ML17252A854
| ML17252A854 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Indian Point  |
| Issue date: | 01/28/1974 |
| From: | Cobean W Consolidated Edison Co of New York |
| To: | O'Reilly J US Atomic Energy Commission (AEC) |
| References | |
| Download: ML17252A854 (2) | |
Text
.......
£.,rj,..~-::-**
- consolidated Edison Company of New York, Inc.
4 Irving Place, New York, NY *10003 1'!'~1* c -*
n;S *y.
January 28, 1974 Re:
Indian Point Unit No. _2 AEC Docket No. 50-247 Operating License DPR_-26 A.0.-4-2-5 Mr. James P. O'Reilly, Director Regulatory Operations, Region I U. s. Atomic Energy Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. O'Reilly,
In accordance with the requirements of Section 6.12~2a of the Technical Specifications of Facility Operating License No. DPR-26, the following report is submitted.
On January 23, 1974 at approximately 1538 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.85209e-4 months <br /> a slight reactor coolant system pressure transient abo've the Technical Specif ica-tions limit was experienced in.the course of placing a reactor coolant pump in service.
At the time of the occurrence, the re-actor was shutdown with all full length control rods fully ifi-serted and a* reactor coolant system temperature of about 190 F.
0 In order to heat the reactor coolant system to 547 F preparatory to returning the plant to service following completion of repairs associated with the November 13, 1973 feedwater line break inci-dent, the first reactor coolant pump was placed in service fol-lowing pre~cribed procedures.
These procedures entailed the es-tablishment of a nitrogen blanket in the pressurizer to act as a surge.volume for the start of the first pump.
Upon starting the pump, the reactor coolant system pressure increased to 525 psig. and 510 psig. as indicated on two installed drag pressure gages.
The pressur~ was immediately brought down to the desired 425 psig *. by operator action.
Technical Specification 3.1.B.l.a states that for indicated temperatures at or below 2200F the max-imum indicated pressure shall not exceed 500 psig.
There was no damage incurred to any system or component as a re-sult of a pressure transient of *this magnitude nor was there any reason to expect any.
The transient experienced was much less
- }o.:.*
.. ~.. \\.
Mr. James P. O'Reilly 2 -
Janu,ary 28, 1974 Re:
Indian Point Unit No. 2 AEC Docket No. 50-247 Operating License DPR-26 A.0.-4-2-5 than those previously reported and demonstrates the effective-ness of a gas blanket in eliminating or minimizing pressure surges when starting the first pump.. We believe this particu-lar transient was due to an insufficient volume of nitrogen in the pressurizer and we plan to modify our procedure to insure the proper arnount.
Mr. Anthony Fasano of your office was informed of this occur-rence by Mr. John Makepeace on January 24, 1974 *
"\\
cc:
Mr. John F. O'Leary
. Very truly yours, r.
w~~~Q,~b1 Warren *R. Cobean, Jr. ~/ 'Manager Nuclear Power Generation
-. -__ J_