ML20083K026
| ML20083K026 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/25/1978 |
| From: | Parker W DUKE POWER CO. |
| To: | Baer R, Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20083K035 | List: |
| References | |
| NUDOCS 7810180076 | |
| Download: ML20083K026 (19) | |
Text
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DUKE PoWEF MPANY
.Powza.Burprwo 422 SouTa Canuca Srazzr, CaAntorrz. N. C. asa sa D
September 25, 1978 re c.-o c: 4.c. n.
m w A
- o. er a n za. a n.
373-4083 v.c p.cs,0c,
Svenne PeocuCtiose f
I Mr. Harold R. Denton, Director l
Office of Nuclear Reactor Regulation I
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 g
Attention:
Mr. Robert L. Baer, Chief Light Water Reactors
-i Project Branch No. 2
Subject:
McGuire Nuclear Station Preservice Inspection Plan g
Docket Nos.
/and 50-370
Dear Sir:
A letter from Mr. Karl Kniel, dated June 14, 1977, transmitted questioti 121.14 concerning the McGuire Inservice and Preservice Inspection Plans. Our 3esponse to this question was transmitted to you in Revision 23 to the McGuire (SAR,
'I 21, 1977. After reviewing our response to question 121.14 your staff dated July
)
issued a request for additional information, with regard to the preservice in-
~1 spection plan, by letter dated April 26, 1978. Subsequently, we tratismitted r 2
response to this request in a letter dated May 31, 1978. Af ter furtb'ev-discus-sions with members of your staff it was determined that Duke would provide, more detailed requests for relief from ASME Code Section XI requirements.
In response to this, Duke provided you with requests for relief from ASME Code Section.XI
~
identified as MC-1-01 through MC-1-024 by this letter and previous letters dated July 24 and Septe=ber 5, 1978. This completes all presently known requests for relie for McGuire Unit 1, Class 1 components.
V truly yours, N
N i
AElle e
William O. Parker, Jr.
GJP:scs Attachment
/
7 ttort o 07 &
Snrial No. MC-1-024 '
p..,
,o I
Page 2 of 2 i
i D' UKE POWER COMPANY Request For Relief From inservice Inspection Requirement Ill.
Basis for Requesting Relief (cont.)
j To examine the 3% of weld obscured would require grinding off the lifting lugs. Considering that the area was radiographed af ter fabrication, the added cost and loss in time does not justify lug j
removal.
t IV.
Alternate Examination:
r i
No alternate examination is possible.
l l
V.
Implementation Schedule:
Inservice Inspection will be performed in accordance with the Section XI required by 10CFR 50.55a, paragraph (g) to the extent j
possible.
e 6
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Scrial No. MC-U-@VW Page 1 of 2 DUKE POWER COMPANY 3
Request For Relief From Inservice Inspection Requirement Station: McGuire Nuclear Station Unit:
I Reference Code: ASME Boiler and Pressure Vessel Code,Section XI 1971 f
Edition through Winter 1972 Addenda 1.
Component for which exemption is requested:
a.
Name and identification Number:
Reactor Coolant Pumps l A, IB, IC, ID Pump Casing Ligament Area b.
Function:
Circulate reactor coolant c.
ASME Section lli Code Class:
Class I d.
Valve Category:
NA 11.
Reference Code Requirement that has been determined to be impractical:
Table IS-261, item 5.4 Volumetric examination of pump casing ligament area between stud holes. Ultrasonic testing has been unsuccessful in penetrating the cast stainless steel pump casing material, l
Ill.
Basis for Requestl'ng Relief
- a. Material - SA-351 Alloy CF8 cast stainless steel
- b. Estimate of extent of preservice examination performed - None
- c. Original fabrication examination - The Flange area was radiographed and inspected with dye penetrant.
- d. Measures which would be required to make the area accessible - The
' area is accessible for examination,
- e. Reference Drawing - MCM 1701-01-120 Attached 4
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Serial No.
MC-1-018
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Page 2 of 2 i
DUKE POWER COMPANY Request For Relief From
,4 '
inservice inspection Requirement Ill.
Basis for Requesting Relief (cont.)
It is believed that the shop radiographic examination and a preservice surface examination will provide adequate assurance of component integ r i ty.
IV.
Alternate Examination:
A surface examination will be performed in lieu of the required volumetric examination. This examination will be performed until such time as an acceptabl,e UT techinque is developed.
V.
Implementation Schedule:
Surface examination data will become the Preservice Examination reco rd.
Inservice inspections will be scheduled in accordance with the Section XI edition required by 10CFR50.55(a), paragra'ph g.
9 4
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59tr o oj i sie). MC-1-06V
{
i Page 1 of 2 i
DUKE POWER,COMPA,NY Request Fdr Relief From inservice Inspection Requirement S ta tioq: McGuire Nuclear Station e
Unit:
1 Reference Code: ASME Boiler and Pressure Vessel Code Section XI,1971 Edition through Winter 1972 Addenda 1.
Component for which exemption is requested:
a.
