ML20083R729
| ML20083R729 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/05/1974 |
| From: | Cobean W CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20083R732 | List: |
| References | |
| AO-4-2-5, NUDOCS 8304040619 | |
| Download: ML20083R729 (2) | |
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5 February 1974 Re Indian Point Unit.No. 2 Facility Operating License DPR-26 9
A.O.-4-2-5 50-247 f
311\\prfL-Mr. John F. O' Leary, Director O6 Directorate of Licensing P
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Dear Mr. O' Leary,
'N_p' 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 slight reactor coolant system pressure transient was experienced in the course of placing a reactor coolant punp in service.
The pressure trans-ientwasabovethe500psigTechnicalSpecificationlimitsetforth 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 sys-0 tem temperature of about 190 p, 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 incident, the first reactor coolant pump was placed in service following pre-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 re-actor coolant system pressure increased to above 500 psig, as in-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 pre-vlously reported following similar reactor coolant pump starts.
The effectiveness of a gas blanket in eliminating or minimizing pressure surges when starting the first pump has thus been demon-strated.
This transient of January 23, 1974 was due to an insuf-ficient amount of nitrogen having b en,added to the pressurizer an pura=%
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a Mr. John F. O' Leary 5 February 1974 Re:
Indian Point Unit No. 2 s
Facility Operating License DPR-26 A.C.-4-2-5 we have changed our procedure to insure that a proper amount is inserted in the future.
There are considered to be no safety implications to this occur-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 0
at coolant temperatures of less than 220 F is imposed only as a means of insuring additional conservatism in the application of fracture toughness concepts and includes the effects of fast neu-tron exposure which would occur over a two year period of opera-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 consid-ered that the safety of the facility was not compromised by this occurrence.
Very truly yours, 00tCu 4CAs Warren R. Cobean, Jr.l Manager - Nuclear Power Generation cc:
Mr. James P. O'Reilly
._