ML19326C226
| ML19326C226 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/19/1977 |
| From: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| To: | Desiree Davis Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19326C227 | List: |
| References | |
| 1-107-7, NUDOCS 8004220801 | |
| Download: ML19326C226 (6) | |
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. DISTRIBUTION AFTER ISSUANC JF OPERATING LICENSE u.s.NucLzAn mEcuLATony coe ?lss4CN CCCXET NL W SEM INRC Penu 195 V _ 30. 313
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. NRC DISTRIBUTION Pen PART 50 DOCKET MhTERIAL
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FROM:
CATECPCoCUMENT Arkansas Power & Light Company 10/19/77 j Mr. D. K. Davis Little Rock, Arkansas cATE RECElvto i
William Cavanaugh III 0726/77 l
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' DTTEM CNCTORIZSD PRCP INPUT PCMM NuMSER CP COPf ES MECElVf D MRIGINAL MNCLAgggpt gO i
Ccerv i 5i M t>C)
Request.
Att. 2 - Inservice.Insting Waiver Request.
Att. 3 - Tech Specs proposed change concerning I
the incorporation of. provisions of compliance with 10 CFR 50.55a for Unit No.
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REGEATOM uGCKET FlECOPY H ELPIN G B UILO ARKANSAS ARK ANS AS POWER & LIGHT COMPANY p0. eQx SS1 Lif TL. AOCM. ARK ANSAS 72203 e (5013 371 -4000 October 19, 1977 g7Euc 6Oc q [OK e(C/yph s
1-107-7 Director of Nuclear Reactor Regulation 3 .s. %%, l9'h
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A ATIN: Mr. D. K. Davis, Acting Chief
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l Operating Reactors Branch #2 U. S. Nuclear Regulatory Commission N
Washington, D. C.
20555 N
Subject:
Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Proposed Technical Specifications (File: 1511.1)
Gentlemen:
Pursuant to 10 CFR 50.55a, a review has been conducted of Arkansas Nuclear One-Unit 1 to determine the extent to which conformance with the provisions of the ASME Section XI Code through the Summer 1975 Addenda are practicable within the limitations of design, geometry and materials of construction. Attachments 1 and 2 provide the basis of the requested exceptions from the abovementioned code for inservice inspection and inservice testing, respectively. The inservice inspection and testing interval, specified in the 1974 Code with addenda through Summer 1975, save those granted exceptions, of Code Class 1, 2 and 3 components, pumps and valves will begin on April 19, 1978.
As committed in our June 9,1976 letter, please find enclosed as Attach-ment 3 our proposed technical specifications to incorporate provisions of compliance with 10 CFR 50.55a for Arkansas Nuclear One-Unit 1.
The pro-posed changes are identified by vertical lines in the margins. Please note that some changes are merely editorial.
Ve truly your l
C. -
William Cavan II Executive Director, Generation 6 Construc WC:DG4: tw Attachment r.-
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Attachm;;nt I 1
NDE INSERVICE INSPECTION WAIVER REQUEST
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ASME Section XI - 1974 with Addenda t' ru Summer 1975 Component:
Reactor Vessel ASME Class:
1 TABLE:
IWB-2600 Item Category Description Discussion Bl.4 B-D Four Inlet Impractical Code Requirement:
Nozzles MKl8 Examine two no zles during to MK86/87.
the first and two during the Two Core Flood second thirds of the interval Nozzles MK17 to per IWB-2411.
MK86/87 Reason for Waiver:
Access to Inlet & Core flood no::les would require defueli.
and removal of core barrel.
Alternate Exar' nation:
Examine 100% of both outlet no::les by the end of the first third of the interval from the nozzle Bore.
Examin:
100% of all nozzles from the vessel ID with the vessel internals removed by the end of the interval.
Cl.6 B-F Two Core Flood Impractical Core Requirement:
No :lc Safe-End Examine one weld during the Welds MK17 to first and last thirds of MK89 the interval per IWB-2411.
Reason for Waiver:
Access would require defuelint and removal of Core barrel.
Although these welds were examined from the OD during baseline, ultrasonic examina%
from the vessel ID using a rG mote examination device is perferred to limit high radio ation exposures to personnel.
