ML19341A153

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Forwards Response to NUREG-0619, BWR Feedwater Nozzle & Control Rod Drive Return Line Nozzle Cracking. NUREG Not Applicable Due to Plant Design Differences
ML19341A153
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 01/16/1981
From: Hoffman D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0619, RTR-NUREG-619 NUDOCS 8101220234
Download: ML19341A153 (3)


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1 h Consumers Power

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3r n General Offices: 212 West uschigan Avenue. Jackson, Michigan 49201

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January 16, 1981 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Reactors Branch No 5 US Nuclear Regulatory Cc= mission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - RESPONSE TO NUREG-0619 - BWR m uWATER N0ZZLE AND CONTROL R0D DRIV 2 RETURN LINE N0ZZLE CR "GNG NRC letter dated November 13, 1980 requested Consumers Power Company to commit t.o implement the requirements of NUREG-0619 in accordance with its required schedule or to prov$ de justification for deviation from all or some of the requirements, including schedule. On December 15, 1930, the NRC staff was in-for=ed that we had not received NUREG-0619 until December 8,1980; therefore, a request for an extension of the response time was requested and granted by the staff until mid-January, 1981.

Our review of NUREG-0619 indicates that is ia not applicable to Big Rock Point because of design differences from those assu=ed in NUREG-0619. Neither t'.e feedvater line nor the control rod drive return line at Big Rock Point ent r the reactor vessel directly as assumed by INREG-0619 Feedvater enters +a pri=ary system through a separate steam drum prior to entering the reactor vessel. General Electric has indicated that there have been no reported prob-lems with feedvater entering through a steam dru=.

Control rod drive return water currently enters the primary system just prior to the inlet of the clean-up demineralizer regenerative heat exchangers, which is at approximately the same temperature as the control rc ' drive return flow. The present configura-tion for the control rod drive return line was established by a modification in September,1966 which was made to rectify cracking of its previous entrance gnto t system at a thermal tee in the clean-up demineralizer return 1line. g prima N

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Director, Nuclear Reactor Regulation 2

January 16, 1981 Big Rock Point Plant The above information was discussed with Mr D Sne.ider of the NRC on

- one of the plants to January 15, 1981 to ascertain whether Big Rock which NUREG-0619 does not apply. It was determine. v ing this discussion that the NRC was concerned only with nozzles on the subject lines that were directly attached to the reactor vessel; therefore, NUREG-0619 is not con-sidered applicable to Big Rock Point.

David P Hoffman (Signed)

David P Hoffman Nuclear Licensing Administrator CC Director, Region III, USNRC NRC Resident Inspector - Big Rock Point I

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CONSUMERS POWER COMPANY Big Rock Point Plant NUREG-0619 Docket 50-155 License DPR-6 At the request of the Co= mission and pursuant to the Atomic Energy Act of 195h and the Energy Reorganization Act of 197h, as amended, and the Commission's Rules and Regulations thereunder, Consumers Power Company submits our response to NUREG-0619, dated November, 1980 entitled, "BWR F,eedvater No::le and Control Rod Drive Return Line No::le Cracking" transmitted by NRC letter dated November 13, 1980. Consumers Power Company's response is dated January 16, 1981.

CONSUMERS POWER CC'@ANY By R B DeWitt (Signed)

R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 16th day of January 1981.

Linda K Carstens (Signed)

(SEAL)

Linda K Carstens, Hotary Public

' Jackson County, Michigan My commission expires June 10, 1981.

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