Name and Identification Number:
Reactor Coolant Pumps I A, IB, IC, ID Lower Seal Housing Bolts (12) per pump 2.00" x 8" long b.
Function:
Circulate reactor coolant c.
ASME Section ill Code Class:
Class I d.
Valve Category:
NA 11.
Reference Code Requirement that has been determined to be impractical:
Table IS-261, item 5.4 Volumetric examination of lower pump seal housing
(
Due to bolt head configuration (recessed hex), an ultrasonic bolts.
examinaiton is impossible.
lit.
Bast's for Requesting' Relief
- a. Material - SA-193 B-7 tool steel
- b. Estimate of extent of preservice examinaton performed - None
- c. Original fabrication examination - magnetic particle surface examination
- d. Measures which would be required to make the bolts accessible -
the bol t is accessible, but due to the geometry,UT examination is not possible
- e. Reference Drawing - MCM 1201-01-120 attached 4
y
Serial No, MC-1-019 ~
Page 2 of 2 DUKE POWER COMPANY Request For Relief From g
Inserv' ice inspection Requirement Ill.
Basis for Requesting Relief (cont.)
The lower seal housing is only pressurized to 80 psig. Complete disassembly of the pump to remove the bolting for a surface examination would not justify the cost and loss of time involved.
1 IV.
Alternate Examination:
No alternate examination is possible. However when the pumps are disassembled for maintenance, the bolting will be inspected by the magnetic particle technique.
V.
Implementation Schedule:
Inservice inspection will be accomplished by the magnectic particle technique.
1 s
b m
1
Page 1 of 2 b
. DUKE POWER,COMPA!4Y Request For Relief From
-inservice inspection Requirement Statioq: McGuire Nuclear Station 9
Unit I
Reference Code: ASME Boiler and Pressure Vessel Code Section XI,1971 Edition through Winter 1972 Addenda.
I.
. Component for which exemption is requested:
a.
Name and Identification Number:
Reactor Coolant Pumps I A, IB, IC, ID Lower Seal Housing Ligament Area t
b.
Function:
Circulate reactor coolant c.
ASME Section 111 Code Class:
Class I d.
Valve Category:
NA
- 11. Reference Code Requirement that has been determined to be impractical:
Table IS-261, item 5.4 Volumetric examination of lower pump housing Examination is not possible without disassembly of the ligament area.
pump.
111.
Basis for Requesting Relief Material - ASTM 182 Type 304 stainless steel a.
b.
Estimate of extent of preservice examination performed - None Original fabrication examination - Ultrasonic and dyle penetrant c.
examinations d.
Measures which would be required to make the lower seal housing accessible - complete disassembly of pumps.
e.
Reference Drawing - MCM 1201-01-120 Attached G
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s.
Serial No. MC-1-020 Page 2 of 2 DUKE POWER COMPANY Request For Relief From q'
Inservice Inspection Requirement Ill.
Basis for Requesting Relief (cont.)
The shop fabrication examination performed is the same as required by ASME Section XI. A redundant examination would provide no increase in component safety and would not justify the cost and time delay of pump disassembly.
f IV. Alternate Examination:
The lower seal housing will be tested during the first maintenance disassembly.
V.
Implementation Schedule:
Inservice Inspection will be performed in accordance with the Section XI required by 10CFR50.55a, paragraph (g).
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9 6
e
Ntt-vvm Page 1 of 2 J
DUKE POWER,CQMPANY Request For Relief From
-inservice inspection Requirement S ta tion: McGuire Nuclear Station 9
Unit:
I
. Reference Code: ASME Boiler and Pressure Vessel Code Section XI,1971 Edition through 1972 Winter Addenda 1.
Component for which exemption is requested:
a.
Name and Identification Number:
Reactor Vessel Head, Control Rod Drive Penetrations (78)
National Board Number 20266 I
b.
Function:
Reactor coolant pressure boundary c.
ASME Section 111 Code Class:
Class I d.
Valve Category:
NA II. Reference Code Requirement that has been determined to be impractical:
(
Table 1S-261 Item 1.5 Volumetric examination of 78 control rod drive penetration welds.
Ill. Basis for Requesting Relief
~
Material - CRDM tubes are SA-167 inconel welded into the SA533 a.
carbon steel closure head.
b.
Estimate of extent of preservice examination performed - No volumetric, visual at hydrostatic test conditions completed satisfactorily.
Original fabrication examination - The weld and base metal were c.
l examined with dye penetrant.
l d.
Measures which would be required to make the penetration welds accessible - Due to the internal J-groove geometry of the weld, no alteration could make the area accessible.