Alternate Examination Examine 100% of both welds from the vessel ID by means of a remote. examination devi@
at the end of the interval.
Bl. ll-B-G-2 CRDM Bolts and Impractical Code Requirement:
Nuts to Head Examine 100% of total quantiS Flange
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ComponOnt:
Rocctor..ssol ASME Class:
1 TABLE:
IWB-2600 Item Category Description Discussion Bl.ll B-G-2 CRDM Bolts Reason for Waiver:
and Nuts to It is impractical to visually Head Flange examine the light flange bolts on each of the 69 CRDM's from the platform of the head servi (-
structure, approximately 20 feet above the flange surface.
Most of the bolts on the 24 peripheral CRDM can be observe through the twelve 12" dia, po.
in the service structure cylin The remainder of the CRDM's ar-accessible for exsmination on1 when removed.
Alternate Examina' tion:
Examine bolts and nuts on 10%
of peripheral CRDM's to coinci6 with the extent of CRDM exami-nation as required by Category B-O " Pressure Retaining Welds in CRD Housing."
Component:
Piping Pressure Boundary ASME Class:
1 TADLE:
IWB-2600 Item Category Description Discussion B.4.5 B-J Circumfenential Impractical Code Requirement:
Pipe Welds:
The area of examination shall High Pressure include the weld and one wall Injection Lines, thickness beyond the edge of Welds Al-SA, A2-the weld.
4A, Dl-10A,and Reason for Waiver:
B2-10A.
Core High Pressure Injection welds Flood Lines, Welds Al-8A, A2-4A, B1-10A, and B2-W-1 and Y-1.
10A are inside penetrations in (See Attached the Shield wall and are not
~ Sketches.)
accessible for examination.
Core Flood welds W-1 and Y-1 are inaccessible for examinatif due to pipe supports.
These welds were not examined during baseline and this fact is docui mented in the preoperational inspection report.
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Componant:
Piping Prgssuro Boundary ASME Class:
1 1
TABLE:
IWB-2600 I' em Category Description Discussion t
B4.9 B-K-1 Integrally Impractical Code Requirement:
Welded Supports Volumetric examination of the weld to the pressure retaining boundary, the base metal benea the weld zone and along the support attachment member for a distance of two support thic nesses.
Reason for Waiver:
The welds are not designed fo ultrasonic examination.
Most of the welded attachment for supports are fillet welds (as opposed to full penetration) and are comprised of componen' with geometric configurations that prohibit ultrasonic exam ation of the examinat on area Alternate Examination:
Surface Examination Inservice Inspection of Components or welds as required by the 1974 ASME Doiler and Pressure Vessel Code Section XI, with Addenda thru Summer 1975 will be conducted to the maximum practical extent possible.
Althoug:
Appendix I, "Ultrisonic Examination "of the ASME Code Section XI does not apply to piping, examination results are recorded on the data in accord-ance with I-5120., " Extent of Scanning".
Class 1 and 2 examinations will be conducte' according to this philosophy.
We do not feel any of the ASME Code Section XI requirements for the Class 2 system are impractical for Inservice Inspection and no specific exceptions are taken for Class 2 components.
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Attachm:nt 2 INSERVICE TESTING WAIVER REQUEST ASME Section XI - 1974 With Addenda Thru Summer 1975 1.
Pump Testing per IWP Impractical Code Requirement:
Take vibration measurements on Service Water Pumps (P4A, B and C) per requirements of paragraph IWP-4500. These pumps are Class 3 components.
Reason for Waiver:
These pumps are submerged with extended casings and shafts with water lubricated radial bearings in the fluid flow path.
Alternate Examination:
Take vibration readings at the lower driver bearing (radial G axial).
2.
Stroke Time Testing of Valves per IWV Impractical Coda Requirement:
Paragraph IWV-3410 requires that stroke time values be compared with the previcus testing to detect slow degradation. This requires the testing personnel go back to each previous test data and calculate the difference in stroke time.
Reason for Waiver:
Maintenance of a running file on previous test stroke times and inclusion of the revised criteria amounts to an undue clerical burden.
Alternate Examination:
Valve stroke times will be compared against the reference values for degradation and the changes in stoke time will be restricted to the 25% and 50% limits specified in IWV - 3410 for increasing the require-ments for stroke testing.
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