION TO DESCRIBE APPROXIMATE SIZE, LOCATION AND TYPE OF LIMITATION.
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8a9079 L
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-Paga 1 of 3 RELIEF REQUEST a
B-6 A.
Item for which relief is requested:
TBX-1-1300-1 RV closure head to flange weld 4
TBX-1-1300-2 RV closure head ring to disciweld B.
Item Code Class:
1 C.
Examination requirement from which relief'is requested:
1 Table:
Examination Category:
B-A Item No.:
Bl.40 and Bl.21 Table IWB-2500-1, Category B-A, Item No. Bl.40 requires volumetric and surface examination of the reactor vessel head to flange weld and Item No. Bl.21 requires volumetric examination of the reactor vessel circumferential head welds.
The Plan requires that 1/3 of each of these welds be examined each period.
D.
Basis for relief:
1/3 of welds TBX-1-1300-1 and TBX-1-1300-2 were ultrasonically examined to the maximum extent possible, however, a portion of each was unable to be examined due l
to limitations encountered from the flange, shroud and a lifting lug.
Required surface exam was performed and-resulted in no indications.
See attached Limitation to Examination sheet.
E.
Substitute examinations:
None F.
Anticipated impact on the overall level of plant quality and safety:
None l
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Attacbment' 3 to Txx-03107
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WESTINGHOUSE NUCt. EAR SERVICE Division R 5 2.
4NSPECTICN SERVICES LIMITATION TO EXAMINATION 2X-e -G00 MV. /
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NOTE:
8% of weld #1 not examined using 45" angle team 13% of weld #2 not examined using 45' angle beam i
t 12% of weld #1 not examined using 60 angle oeam 17% of weld #2 not examinea using 60 angle Deam
Attcchm:rt 4 to TXX-93107
..?cg2 1 ofl 1 5
Relief Request C-5 Item for which Relief is Requested:
Nozzle inner radii Code Class:
2 Examination Requirement (s):
Table:
IUC-2500-1 Cate5ory:
C-B Item No.:
C2.22 Table IWC-2500-1, category C-B, item number C2.22 requires volumetric examination of the nozzle inside radius section for nozzles associated i
with class 2 components.
The nozzles of concern are Main Steam and-Feedwater (steam generator secondary side), RHR Heat Exchanger and CT Heat Exchanger nozzles.
Basis for Relief:
Specialized techniques and nozzle specific calibration blocks are required to ensure meaningful results for volumetric examination of the-referenced inside radius sections. To determine which nozzles warranted the use of these enhanced techniques, an evaluation of each nozzle was performed.
In this evaluation the nozzle stress and usage factor as well as the potential for thermal shoct was considered. Of the referenced nozzles, only the main feedwater nozzles exhibit a potential.
for thermal shock and contain stresses and associated usage factor close to the allowable.
It is therefore concluded that only the main feedwater nozzles be subgected to the required volumetric examination using the enhanced technLques to maximize coverage.
For the' nozzles associated with main steam, RHR heat exchanger and CT heat exchanger, the cost and additional exposure associated with volumetric examination do not produce a corresponding increase'in reliability or safety.
Alternative Examination (s):
None Safety impact:
The referenced evaluation indicates that only the main feedwater nozzles experience conditions under which the integrity of the inner radius might be compromised. Not performing volumetric examination on the remaining nozzles will not introduce any anticipated impact on the overall plant quality and safety.
Radiological Concerns:
Performance of fewer inner radius examinations will result in less exposure. Also, a sipificant number of manhours in radiation areas will be saved by not installing scaffolding, removing and reinstalling insulation and then removing the scaffolding.
Attcphn:nt 5 to T::-93107
.?cge'l of 2 RELIEF REQUEST C-6 A.
Item for which rehef is requested:
TBX-2-2580-3 Circumferential Piping Weld R
Item Code Class:
2 C.
Examination requirement from which relief is requested:
ASME Section XI 1986 edition, no addenda.
The requirement for volumetric examination of 100% of the weld length as described in Table IWC-2500-1, Examination Category C-F-1, Item No.
C5.11.
D.
Basis for relief:
The specific examination area geometry of this pipe to valve weld precludes the complete ultrasonic examination of the volume required by.
Fig. IWC-2500-7. Approximately 50% of the exam volume did not receive the full code required coverage.
A best effort examination consisting of two separate base metal angle shear and longitudinal waves was performed. Full circumferential scan coverage was obtained. Axial scan coverage was achieved in at least 1 direction with at least 1 beam angle for the entire exam volume (see page 2).
There were no recordable indications identifled by the best effort volumetric exam or by the required surface exam performed.
E.
Substitute examinations:
None F.
Anticipated impact on the overall level of plant quality and safety:-
None
-Attachnent 5 to TII-93107
.Page.*2 of 2 3
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'Attcchment 6 to TXX-93107
, Page*1 of 2 RELIEF REQUEST C-7 A.
Item for which relief is requested:
TBX-2-3110-1-3WS, 4WS Integrally Welded Pump Attachments l
a Item Code Class:
2 C.
Examination requirement from which relief is requested:
ASME Section XI 1986 edition, no addenda.
The requirement for surface examination of 100% of the weld length as described in Table IWC-2500-1, Examination Category C-C, Item No.
C3.30.
D.
Basis for relief:
The specific conflguration of the pump base plate and housing does not provide access for IIquid penetrant examination of 23% of the area required by Fig. IWC-2500-5 (see page 2). The accessible areas have been examined with no unacceptable indications identified.
E.
Substitute ernminations:
None F.
Anticipated impact on the overall level of plant quality and safety:
None
P.teachment' 6' to TX't-93107 PagE 2 of-2 l
I WESTINGHOUSE NUCLEAR SERVICE DIVISION INSPECTION SERVICES l.lMITATION TO EXAMINATION PLANT b o MQ M CME Mr_ h K NO' [
T RX 3110, TEV-I UNIT SKETCH SYST/ COMP (EMTMFut.h (Mhar-mf.- Pu u P f
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PROCEDURE EXAMINER lO~lI~SA DATE t
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WS QELATED TO: U/T P/T M/T V/T ITEMtsl:
't PROVIDE GENERAL INFORMATION TO DESCRIBE APPROXIMATE $!ZE, LOCATION AND TYPE OF LIMITATION.
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