ML20083N660
| ML20083N660 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/13/1984 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM 5211-84-2089, NUDOCS 8404190254 | |
| Download: ML20083N660 (3) | |
Text
GPU Nuclear Corporation NggIg{
Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
April 13, 1984 5211-84-2089 Office of Nuclear Reactor Regulations Attn: John F. Stolz, 01ief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Cmmission Washington, D.C. 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station Unit I (TMI-1)
Operating License No. DPR-50 Dockct No. 50-289 Cbntainment Pressure and Hydrogen bbnitors (II.F.1)
Licensee letter 5211-83-323 dated Novmber 28, 1983, forwarded design information on the subject monitors pursuant to NUREG 0737 II.F.1.
Diclosed are corrections to that letter, as indicated by margin bars, regarding proposed surveillance requirenents.
Sincerely,
- 1. D.
- ukill, Director, TMI-l HIII: RAS:mle Attachments cc:
Dr. T. E. Murley J. Van Vliet k
S404190254 840413 pDR ADOCK 05000289
\\
p PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
4-3 DESIGN AfD OUALIFICATION OF THE CONTAI!NEN~ HYC; OGEN MONITOR (C,M)
(1)
Seismic / Environmental Oualification - The sa ple lines are supacr:ed seismically as is all otner equipment in a::creance with Reg. Guice 1.100 and IEEE 344-1975.
The environment c.:alification of the Containment Hydrogen Monitor has been reviewed against the DDR Guidelines.
The results of this evaluation nave been included in licensee letter 5211-83-076, May 16, 1983.
(2)
Sinole Failum - The Containment Hydrogen Monitor has redundant safety grade channels and is powered by a class lE power source and therefore, single failure proof.
The alarms and computer inputs are not safety related.
(3)
Power Sources - The power supplies for the Hydrogen Monitor are provided from redundant 1E power supplies (vital bus).
(4)
Availability - The CHM is on-line continuously during normal e
operations. Samples are drawn continuously during accident and post accident conditions.
Operability requirements have been addressed in a Tech Spec. Change Request No. 114.
l, (5) 0A Requirements - The CHM with the exception of the alarms and computer inputs are nuclear safety related and the applicable sections of the GPU Nuclear OQA Plan are invoked.
(6)
CoRtinuous Operation - See (4)
(7)
Recordino Instrumentation - A recorder for each channel is located in the Control Room and will provide continuous recording.
(8)
Identification - The Containment Hydrogen Monitoring instninentation has been " human factored" and the recorders are located on the left front panel in the Control Room.
(9)
Isolation Devices - The CHM System is self contained and does not interface with other systems.
Therefore no isolation devices are provided..
(10) Testing - Surveillance requirements are addressed in Technical Specifications Change 11equest No.114.
(11) Surveillance - See (10)
(12) Removal From Service - Testing shall be perforined in accordance with the applicable portions of Reg. Guide 1.118 for testing of instrument channels.
.rennt
f ATTACHv.EN' '.
DESIGN AND OUALIFICATION OF THE C%'TWENT EESSU:E CCTC:.
(1)
Seismi:/ Environmental Qualification - Tne seismic cualifica:icn cf :ne pressure transmitter an: signal concitic.ing ecui: ment is in act:::ance with RC 1.103 and IEEE-344 1975.
Ea:n :.annel re:orcer and asse:ia:e:
nower supply has a steel protective shield surrouncing them to serve as a seismic barrier from other non seismi: qualified components.
Environmental qualification of the containment pressure monitor was included in licensee letter 5211-83-076, May 16, 1963.
(2)
Sincle Failure - The containment pressure monitor is composed of recuncant safety grade, Class 1E equipment channels and power sources which have both narrow and wide range recorder indication and are therefore single failure proof.
I (3)
Power Sources - The containment pressure monitor is energized by e
separate power supplies from Class 1E uninterruptible power.
The signal conditioning cabinets provice additional isolation of the non lE ccrnputer signal from the lE recorder signal in each channel.
(4)
Availability - The containment pressure indicator is in constant
\\
l operation curing all plant operating modes, infrequent operation, accident conditions and post accident conditions. Operability requirements have been adcressed in Technical Specification Change
]
3equestNo.114.
(5)
DA Reovirements - The portion of the containment pressure indication external to tne Control Room panel has been designated nuclear safety related under the applicable section of the G UN 00A Plan.
(6)
Continuous Indicaticn - See response to Item (4).
Any component malfunction or loss of power leaves inta : a redundant channel fcr indication.
(7)
Recordino Instrumentation - The 0-10 VDC outcut signal of each channel is routea to 1 of 2 Eailey Controls 2 pen rec rders in the Control Room with strip chart' output for trending, g
(6)-
Disclay Instrumentation - The recorders are mounted on the front of the PmF vertical panel, be31nd the contrcl console.
Inis will be a normal.
CR0workarea{orpost-accidentconditions.
y (9)
Isolation - See (3)
(10) Testing - Surveillance requirements are addressed in Technical spec-ification Change Request No.114.