ML19242B303
| ML19242B303 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 07/16/1979 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7908070844 | |
| Download: ML19242B303 (2) | |
Text
fg BALTIM ORE GAS AN D ELECTRIC CO M PANY GAS AN D ELECTRIC B UI LDI NG B ALTI M O R E, M A RY LA N D 21203 ARTHUR E. : U N DVALL, d R.
July 16, 1979 V+C C P*E Si ? t *e f s-Mr. Boyce H. Grier, Director Office of Inspection and Enforcement - Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19h06
Subject:
Calvert Cliffs Nuclear Power Plant Units Nos. 1 & 2, Dockets Nos. 50-317 & 50-318 IE Bulletin 70-13
Reference:
NRC letter dated 6/25/79 from :. H. Grier to A. E. Lundvall, Jr.
Dear Mr. '<rier :
The referenced letter forwarded IE Bulletin 79-13, which requested that we provide (1) a Ochedule for conducting an inspection of the feedvater nozzles and piping for the Ca2 vert Cliffs steam generators; (2) an assessment of the adequacy of ot feedvater l'ne break procedures; and (3) a description of the method and sen ntivity of detecting feedvater leaks.
During the just-concluded refueling outage for Unit No. 1, we conducted radiographic inspections of the main feedvater nozzle-to-pipe, pipe-to-elbow, and elbov-to-pipe vc19 of both steam generators. No cracks were found to be present in any of those velds. During the course of the inspection, two possible indications were found which, upon further inspec-tion vere found to be (1) a 2"-3" lack of fusion and (2) a 2"-3" machining groove.
Both were re=oved by g-inding (.040" for the former and.010" for the latter).
No refilling was required. We vill submit a fofmal report on this inspection as required by paragraph 6 of the Ealletin.
We have reviewed the apprrpriate plant emergency procedure which would be used for a feedvater line break in the piping adjacent to the steam generators. This procedure is entitled Steam Line Rupture, E0P h.
We have found the procedure to be adequa* e for this type of emergency.
Leakage from the feedvater system would be detected inside containment sump level and increased drainin,- frequency. This method and censitivity and other possible leak detection icethods such as containnent temterature, pressure and humidity changes are disnussed in our response to Question h.hh of the Supplement to the Calvert Clift s Final S*.fety Analysis Report.
The Bulletin specifies that the raciocraphic inspection of the feedvater no: le-area piping velds h comolete within 90 days and that a volumetric exam of all of the feedv ster piping inside containment be conducted at the subsequent refueling outage or other outage of sufficient duration.
505 N 0 s ca m fyr
Page 2 r
e Our plans are to conduct the required volumetric examination of the main feedvater piping on Unit No. 1 at the next refueling outage (Spring 1980).
Inasmuch as Unit No. 2 is scheduled for a refueling outage beginning on or about October 14, 1979, we request that the specified date for the required radiographic inspection of the main feedvater nozzle velds be extended from September 25, 1979 into the scheduled refueling outage. At that time ve would conduct both the radiographic inspection of the nozzle velds and the volumetric inspection of the main feedvater piping velds inside contain=ent.
In support of this request for an extension we point out that an ultrasonic inspection was conducted on the main feedvater nozzle-to-pipe velds on both Unit No. 2 steam generators in October 1973, and no indications were found. We vould appreciate your informing us if this proposed schedule is unacceptrble.
Very truly yo l.
i e&n fa Wr f I
cc:
J. A. Biddison, Esquire G. F. Trowbridge, Esquire Mr. E. L. Conner, Jr. - NRC Mr. J. W. Brothers - Bechtel Mr. P. W. Kruse - CE
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