ML19320C223
| ML19320C223 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/11/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19320C224 | List: |
| References | |
| NUDOCS 8007160471 | |
| Download: ML19320C223 (5) | |
Text
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..i 400 Chestnut Street Tower II July 11, 1980 Director of Nuclear Reactor Regulation Attention:
Mr. A Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulator *, Commission Washington, DC 20555
Dear Mr. Schwencer:
In the Matter of the Application of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 In response to informal questions asked by J. Spraul on the Sequoyah Nuclear Plant Final Safety Analysis Report (FSAR) Table 17.2-1, we are enclosing the following infor=ation. - Responses to J. Spraul's Questions on FSAR Table 17.2-1 - Appendix A to the Operational Quality Assurance Manual (0QAM) for Sequoyah Nuclear Plant, "The Critical Structures, Systems, and Components List" - Part III, Section 2 of the CQAM for Sequoyah Nuclear Plant, " Materials and Spare Parts" If you have any questions please get in couch with D. L. Lambert at FTS 857-2581.
Very truly yours, TENNESSEE VALLEY AUTHORITY
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L. M. Mills, Manager Nuclear Regulation and Safety Enclosures 3CM THIS DOCUMENT CONTAINS jj P00ft QUAUTY PAGES 8007160011
ENCLOSURE l'
-Responses to Questions on FSAR Table '17.2-1 1.
Question:
The following items from the Q-list (FSAR Table 17.2-1) need expansion and/or clarification as noted. Revise the list as indicated or justify not doing so.
1.0 Primary Containment Include missile barriers and containment sump system.
2.2 Electrical Identif y the specific electrical systems included.
3.1 Emergency Gas Treatment Include H -0 m nit rs, H
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System recombiner,_and control panel.
4.0 Reactor Building Include missile barriers.
4.2 Containment Purge System Include radiation monitors.
5.0 Auxiliary Building Include filters for the venti-lation system and include individ-ual room vent systems for SI, RHR, end CS pump rooms.
5.9 Fuel Handling Area Include fuel handling system Ventilation radiation monitor.
6.0 Control Building Include filters for the ventilation system.
6.3 Main Control Room A/C Identify the systems included sucN System as the radiation monitoring system, the chlorine monitoring system, etc.
10.0' ' Refueling Water Storage Identify the systems included.
Tank 11'.0
. Reactor Coolant System Identify leak detection system, PORV's pressurizer safety valves, PORV block valves, and RCP cooling water and RCP seal water systems.
11.11 Electrical Identify the electrical systems included.
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2 12.1 Main Steam Indicate that the system extends to and includes the outermost contain-ment isolation valves and includes the steamline power operated atmospheric dump valves.
13.1 dhin Feedwater Systen Indicate that the system extends to arid includes the outer =ost containment isolation valves.
-14.0 Safety Injection System Include sump instruments and RWST level instruments needed for switchover to recire phase.
'16.0 Containment Spray System Include cold leg accumulators.
18.0 Chemical and Volume Include boron recovery system.
Control System 22.0 Instruments and Controls Include reactor trip sy tem and ESF actuation system.
22.1 Cabinets, Panels, Racks Include sensors, indication systems, and annunciation systems.
23.0 Emergency. Power System Include the emergency diesel fuel oil system including the storage tanks.
23.1 Diesel Generator System Include auxiliary systems such as the lube cil sysrem, the air starting system, and the jacket cooling system.
24.
Upper Head Injection Include isolation valves and the System system. -
30.
Safety Related Display Identify the systems included and*
Indication include ceteorological data collection system.
Response
A complete explanation of these items, with two exceptions, is found in the detailed listing of critical structures, systems, and components j
(CSSC) which is contained in the Sequoyah Operational Quality Assurance i
Manual. As explained in the preface to Table 17.2-1, the detailed CSSC list is maintained at the plant but a copy of the current list is attached for NRC review. One exception is tne NRC comment on section 16.0.
There are no cold leg accumulators in the containment spray system. -The other exception is the meteorological data collection I
system, jrVA's meteorological data collection system is maintained by by a different division within TVA and the required quality assurance program is conducted by that division and is not contained in the_
Division of Neclear Power's CSSC list.
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Question:
The follbwing items do not appear on the Q-liet (FSAR Table 17.2-1).
Add these itens -to the list or justify no doing so:
a.
b.
Environmental Monitoring System for areas that contain safety-related equipment.
c.
Electro-Hydraulic Control System - Portions that control the closing of turbine stop valves, intercept valves, turbine bypass valves, a -i other main steam system downstream valves that are needed co close in the event of a MSLB with failure of MS1V to c1: se, d.
Emergency AC Auxiliary Power Systems (Class IE) 1.
Fire Stcps and Seals 2.
AC Power Inverters 3.
Auxiliaries associated with the diesel generator system 4.
Switchgear, Load Centers, and Motor Control Centers 125 Volt Class IE DC Vital Power Distribution System e.
1.
Battery Racks 2.
Cable Trays and Supports (Raceway installation conraining Class IE cables and other raceway installations required to meet seismic Category I requirements) f.
Expendable and Consumable Items necessary for the functional performance of CSSC (i.e., weld roa, fuel oil, boric acid, snubber oil, etc.)
g.
Measuring and Test Equipment h.
Spent Fuel Pool Cates
Response
The cooling towers are not included in the CSSC list since they a.
are not part of the Ultimate Heat Sink and thus have no safety
- function, b^.
A detailed listing of safety-related environmental monitoring instruments is contained in the attached CSSC list.
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4 c.
The turbine stop valves, intercept valves, turbine bypass valves, and ocher main steam system downstream valves provi,de no safety or isolation function in the event of a main steamline break.
Thu*, that accident sequence is not a justification for including the operators and control systems for these valves on the CSSC list.
d.
All of these items are included in the attached CSSC list, e.
All of these items are included in the attached CSSC list.
f.
The CSSC list contains only permanently installed structures, systems, and components. Expendable and consumable items necessary for the functional performance of CSSC and measuring and test equipment used on CSSC are controlled by separate procedures as explained in the TVA Topical Report, TVA-TR-75-1A,
" Quality Assurance Program Description for Design, Construction, and Operation of TVA Nuclear Power Plants."
g.
See response to item f. above, h.
The spent fuel pool gates are not on the CSSC list because failure of the gates would not lead to unacceptable water levels in the spent fuel pool.
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d
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