ML19257B794

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Revised Tech Specs Page 3/4 4-31,allowing Delay in Testing of Reactor Vessel Internal Vent Valves
ML19257B794
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 01/10/1980
From:
TOLEDO EDISON CO.
To:
Shared Package
ML19257B792 List:
References
575, NUDOCS 8001180351
Download: ML19257B794 (2)


Text

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Docket No . 50- 34 6 License No. NPF-3 Serial No. 575 January 10, 1980 Change to Davis-Besse Nuclear Power Station Unit No. 1 Technical Specifications, Appendix A of Technical Specification 4.4.10.1 concerning reactor vessel internal vent valves. See proposed change attached.

A. Time Required to I=plement -

This change can be ef fective upon NRC issurance, and is required prior to March 27, 1980.

B. Reason for Change (Facility Change Request 79-316)

See attached safety evaluation 1770 325 800118 o JE 55 /

Docket No. 50-346 License No. NPF-3 Serial No. 575 January 10, 1980

- REACTOR C0CLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

b. Each internals vent valve shall be demonstrated OPERABLE at least once per 18 months *during shutdown, by: l
1. Verifying through visual inspection that the valve body and valve disc exhibit no abnormal degradation,
2. Verifying the valve is not stuck in an open position, and
3. Verifying through manual actuation that the valve is fully open when a fcrce .of < 400 lbs. is applied vertical-ly upward.
  • At the end of the first fuel cycle the testing and inspection may be delayed up to May 30, 1980. j DAVIS-BESSE, UNIT 1 3/4 4-31 1770 326 h

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