ML19220A861
| ML19220A861 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/18/1975 |
| From: | Rosa F Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904250044 | |
| Download: ML19220A861 (3) | |
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JUL. 3 375 V. A. 71 core, Assistant Director for LWRs, Group 2, D Eca '",
THRJ: Tnonas A. Ippolito, Chief EldCS Brancn, TR THREE MILE ISLAaD I4bCLEAR STATICii, U;ili 2, REQUEST FOR ADDITI0 rial INFOR!!ATI0a Plant iiare: Three Mile Island Unit 2 Docket Numoer: 50-320 Licensing Stage: Operating License
- tilastone Numer: Request for Additional Inforration Responsible Branch and Project Leader: LWR 2-2, H. Silver Tecanical Review Branch Involved: EISCS Branch Description of Review: Supple: rental Question xequested Completion Date: NA Review Status: Awaiting Infomation Please trans:ait tne attached information requests to the applicant This informatien is required for cocpletion of our review.
This concern is being uniformly applied to all OL's presently under review. We request that the applicant's res?onse De submitted to us in a timely canner ao that our evaluaticn may be incorporated in tne Safety Evaluation Report.
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?a Faust Rosa. Section Leader Electricai, Instrurentation and Control Systems Branch Division of Techiical Review Office of Nuclear Reactor Regulation
Enclosure:
As stated aoove
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JUL 18 F75 V. A. Moore, Assistant Director for LWRs, Group 2, RL.-
THRU: Thcmas A. Ippolito, Chief, EI&CS Branch, TR-J, y THREE MILE ISLAND :UCLEAR STATI0il, UtiIT 2; REQUEST FOR ACD!TICNAL If4FOPJiATIO:4 Plant Name: Three Mile Island Unit 2 Docket Numoer: 50-320 Licensing Stage: Operating License Milestone "umcer: Recuest for Additional Information Responsible Branen anc Project Leader: LWR 2-2, H. Silver Tecnnical Review 3rancn Involved:
EI&CS Branch Description of Review: Supplemental question Requested Comoletion Date:
JA Review Status: Awaiting Infor ation Please transmit the attached information requests to tne apolicant.
This information is recuired for completion of our review.
This concern is being uniformly apolied to all CL's presently under review. We recuest tnat the apolicant's response be submitted to us in a timely manner so that our evaluation may be incorporatec in the Safety Evaluaticn Report.
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i ale-aw Faust Rosa, Section Leace'r Electrical, Instrumentatien and Control Systems 3 ranch Division of Technicai Review Office of Nuclear Reactor Regulation
Enclosure:
As stated acove cc:
S. Hanauer R. Heineman A. Giam::usso V. Stelio K. Kniel H. Silver T. Ippolito F. Ashe W. Mcdonald 71-002
ENCLOSURE
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222.41 Provide jour design criteria and procedures for fire stocs and (None) seals. Your response should address but not be limited to the folicwing:
a) Cable and cable tray penetrations through walls and ficors, and all other types of cable ways or conduits.
b)
Design criteria for each type of fire stop and seal installation.
c)
Interval (physical distance) at which the fire stops are installed in vertical cable trays, and in horincntal cable trays (if any).
d) List of materials used and their characteristics with regard to flammability and fire retardancy and their fire uncerwriters rating.
e) The CA and test procecures used to verify that cenetration fire stops and seals have been properly installed.
f) The ;ualificaticn testing of the fire steps and seals to demonstrate adequacy over tne life of the plant.
g) The administrative precedures and controls that will be follcwed wh9n it becomes necessary to breacn a ccmoleted fire stop or seal to add or remove caoles.
h) The periodic inspections erformed to identify open or deteriorated fire stcps and seals:
In addition evaluate the adecuacy of your design with regard to fire hazards in areas of concentration of elec.rical cabies.
Identify the areas involvec and descrice tne fire detection and protection system anc ecuipment crovided to controi anc extinguish cable fires and to assure that fire in one system will not propagate to enother reduncant system.71-003
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