ML19220C136
| ML19220C136 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/24/1975 |
| From: | Stello V Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904280284 | |
| Download: ML19220C136 (3) | |
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---y Cocket Fil e Cocket :ios. ST'i 50-320 TR Reading RSB Reading V. Stello E. Leins Voss A. Moore, Jr., Assistant Director for L'JR's Crc o 2 Division of Tecnnical Review SECOND 20U:0 QUESTIO:iS - THREE "ILE ISLND NL'CLEAP. STATION, UNIT 2 Plant ilare: Three Mile Island, Unit 2 Licensing Stage-OL Cocket tio. : ST:i 50-320 Restensible Bear.ch and Project Manager: LWR 2-2. D. Washburn Technical Review Branch Involved: Reactor Syste.s Brancn Requested Completion Date: February 14, l'375 Applicant's Response Date lece:sary for Completion of hext Action Planned on Project: June 27. 1975 Review Status: Awaiting Infomation Adequate responses to the enclosed list of questiens prepared by the Reactor Systems Branch are required before we can enfrplete our review of the subject application. This request concems compliance by the applicant with the Codes and Standards Rule, Seci.icn 50.55a of 10 CFR Part 50, System Quality Grtuo Classifications and Seisnic Classiff-cations of fluid systems important to safety.
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31cice Steno Victor Stello, Jr., Assistant Director for Reactor Safety Division of Technical Reviea Office of Nuclear ocactor Regulation
Enclosure:
Question List ec:
S. Hanauer F. Sc h eder K. Kniel 97'!
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T. Novak R. Kirkwood S. Varga
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e THREE MILE ISLAND NUCLEAR STATIC'l, UNIT 2 CCCKET NO. 50-320 211.0 Reactor Systems Branch 211.18 The following systems, portions of systems or coroonents (3.2.2) important to safety are currently classified Quality Grouc C by the commission in conformance with Regulatory Guide 1.26.
These systems are:
(1) Emergency Feedwater System (2) Cooling Water Systems (to the ultimate heat sink) which service ccmocnents in systems important to safety (3) Diesel Fuel Oil System, and (4) Diesel Generator Auxiliary Systems Demonstrate thac your A-E Quality Group D Classification of these systems ano th'e use of the ANSI B 31.1.0 Pcwer Pioing Code is essentially equivalent to those ASME Code requirements in Ragulatory Guide i.26 by identifying the nondestructive testing and quality assurance requirements that you will in-pose and by demonstrating that the requirements t.ill provide a quality level at least equivalent to that associated with the corresponding AS"E code class in Pegulatory Guide 1.26.
Indicate those measures that will be taken to implement any additional requirements in terms of the quality assurance provisions to be applied.
211.19 In Table 3.2-1, identify the code class in the Draf t ASME Ccde (3.2.2) for Pumps and Valves for the folicwing components:
(1) Decay Heat Closed Cooling Water Valves, (2) Decay Heat Removal System Valve CH-V3, and (3) Reactor Coolant Makeup and Purification Pumps 211.20 In Table 3.2-1, identify the ccde class ir. ANSI B31.7 Nuclear Power Piping Code for piping BS-VlA/S and 3A/B in the Reactor Building Emergency Spray System.
211.21 In Figure 9.3-6 of the Makeup and Purification System, the (3.2.2) classification change of the letdown line frcm Ouality Group B to Quality Group C at valves MU-VICO, YU-V102 and MU-V103, and continuing through the purificaticn filters, purificaticn demineralizers, makeuc filters, seal return coolers, makeup tank to valves MU-V12 and MU-V26 is not in agreement with
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current AEC cractice. The Regulatory staff position is that the entire letdcwn line of the Makeup and Purification System should be classified Quality Group B.
Sinct the system is in an advanced stage of comoletion, denenstrate that with additional nondestructive testing requiremeats you will impose on systen piping, your prouosed classifica-tien will provide a quality level essentially equivale.it to that associated with Quality Group 3.
Incicate those measures that will be taken to implement any addit';nal requirements in terms of the quali y assurance provisions t
to be applied.
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