ML17252A850
| ML17252A850 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/05/1974 |
| From: | Cobean W R Con Edison |
| To: | O'Leary J F US Atomic Energy Commission (AEC) |
| References | |
| Download: ML17252A850 (2) | |
Text
, . . , Consolidated Edison York, Inc.
- l'§tli1. 4 Irving Place, New York, NY 10003 . DOCKETED USAEC 111974 po-REGULATORY ;_--; f.4All
'!
DOCKET CLERK * ..
.. --< *-,,// fo -(. / Mr. John F. o
- l\
- irector Directorate of Licensing Re: u. S. Atomic Energy Commission Off ice of Regulation Washington, D *. c. 20545
Dear Mr. O'Leary,
5 February 1974 Indian Point Unit.No. 2 Facility Operating License DPR-26 A. 0. -4':'2-:-5 50-247 The following report is provided pursuant to the requirements of Section 6.12.2(a) of the Technical Specifications to Facility Operating License No. DPR-26. On January 23; 1974, at approximately 3:38 P.M. a coolant system pressure transient was experienced in the course of placing a reactor coolant pump in. service. The pressure was above .the 500 psig Technical Specification limit set borth in Figure 3.1-1 for reactor coolant temperatures less than 220 F. At the time of the occurrence the reactor was shutdown with all full length control rods fully inserted and-a reactor coolant tem temperature of about 1900F. In order to heat the reactor coolant system to 547oF, preparatory to returning the plant to service following completion of repairs associated with the November 13, 1973 feedwater line break incident, the first reactor coolant pump was placed in service following scribed procedures.
These procedures entailed the.establishment 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 actor coolant system pressure increased to above 500 psig, as dicated by readings of 525 and 510 psig on two drag pressure gages. The pressure was immediately brought down by operator action to the desired 425 psig. The pressure transient experienced was much less than those viously reported following*
similar reactor coolant pump starts. The effectiveness of a gas blanket in eliminating or minimizing pressure surges when starting the first PWilP has thus been This-transient of January 23, 1974 was due to an ficient amount of nitrogen having been added to the pressurizer and ... '}
- --.. John F. O'Leary ' Re:
- 5 February 1974 Indiari Point No. 2 Facility Operating License DPR-26 A.0.-4-2-5 we have changed our procedure to insure that a proper amount inserted in the future. There are considered to be no safety implications to this rence. There was no damage incurred to any system or component nor was there any reason to expect any as a result of a pressure transient of this magnitude.
The pressure limitation of 500 psig at coolant temperatures of less than 2200F is imposed only as a means of insuring additional conservatism in the application of fracture toughness concepts and includes the effects of fast tron exposure which would occur over a two year period of tion. In light of the minimal amount that the limit was exceeded, and the fact that the reactor vessel* has been exposed to only a small fraction of the neutron irradiation assumed, it is ered that the safety of the facility was not compromised by this occurrence.
cc: Mr. James-P. O'Reilly Very truly yours, Warren R. Cobean, Jr.GJ Manager -Nuclear Power Generation