ML19309A844
| ML19309A844 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/27/1980 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004010406 | |
| Download: ML19309A844 (2) | |
Text
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PHILAD ELPHI A ELECTRIC COM PANY 2301 M ARKET STREET A
P.O. BOX 8699 PHILADELPHIA. PA.19101 G W "4" enictos t. oat.in,or, b
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.L.CTRic PRODUCTIOss March 27, 1980 Mr. Thomas A.
Ippolito, Chief Operating aeactors Branch #3 Division of Operating Reactors U.S.
Nuclear Regulatory Commission Washington, DC 20555
References:
1)
Letter from S.
L.
Daltroff to T.
A.
Ippolito dated January 30, 1980 2)
Letter from J.
W.
Gallagher to T.
A.
Ippolito dated February 13, 1980
Dear Mr. Ippolito:
This letter is a follow-up to our letters of January 30, 1980, and February 13, 1980, and provides additional information concerning analog transmitters and trip units as addressed in our Amendment request submitted on August 27, 1979.
The license amendment is necessary to allow the removal of 24 safety-related switches in the Reactor Protection System, Residual Heat Removal System, Automatic Depressurization System, Primary Containment Isolation System, and Core Spray System, and removal of two reactor water level sensors used for indication in the control room and replacing them with transmitters and electronic trip units.
In order to assist in the review of this license amendment, additional information concerning the proposed installation is provided below, a)
General Electric Company topical report NEDO-21617-A, " Analog Transmitter / Trip Unit System for Engineered Safeguard Sensor Trip Inputs", was not referenced in our original submittal.
However, the equipment used in our installation is the same as that described in this report.
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It should be noted that additional qualification testing, as summarized by Amerace Corporation Specification ECP, beyond that described in NEDO-21617-A, has been performed on
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A.
Ippolito Page 2 the relays proposed for this installation.
The relays have been tested in the deenergized state in a 212*F environment for 42 days followed by subsequent operation in a 172*F environment.
The relays have been operated in a 95% relative humidity environment and have operated after a total integrated radiation dose of 2x10 R.
b)
Modifications to our facility to meet the accident monitoring instrumentation requirements of NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations" will include the relocation of the power supplies and inverters that interface with the Emergency Core Cooling System equipment proposed by the subject license amendment.
The power supplies and inverters will be moved to the cable spreading room.
This modification will be completed at the same time as, or prior to, completion nf the proposed analog transmitter and trip unit installation.
c)
The equipment is qualified to operate in the environment described in the PBAPS FSAR.
In addition, we are continuing our review of the facility environment with respect to Inspection and Enforcement Bulletins 79-01,79-01A, and 79-OlB.
Preliminary, highly conservative environmental profiles were developed and transmitted in ou.
letter of January 30, 1980.
The profiles were developed using simplified assumptions in order to provide a timely response to IE Bulletin 79-01B regardins equipment qualification data.
This approach resulted in unrealistically high temperatures.
Detailed calculations are in progress that should yield more realistic, yet conservative results.
Although the calculations of the environmental conditions in the reactor building that have been performed to date are of preliminary nature, we believe that the equipment is a
qualified to perform its intended function in the environment expected following an accident.
Our response to IE Bulletin 79-01B will include revised tempe.ature profiles and will show the capabilities of the proposed equipment in the newly analyzed environment.
A copy of our response to Bulletin 79-OlB will be forwarded to you at the time it is submitted to the Office of Inspection and Enforcement.
Should you require additional information in this matter, please contact us.
Very truly yours, j,7 l/
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