ML19331D318

Amend 56 to PSAR

ML19331D318
Person / Time
Site:	Clinch River
Issue date:	08/29/1980
From:	ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To:
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ML19331D317	List: ML19331D316 ML19331D318
References
NUDOCS 8009020003
Download: ML19331D318 (125)

Text

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PAGE REPLACEMENT GUIDE FOR AMENDMENT 56 l

CLINCH RIVER BREEDER REACTOR PLANT PRELIMINARY SAFETY ANALYSIS REPORT (DOCKET NO. 50-537)

Transmitted herein is Amendment 56 to the Clinch River Breeder Reactor Plant Preliminary Safety Analysis Report, Docket 50-537. Amendment 56 consists of new and replacement pages for the PSAR text.

Vertical lines on the right hand side of the page are used to identify question response information and lines on the left hand side are used to identify new or changed design information.

O The following attached sheets list Amendment 56 pages and instructions CJ for their incorporation into the Preliminary Safety Analysis Report.

I

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l v) 8009020 00 3

i O AMENDMENT 56 PAGE REPLACEMENT GUIDE REMOVE THESE PAGES INSERT THESE PAGES Chacter 1 1.1-15, 16 1.1-15, 16 1.2-7, 8 1.2-7, 8 1.2-16 thru 103 1.2-16 thru 104 1.3-11, 12 1.3-11, 12 Chapter 2 2.4-49, 49a 2.4-49, 49a Chapter 3 3.1-57, 58 3.1-57, 58 3.2-9a O

3.2-16, 17 3.2-16, 17 3.7-15, 15a, 16 3.7-15, 16 3A.1-9a, 9b 3A.1-9a, 9b 3A.4-5, 4-6 3A.4-5, 4-6 Chapter 4 i 4.2-60, 61 4.2-60, 61 4.2-76, 77 4.2-76, 77 4.2-242, 243 4.2-242, 243 4.2-518, 519 4.2-518, 519 l

4.3-15, 16 4.3-15, 16 4.3-35, 36 4.3-35, 36 4.3-39 thru 50 4.3-39 thru 50 4.3-53 thru 56 4.3-53 thru 56 4.3-59, 60 4.3-59, 60 4.3-63, 64 4.3-63, 64 4.3-67 thru 88 4.3-67 thru 88

4.3-94, 95 4.3-94, 95 4.3-106, 107 4.3-106, 107 4.3-110 thru 119 4.3-110 thru 119 4.3-122 thru 125 4.3-122 thru 125 4.3-128 thru 131 4.3-128 thru lal 4.3-144, 145 4.3-144, 145 l ()

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( REMOVE THESE PAGES INSERT THESE PAGES Chapter 4 (Cont'd.)

4.3-148, 149 4.3-148, 149 4.3-174, 175 4.3-174, 175 4.3-178, 179 4.3-178, 179 4.3-202, 203 4.3-202, 203 4.4-31, 32 4.4-31, 32 4.4-39, 40 4.4-39, 40 4.4-81 thru 86 4.4-81 thru 86 4.4-91 thru 94 4.4-91 thru 94 4.4-119, 120 4.4-119, 120 4.4-135, 136 4.4-135, 136 4.4-153, 154 4.4-153, 154 Chapter 5 5-xv thru xviii 5-xv thru xviii 5-xix, xixa 5-xix, xixa 5-xxi, xxia, xxib 5-xxi, xxia, xxib 5.1-12, 13 5.1-12, 13 5.2-1, la 5.2-1, la 5.2-4a, 4b 5.2-4a, 4b O 5.2-6, 6b 5.2-14, 14a 5.2-6, 6a 5.2-14, 14a 5.3-9, 10 5.3-9, 10 5.3-28, 28a 5.3-28, 28a i 5.3-30, 31 5.3-30, 31 5.3-39b, 39c 5.3-39b, 39c 5.3-71, 71a 5.3-71, 71a 5.3-74a, 74b 5.3-74a, 74b 5.3-75, 75a, 75b, 75c 5.3-75, 75a, 75b, 75c 5.3-88 thru 94 5.3-88, 89 5.3-98 thru 109 5.3-98 thru 109

! 5.3-123 thru 133 5.3-123 l 5.3-136 thru 141 5.3-136 thru 141 l 5.4-10, 11 5.4-10, 11 Chapter 7 7.5-18a, 18b, 19, 19a, 7.5-18a, 18b, 19, 19a, 20 thru 25 20 thru 25 7.5-40, 41 7.5-40, 41 7.5-45, 46 7.5-45, 46 l Chapter 9 l

9.8-14, 15, 16 9.8-14, 15, 16 l

9.13-47, 48 9.13-47, 48 l

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i . t j' Chapter 15 i- 15.3-50, 51 15.3-50, 51 }

{ 15.6-41, 42 -15.6-41, 42 .

! Chapter 17  :

i j 17E-33, 34 17E-33, 34 i 17J-3, 4 17J-3, 4

$ 17J-38, 39 17J-38, 39 I l

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AMENDMENT 56 ,

QUESTION / RESPONSE SUPPLEMENT This Question / Response Supplement contains an Amendment 56 tab

{ sheet to be inserted following the Q-i (Amendment 55, June 1980) page.

