ML19341C212

Proposed Tech Spec Table 4.6-1,Item 1.6,correcting Typographical Error in Insevice Insp of Pressure Containing Welds in Vessel Penetrations.Safety Evaluation Encl

ML19341C212
Person / Time
Site:	Arkansas Nuclear, FitzPatrick
Issue date:	02/20/1981
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML19341C205	List: ML19341C204 ML19341C207 ML19341C212
References
NUDOCS 8103020391
Download: ML19341C212 (5)

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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATIONS CHANGES RELATED TO INSERVICE INSPECTION OF PRESSURE CONTAINING WELDS IN VESSEL PENETRATIONS POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 FEBRUARY 20, 1981 8103020dl ..

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FitzPat r ick Prognsed Progr.im

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,j,, , h ibility y C nts and Examination Methods

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• visual examination will be gerformed using optical l l '4 e % e bottom head insulation. equipment capable of providing a complete viewinq of the O.D. of the housing external to the vessel

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j . for signs of leakage.

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[%,henctor preeeurs vessel safe-end welds are made Demote or local visual examination will be lerformed. ,

,' accessible by removing thermal insulation and De extent to which surface examination is performed is escrificial shield plugs. determined by radiological considerations. Manual ultrasonic examination M- will be performed, where possible, until automated equipment is available g but the extent of the examination will be determined by radiological considerations.  ;

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?-Gera ende in branch welds and dissimilar metals welda Remote or local visual examination will be performed. n e extent to which surface made accessible by removing piping thermal examination is performed is determined by radiological considerations. Although d{(

T ulation. radiation dosage is high, manual "ltrasonic examination will be perforsu o, where .- 5 }

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possible, until aut.omated equipment becomes available, but the extent of the 4 examination will be determined by radiological considerations. g

y , Exception is taken to voltanetric examination of welds which require drainage of f.

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j, the reactor vessel.

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-s. 4 GRetapp!! cable . Not applicable. Dere are no no2Eles to safe-end welds on pu=.ps. . L hN N fa errfs in valves are made accessible by Remote or local visual examination will be performed. E l

,. samoving thermal insulation. Although radiation dosage is high, manual ult re-mic examination will be performed, 1

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r d where possible, until autosutic equigaent tecomus available. ,% '[

' Exception is taken to vt6wnetric examination of welds which require drainage of ..a f,8 reactor vessel.

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As Per ASML Cs=le Seetion X!-15-200 Examination Extent of Item Category Estent of Eman1 nation. 4 Ca smg u ine n t a and Parts Ensman.stion Exam a nat ion ,Intervsla No. Table 1S-151 to be Lxamaned Me t hi wi

% in 10 Vaats 10 Veers S Veers _

F-2 1.6 Pressure-runtaining welds an Welds in vessel at suntrol a rmt dr i ve Visual JS 25 O l l vessel genet r at toria genet r at ions and in-core suin s t or e housing ( St uit t ute- t ar hous i ng and l vessel) r 1.7 Pressure-contaaning dissimillar P r i ma ry reor r i e s to safe-end welds: Vinual, surfa<e, 100 100 33 metal welds ke<irculation anlet and volumetric Re< t r eul a t t on ou t le t

( l e is u r e- norzles Come spaay l 4.1 Pressure-containing dissimilas Pipany pics. ore tu runda r y nafe ends in Vanual, 100 100 11 nutal welds branch piping welds surfare,and ,b. t vo l ume t r li- '

f Paping pressure laiundary welds twtween dissimalas metals aL, 5.3 Pressure-containing diswamalar Pump presnure immundary nearzleb-t - ..s f e V a n ua l and 100 O 30 metal weids end welds

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o ATTACHMENT II l

j SAFETY EVALUATION j

-RELATED TO INSERVICE INSPECTION OF PRESSURE CONTAINING WELDS IN~ VESSEL PENETRATIONS L

i-POWER AUTHORITY OF THE -STATE OF NEW YORK JAMES A'. FITZPATRICK NUCLEAR POWER PLANT-

. DOCKET NO. 50-333-FEBRUARY.20, 1981 s

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l Section I - Description of Modification The modification corrects a simple typographical error in Item 1.6 of Table 4.6-1, " Comparison of the James A. FitzPatrick Nuclear Power Plant Inservice Inspection Program to ASME Inservice In-spection Code Requirements". The subsolumn "5 years" under the column" Extent of Examination, % Intervals" has the value 8, which is incorrect. The correct entry is zero, as specified by Section XI of this 1970 ASME Code.

Section II - Purpose of the Modification In accordance with Section XI of the 197 0 edition of the ASME code, the visual exam required by Category E-2 shall be done at the time of the system hydrostatic test required by Section IS-  ;

520. Section IS-520 requires the hydrostatic test to be per-formed'at or near the end of the inspection interval, which is 10 years. The typographical error in the present Technical Specifi-cations would require a major hydrostatic test every 5 years which would subject the plant to needlessly high pressure. The purpose of the modification is to obviate some needless hydrostatic tests.  !

Section III - Impact of the Change These modifications will not alter the conclusions reached in the FSAR and SER accident analysit Section IV - Implementation of the -Modification The modification as proposed will not impact the ALARA or Fire Protection Program at JAF.

Section V - Conclusion The incorporation of these modifications: a) will not increase the probability nor the consequences of an accident or malfunction of

-equipment important to safety as previously evaluated in the Safety ~ ~

Analysis Report; b)' will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety.as defined in the basis for any Technical Specification, and d) .does not constitute an unreviewed safety question.

Section VI - References-(a) JAP FSAR (b) JAF SER