ML20030D341
| ML20030D341 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/02/1980 |
| From: | Rood H NRC |
| To: | Pawlicki S NRC |
| Shared Package | |
| ML20030D342 | List: |
| References | |
| NUDOCS 8109010205 | |
| Download: ML20030D341 (1) | |
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UNITED STATES s
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- ..tiic se ce Eec:ric anc Gas Compcny 80 Fa x P: ace Newark, N.i 07101 Pr.cr.e 201430-7000 January 30, 1979 Director cf Nuclear Re' actor Regulation U.
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Gentlemen:
EOPE CREEK GENERATING STATION DOCKET NOS. 50-354 AND 50-355 CODES AND STANDARDS FOR REACTOR' COOLANT. PRESSURE BOUNDARY EQUIPMENT Pursuant to Section 50.55a (a) (2) (i) and (ii) of 10 CFR Part 50, Public Service Electric and Gas Company hereby requests authori-
=ation to use certain components in its Ecpe Creek Generating Station, Units 1 and 2 which were designed to codes which differ' from those specified in Subsections (c) through (f) of 10 CFR 50.55a.
The specific components for which authorization is requested are set forth in the table attached hereto.
On February 27, 1970, Public Service Electric and Gas Company filed its construction permit applicatien for Hope Creek, Units 1 and 2.
Engineering and Construction schedules at that time were based on expected construction permit issuance in 1971.
Initial engineering design and procurement activity was based.
on this forecast.
The design, fabrication, and testing of ccmponents purchased in this peraod were based on recognized codes and standaids in effect at the time.
Since the construc-tien permits were not issued until November 1974, some of the codes used differ from those now listed in 10 CFR 50.55a Sub-sections (c) through (f).
We believe that the costs associated with replacing the components in the table solely for the purpose of changing the design codes would represent a severe hardship without a compensating increase in quality or safety.
Further-more the codes to which the subject equipment and ccmponents were designed assure the achievement of an acceptable level of quality and safety.
T)ttPG OF 3:ni t t.Tnny V)P!'ET T'! C DAD a
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Director of Nuclear Reactor Regulation 2-1/30/79 In view of the above, respectfully recuests an authcrization frcm the Cc=.ission inPublic Se accordance with Section 50. 55a (a) (2) (i) and (ii) of 10 CFR Part in the attachment to this letter.50 to use the codes referenced for the compon
. Very truly yours,
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L. Mittl General Manager' - Licensing and Environment Engineering and Construction Department y
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HOPE CPIER. GENERATING STATION UNITS NO. 1& 2 DOCKET NCS. 50-3f4 AND 50-355 PIACTOR COOLANT PRESSUPI BOUNDARY EQUIPMENT CODE STATUS Purchase Code Ecuipment Ecuipment Order Date Was Built to:
Reactor Pressure May.7, 1970 ASME III, 1968 Edition vessel-Unit One with Winter 1969 Addenda Reactor Pressure April 30, 1971 ASME III, 1968 Edition vessel-Unit Two with Sur=er 1970 Addend.1 Centrol Rod Drive January 5, 1971 ASME III, 1968 Edition Housings with Surser 1970 Eddenda Control Rod Drive
, August 18, 1971 ASME III, 1968 Edition with Winter 1970 Addendum Power Range Monitor January 5, 1971 ASME III, 1968 Edition Incore Housing with Su =er 1970 Addenda Jet Pump Instrumen-January 5, 1971 ASME III, 1968 Edition tation Penetration with Summer 1970 Addenda Main Steamline safety January 28, 1971 Nuclear Pump and Valve relief valves Code, 1968 Edition with l e,10
- n. a..cenca Main Steamline isola-October 8, 1969 Nuclear Pump and valve tion valves Cede, 1968 Edition Main Steamline pipe January 27, 1972 ASME III, 1971 Edition with Stamer 1.971 Addenda 2,
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elemenus with Surrer 1972 Addenda Reactor recirculation May 7, 1971 Nuclear Pump and Valve system pump Ccde, 1968 Edition with 19 0 a.c..cenca
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Reactor recirculation February 23, 1971 Nuclear Pu.p and Valve system shut off valves Code, 1968 Editien with 1970 Addenda Reactor recirculation December 23, 1971 ASME III, 1971 Edition system, by-pass valve Reactor recirculation Febr_ary 25, 1971 ASME III, 1968 Edition system, pipe with Sur=er
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