1
Serial No.MC-1-021 p
Page 2 of 2 DOKE PONER COMPANY Request For Relief From Inservice inspection Requirement Ill.
Basis for Requesting Relief (cont.)
Attachment I shows the weld groove geometry.
The 1974 Edition Section XI requires only visual examination of partial penetration vessel welds.
Unit I will be upgraded to the 1974 Edition Section XI at the commence-ment of commercial operation.
IV.
Alternate Examination:
1 The CRDM penetration tubes were examined visually during hydrostatic test with no evidence of leakage.
V.
Implementation Schedule:
The visual examination will be used as the Preservice Examination Record.
Inservice inspections will be performed in accordance with the Section XI edition required by 10CFR50.55(a), paragraph g.
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, Sarlal No.
-MC-1-022 Page 1 of 2 u
o DUKE POWER. COMPANY Request For Relief From Inservice inspection Requirement
_[~
,5 S ta tion: McGuire Nuclear Station g
Unit:
I Reference Code: ASME Boiler and Pressure Vessel Code.Section XI,1971 Edition through Winter 1972 Addenda q
I.
Canponent for which exemption is requested:
a.
Name and identification Number:
Reactor Vessel Incore Inst ument Penetratlons (58),
National Board Number 20766 I
b.
Function:
Reactor coolant pressure boundary s
c.
ASME Section til Code Class:
L Class I s
d.
Valve Category:
NA II.
Reference Code Requirement that has been determined to be ~ impractical:
Table IS-261 Item 1.5 Volumetric examination of 58 vessel I
instrument penetration welds.
A
~
lit.
Basis for Requesting Relief u
Material - Instrument tubes are S8-166 Inconel welded into the a.
j',.
SA533 carbon steel bottom head.
b.
Estimate of extent of preservice examination performed ^ No volumdtric, 7
visual at hydrostatic test condition cenpieted.
l c.
Original fabrication examination - Each weld pass examined wit.h dye penetrant,then all internal surface of vessel examined with dye penetrant af ter hydrostatic test.
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Sarial No, MC-1-022 0.-
Page 2 of 2
~
DUKE P0'WER COMPANY Request For Relief From 2
Inservice inspection Requirement lil.
Basis for Requesting Relief (cont.)
d.
Measures which would be required to make the penetration welds accessible - Due,to the internal J groove geometry of the weld, no alteration could make the area accessible.
Attachment I shows the weld groove geonetry. The 1974 Edition Section XI
, requires only visual examination of partla1' penetration vessel welds.
Unit I will be upgraded to the 1974 Edition Section XI on the commence-ment of commercial operation.
g IV.
Alternate Examination:
~
The incore Instrument penetrations were examined visually during the hydrostatic test with no evidence of leakage.
V.
Implementation Schedule:
.y.
~-
The visual examination will be used as the Preservice Examination record.
inservice inspections will be performed in accordance with the Section XI edition required by 10CFR50.55(a), paragraph g.
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Pcga 1 of 2 l
DUKE P0,WER COMPANY Request For Relief From
' Inservice inspection Requirement Station: McGuire Nuclear Station Un t't*:
I Reference Code: ASME Boiler and Pressure Vessel Code Section XI,1971 Edition through Winter 1972 Addenda I.
Component for which exemption is requested:
a.
Name and identification Number:
Control Rod Drive Mechanisms (78) Housing Welds b.
Function:
(
Reactor coolant pressure boundary c.
ASME Section III Code Class:
Class I d.
Valve Category:
NA II.
Reference Code Requirement that has been determined to be impractical:
Table 15-261 Item 1.5 Volumetric examination of 78 CRDM housing welds.
Ill.
Basis for Request 1~ng Relief Material - CRDM Penetration tubes are 58-167 inconel welded to a a.
SA-182 F316 stainless steel flange.
b.
Estimate of extent of preservice examination performed - Approximately 40 of the 78 welds will be fully e:tamined.
)
Original fabrication examination - Each weld was examined by c.
radiography and dye penetrant.
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hWrT&TRN'N Page 2 of 2 DUKE POWER COMPAl;Y Request For Relief From q'
Inservice Inspection Requirement e
Ill.
Basis for Requesting Relief (cont.)
d.
Measures which would be required to make the welds accessible -
Complete disassembly of the head and CRDM's. Welds would still not be completely accessible.
Attachment i shows the weld geometry. The 1974 Edition Section XI requires that only the peripheral CRDM housing welds be examined.
Unit I will be upgraded to the 1974 Edition Section XI at the comencement of commercial operation.
I IV.
Alternate Examination:
.The 40 peripheral CRDM housing welds will be examined fully by ultrasonic testing.
V.
Implementation Schedule:
The examination of 40 CRDM housing welds will become the Preservice Examination record, inservice inspections will be performed in accordance with the Section XI edition required by 10CFR50.55(a),
g paragraph g.
e-4