ML20033C207

Requests Evaluation Status & Resolution Re Encl Licensee 791030 Request for Code Exemption on Reactor Pressure Vessel & Other Components Not Mfg Per ASME III Requirements

ML20033C207
Person / Time
Site:	Hope Creek
Issue date:	08/17/1981
From:	Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Blackwood E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20030D342	List: ML20030D341 ML20033C197 ML20033C207
References
NUDOCS 8112020869
Download: ML20033C207 (1)

Text

l segg UNITED STATES NUCLEAR REGULATORY COMMISSION n

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' REGION I 631 PARK AVENUE o

KING OF PRUSSIA, PENNSYLVANIA 19406 AUG 171981 Docket Nos. 50-354 i

50-355 MEMORANDIN FOR:

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wood, Chief, Reactor Projects Section, DRRRI, IE

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SUBJECT:

REACTOR PRESSURE YESSEL AND OTHER COMPONENTS NOT MANUFACTURED.

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• -' : e Sh..The ' attached letter (PSE&G tb NRR^ dated" January W.

30, 1979) details differences between required codes listed in 10 CFR 50.55a subsections (c) through and the codes used to annufacturithiHope" Creek 1.and 2 reactor pressur(ef)

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[E vessels as well as other reactor system components.

Based on the expected issuance of a construction permit in 1971, the licensee's engineering t'esign and component fabrication were accomplished using codes in effect at thr.t time. The construction pennit was issued November 4,1974.

h Region I rSquests that evaluation status and resolution of the licensee's request

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8112O20869 811104 f

I PDR ADOCK 05000354 l

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January.30, 1979 PSE&G/

HOPE CREEK'-

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Director of Nuclear Reactor Regulation SITE OAD' -

U. S. Nuclear Regulatory Commission t AG 1 Washington, D. C.

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DEC 2 1980..

Gentlemen:

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HOPE CREEK GENERATING STATION a yei E O als a

DOCKET NOS. 50 -354 AND 50-355

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O con To H. o. cAn CODES AND STANDARDS FOR REACTOR --

.G CODIANT PRESSURS BOUNDARY EQUIPMENT;Y

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Pursuant to ' Sectio'n.50.55a(a) (2). '(I) and (15.) of 10.CFR Yart 50, Public Service Electric'and Gas Company-hereby"re'uests'authori-q zation to use cer'tain compon~ents.in, its Hope Creek Cenerating.

Station, Units 1 and 2 which were designed to codes which differ from those specified in Subsections (c) through (f) of 10 CFM The, specific components for which authorization is -

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requestod are set forth in the table attached hereto.

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. ;.1-OnFebruary27h.1970,:publicServiceElectricandGas[CohaSy filed its construction. Permit application. for Hope Creek,. Units Enginoering.and Construction schedules at'that' time 1 and 2.

were based on' crpected construction permit issuanc.e in 1971.

Initial engineering design and procurement activity 'was based on this forecast.

The design, fabric'ation, and testing of components purchased in this period weie based on recognized Since the construc-codes and standards in effect at the' time.

tion permits were not issued until November 1974, some of tha'-

codes used differ from those now listed in 10 CFR SD.55a.Sub-sections (c) through -(f).

We believe that the costa associated

' with replacing the components 'in the table solely for the purpose of changing the design codes would represent a sovere hardship

'Further-witihout a compensating increase"ih quality or safety.

more the codes to which :th, subject equipment and components were designed ashure the achievement of an acceptablo level of quality and safety.

DaPE OF 70 Sh00

mtor of Nuclear 1/30/~19. actor Regulation

. In view of the above, Public Service Electric and Gas Company respectfully requests an authori=ation from the Commission in accordance with Section 50.55a(a) (2) (i) and (ii) of 10 CFR Part 50 to use the codes referenced for the components listed

.in'the. attachment to.th.i,s letter. -

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Very,truly yours, l

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l R. L. Mittl-f General Manager - Licensing.and Environmen't' C.: 3:,

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HOPE CREEK GENERATING STATION UNITS NO. 1& 2 DOCKET NOS: 50-354 AND 50-355 REACTOR COOLANT PRESSURE BOUNDARY EQUIPMENT CODE STATUS Purchase Code Equipment Order Date Was Built to:

Ecuipment

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'ASME III, 1968 Edition May 7, 1970

/actorPressure

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with Winter 1 9 Addenda

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essel-Unit _ One n

j April 30, 1971 ASME III, 1948 ition Raactor Pressure with Summer Addenda.

bessel-Unit Two

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l*> 70 January 5, 1971 ASME III, 1968 Edition 5ontrel Rod Drive housiags with Summer 1970 Addenda hontrolRodDrive

' August 18, 1971 ASME III, 1968 Edition with Winter 1970 Addendum g

hower Range Monitor January 5, 1971 ASME III,- 1968 Edition with Summer 1970 Addenda (Incore Housing t

Je't Pump Instrumen-January 5, 1971 ASME III, 1968 Edition with Summer 1970 Addenda tation Penetration Main Steamline safety January 28,.1971~

Nuclear Pump and Valve Code, 1968 Edition with l

r.elief va. ves 1970 Addenda Main Steamline isola-Oc'tober 8, 1969 Nuclear Pump and Va].ve tion' valves Code, 196s Edition Main Steamline pipe January 27, 1972 ASME III, 1971 Edition with Summer 1971 Addenda iMain Steamline flow February 5, 1973 ASME III, 1971 Edition with Summer.1972 Addenda Ielements Reactor recirculation May 7, 1971 Nuclear Pump and Valve

' Code, 1968 Edition with system pump 1970 Addenda l Reactor recirculation February 23, 1971 Nuclear Pump and Valve Code, 1968 Edition with system shut off valves 1970 Addenda l

Reactor recirculation December 23, 1971 ASME III, 1971 Edition system, by-pass valve l Reactor recirculation February 25, 1971 ASME III, 1968 Edition with Summer 1970 Addenda system, pi e P

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