ML19220B277

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Forwards Safety Evaluation of FSAR Through Amend 33. Unresolved Areas Include Protection Against Dynamic Effects Associated W/Postulated Rupture of Piping
ML19220B277
Person / Time
Site: Crane Constellation icon.png
Issue date: 11/05/1975
From: Tedesco R
Office of Nuclear Reactor Regulation
To: Moore V
Office of Nuclear Reactor Regulation
References
NUDOCS 7904250577
Download: ML19220B277 (2)


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Docket File NRR Rdng N0/ 5 top:

CS Rang APCSB Rdng Decist No. 50-320 Voss A. Moore, Assistant Director for Light Water Reactors, Group 2, RL SAFETY EVALUATICN REPCRT, AUXILIARY AND PCh7.R CQiVEFSICN SYSTEFJ BRANCH Plant Nue: Three Mile Iaind Nuclear Station, Unit 2 Licensing Stage: OL Do&t Hu:aber: 50-320 Milestone Nunber: 24-02 Responsible Branch: La 2-2 Project Leader:

H. Silver Requested Cmpletion Date: October 31, 1975 The enclosed Safety Evaluation Report covers areas of the FSAR for which the Auv4142ry and Power Conversion Systma Branch has primary responsibility.

The review includes all amendmento through A:neccsant 33.

The following araas have not been resolved:

(1) Section 3F, Protection Against Dynamic Effects Associated With the Postulated Rupture of Piping The applicant has not submitted the results of a moderate energy line failure analysis in conformance with the impimentation section contained in Branch Technical Position APCSB 3-1, "Protaction Againac Piping Failures in Fluid System Cutside Cone =4nm=nt."

We will require the applicant to provide a satisfactory moderate energy line failure analysis.

(2) Section 9.4.3, Puel Building HVAC System The applicent has not designed the isolation depers of the fuel building supply air system to sai mic Category I requirements. We v111 requise that these dampers, necessary to prevent the release of radioactivity in the event of a fuel hind 14nE accident to be designed to seim ic Category I requirements in accordance with Regulatory Guides 1.13.

79042505TJ 74-191 p

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NOV 5 1975 Voss A. Moore (3) Section 9.4.9, Centrol Building Area EVAC Svstem The applicant has not designed the control building area HVAC system to seismic Category I requirements. During a loss of offsite power caused by a seismic event, there vill be no cooling in the control building area. One motor driven emergency feedvater pump and one Control Bniiding booster pu=p are required for a duration of eight hours for safe shutdown of the unit. These pumps can withstand temperature envircr:ments up to 140*F.

The applicant states that without cooling in the Control Building Area and with the operation of the above two pumps, the temperature of the area vill rise to a steady state value of 139'? in five hours. This value of 139*7 does not demonstrate adequate safaey nargin for justifying a non-eeismic Control Building WAC system, and, therefore, we do not find the system acceptable.

Robert L. Tedesco, Assistant Director for Conen%-nt Safety Division of Technical Review

Enclosure:

As Sutted cc:

S. h uuer, TA W. Mcdonald, MIFC R. Boyd, EL R. n= 4 ~= =, TR K. Inial, RL V. Benaraya APCSB

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H. Silver, RL D. Fischer, APCSB F. Matthews, APCS 3 S. Yarga, RL J. Glynn, CS P. Hearn, APCSB D. Eisenhut, NBR APCSB:CS:TR APCSB :C&s TR APCSB:CS:TR CS:.TR o,,,,,,

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