ML17311B318: Difference between revisions

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{{#Wiki_filter:RELIEF REQUESTS INDEX 2.3.4, 6.7.E I Hydraulic and Mechanical Snubbers will be tested in accordance with PVNGS Technical Specifications.
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Withdrawn Insulation will not be removed, for visual examinations or welded or mechanical attachments.
Level III Personnel will be recertified by examination every 5 years.Withdrawn Reactor Vessel Support Visual Examination, Class 2 and 3 Systems Pressure'lbst.Withdrawn 9-2 95i2270003 95i220 PDR ADOCK 05000528 9 PDR
 
RELIEF REQUEST NO.3 COMPONENT OR 1TEM CODE PROGRAM TABLE CODE EXAM CATEGORY SUPPORT COMPONENTS INTEGRAL AITACHMENTS 1 2 3 3 1-IWF 2-IWF 3-IWF 3-1 F-A, F-B 4 FN F-A, F-B 4 F-C F-A, F-B A F-C D-A, D-B kD-CODE RE UIREMENT Perform visual examinations (VT-3)of the mechanical or wcldcd attachments to the pressure retaining component on insulated systems.~AS'Ihe visual examinations of the mechanical or welded attachments will be petfotmcd to the extent practical.
The insulation will not be rcmovcd to perform these examinations.
It has been our experience that any loss of support capabiTity or adequate restraint can usually be detected through the examination of uninsulated portions of the support, the accessible portions of the attachments through the insulation gaps, and or the surrounding insulation.
TIO'Ihe mechanical and welded attachments wiH bc visually examined to thc extent pzacticaL'Ihc insulation will be removed from around thc support attachment for further examinations whencvcr the mechanical connections cannot be examined or whencvcr an abnormality is detected.UL 0 LE ON First Ten Year Inspection Interval hRREOO~4 NRC letter dated October 21, 1987, from E A.Licitra, NRC, to EF Van Brunt, Jr.,"Insezvice Inspection Programs Palo Verde, Unit 1, 2, 8h 3" I 1 RELIEF REQUEST NO.6 COMPONENT OR ITEM Reactor Vessel Supports CODE CLASS PROGRAM TABLE I-IWF CODE ITEM F2.10 F220 F230 F2.40 EXAM CATEGORY F-B C UIRE Pezfonu visual examination (VT-3)of the Reactor Vcsscl Supports'Ihc visual examination of thc reactor vessel supports will not be performed.
'Ihe supports aze inaccessible from the refueling cavity seal zing area for either dizect or remote visual examination.
Examination from thc ICI chase below the vessel would requite extensive scaffolding to bc erected in order to get up to thc support pedestal and the exam would still be scvezely limited due to acccssibiTity between thc reactor vessel and the cavity.The perfozmance of this visual would require extzemely large amounts of time, effort, expense, and radiation exposuze (expected to bc 3 man zem per support based on surveys taken in Unit 3 during first zefueling outage).No alternate examination is proposed.SCHEDUL 0 L First Tcn Year Inspection Interval.APPROVAL Pending NRC appzovaL.
ft l RELIEF REQUEST NO.7 COMPONENT OR XIEM PRESSURE REI'AINING COMPONENTS CODE CLASS PROGRAM TABLE 2-7 3-1 CODE ITEM C710 C730 C750 C770 D110 D210 D310 EXAM CAIKGORY C-H D-A D-B DN CODE RE UIREMENT Perform System Functional (class 2)and System Inservice (class 3)pressure test in accordance with IWA-5000, IWC-5000, IWD-5000.G CH-275 CH-283 DW55 FP496 GA-002 GA409 GR~1 IAM9 IA480 NC-135 NC-137 PC072 PC073 RD-259 WC-039 WC042 1-1/2" 311 6" 1 tl I'lt 2't%1(P 1tP 4M 4t%3'0" 1tP 13-M-CHS403 13-M-CHS403 13-M-DWS-002 13-M-FPS-006 13MNA$401 13-M-GAS-001 13-M-GRS401 13-M-IAS-003 13-M-IAS-002 13-M-NCS403 13-M-NCS403 13-M-PCS@01 13-M-PCS-001 13-M-RDS401 13-M-WCS-001 13-M-WC&401 BASIS'Ihis relief is applicable only to portions of piping systems that axe classi6ed ASME due to penetration of containment building liner plate.
4 Relief Recpest Number 7 continued.
For the applicable class 2 systems the piping upstream and downstream of containment isolation is classi6ed non-ASME.A ON The applicable containment piping penetrations aze routinely subjected to 10 CFR 50, Appendix J testing.'ihis testing is more conservative than the VT-2 examination required by the code.Local Lek Rate Testing is signi6cantly more sensitive than a visual examination for lealzage.Reference Code Case N-522 for the ASME Code interpetation.
First Ten Year Inspection Interval.+i~PROV L Pending NRC appzovaL
 
RELIC REQUEST NO.8 COMPONENT OR HEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CA%GORY PRESSURE REI'AINING COMPONENTS 3-1 D2.10 D-B 1 I}}

Revision as of 17:51, 24 October 2019

Revised Pages to ISI Program Summary Manual
ML17311B318
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 12/20/1995
From:
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17311B317 List:
References
PROC-951220, NUDOCS 9512270003
Download: ML17311B318 (12)
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