ML20084A381
| ML20084A381 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/01/1973 |
| From: | Cobean W CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084A384 | List: |
| References | |
| AO-3-2-14, NUDOCS 8304050174 | |
| Download: ML20084A381 (2) | |
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November 1, 1973 Re:
Indian Point Unit No. 2 Facility Operating License DPR-26 A.O.-3-2-14
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Dear Mr. O' Leary:
A The following report is provided pursuant to the requirements of Section 6.12.2 (a) of the Technical Specifications of Facility Operating License DPR-26.
On October 17, 1973, prior to planned maintenance en the three pressurizer safety valves, to correct mir;or seat leakage which had been experienc'ed, the lift pressures of those valves were checked.
Two of the valves were found to be set approximately 1.0% higher than the limit set forth in section 3.1.A.3.C of the Technical Specifications.
The third valve was approximately 0.6% above this limit.
At the time of this observation, the reactor was in a shutdown condition.
The three Pressurizer safety valves were disassembled for in-spection and reworking of the seating surfaces.
Upon comple-tion of this maintenance, they were reassembled and reset to the value specified in the Technical Specifications.
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The safety valves on the Pressurizer are designed to prevent a rise in system pressure above 10% of the normal operating value and to relieve the reactor heat surge should a total., loss of load occur with the plant at full power.
This typerof incident was examined and rsported upon in the Final Safety Analysis Re-port under the assumptions that there is no direct control rod insertion, or pressurizer spray, and main steam safety valves and steam bypass valves to condenser do not operate.
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found that the pressurizer safety valve setpoint would not be 1
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U Mr. John F. O' Leary, November 1, 1973 Indian Point Unit No. 2 Facility Operating License DPR-26 A.O.-3-2-14 reached and that the reactor coolant system is protected against excessive pressurization due to heat surge without safety valve actuation.
For these reasons, the safety implications of setpoint variances on the Pressurizer safety valves are considered to be negligable, Very truly yours, gg b JSA ',
Warren R. Cobean, Jr.
Manager - Nuclear Power Generation Department cc/
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