Page Q-1 (Amendment 56, August 1980) is to follow the Amendment 56 tab.

l There are no new or updated Question / Response pages included in this Amendment.

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TABLE I (Continued)

(\

C Discussed Further in No. Title Rev. PSAR Section(s) 56l 1.38 Quality Assurance Requirements for 2 17.1, Question 411.2 Packaging, Shipping, Receiving, Storage & Handling of Items for Water-Cooled Nuclear Power Plants 56l (5/77) 1.39 Housekeeping Requirements for -

17.1, Question 411.2 Water-Cooled Nuclear Power Plants (3/16/73) 1.40 Qualification Tests of Continuous- 0 7.1.2 Duty Motors Installed Inside the (Tables 7.1-2 and 7.1-3)

Containment of Water-Coo 1'd Nuclear Power Plants (3/16/73) 8.3 1.41 Preoperational Testing of Redundant 0 8.3 On-Site Electric Power Systems to Verify Proper Load Group Assignments (3/16/73) 1.42 Interim Licensing Policy and As Low -

This Guide has been withdrawn As Practicable for Gaseous Radio- by the NRC.

iodine Releases from Light-Water-Cooled Nuclear Power Reactors (6/73) 1.43 Control of Stainless Steel Weld 0 Note 3 Cladding of Low-Alloy Steel Components (5/73) 1.44 Control of the Use of Sensitized -

NA Stainless Steel (5/73) t

1.45 Reactor Coolant Pressure Boundary -

NA j Leakage Detection System (5/73) 1.46 Protection Against Pipe Whip Inside -

NA Containment (5/73)

! 1.47 Bypassed and Inoperable Status Indi- 0 7'.l.2.9 i cation for Nuclear Power Plant Safety

Systems (5/73) 44 i

fa 1.1-15 Amend. 56 l Aug. 1980

- - - , - - - - - , ,,,emw--r, - - -

TABLE I (Continued)

O Discussed Further in No. Title Rev. PSAR Section(s) 1.48 Design Limits and Loading Combinations 0 3.9.1.5 for Seismic Category I Fluid System Components (5/73) 1,49 Power Levels of Nuclear Pcver Plants 1 Due to the Power Levels of CRBRP, this Guide has no impact.

1.50 Control of Preheat Temperature for 0 Note 4

, 44 ' Welding of Low-Alloy Steel (5/73) 1.51 Inservice Inspection of ASME Code -

This Guide has been with-Class 2 and 3 Nuclear Power Plant drawn by the NRC.

25 Components (5/73)

I Amend. 44 April 1978 1.1-16

!~

' the secondary shutdown system is arranged using a general coincidence logic. These logics are described in Section 7.2.1. Primary and O secondary systems are electrically and mechanically isolated. Sufficient redundancy is included within each system to assure that single random failures will not degrade protection by either system.

j l.2.7 Auxiliary Systems o

The Auxiliary Liquid Metal System provides the facilities for

receipt, storage and purification of all liquid metal used in the CRBRP.

It also provides the capability for controlling reactor sodium level variations, accommodates primary sodium volumetric changes, provides cooling for the core components stored in the Ex-Vessel Storage Tank (EVST),and by means of the Direct Heat Removal Service (OHRS) oives a means of long term reactor decay heat removal that is independent of the i 26 intermediate heat transport system and steam generator system loops.

4 The Compressed Gas System processes ambient air to provide compre > sed dry air for pneumatic instruments, maintenance systems, unloading devices, tooling, and miscellaneous cleaning and inspection services. This system provides for sodium removal systems and as required for plant usage.

j i

The Recirculating Gas Cooling System provides cooling service to cells and equipment located in the Reactor Containment Building and the Reactor Service Building. ,

15 The Chilled Water Systems provide heat removal l

' capability from certain equipment and areas in~ the Reactor Containment 4 Building and the Reactor Service Building.

The Inert Gas Receiving and Process 199 System (IGRPS) provides j

inert gases as required by other systems of the CRBRP, including cover gas, 1

cell inerting atmosphere, valve actuation gas in inerted cells, cooling gas, gas for certain seals, gas for fire-control blanketing, for component

! cletning and other services, and vacuum for out-gassing and gas-collection purposes. In addition, the IGRP System provides for the control of reactor

cover gas radioactivity and for the processing of gases to be released from the system to remove their contained radioactivity.

i The Impurity Monitoring and Analysis System provides for the I' sampling, monitoring, and analysis of the sodium, NaK, and argon cover gas systems in the plant, and acceptance sampling and analysis of incoming j 56 sodium, NaK, argon, and nitrogen.

!' The Treated Water System includes the domestic (potable) water 4

system, the closed cooling water system, water (makeup) treatment system j and the cooling water makeup system.

i i

The River Water Service System handles and treats river water

, for the plant. The system includes the river water pumps and piping, 4

intake filtration equipment and the plant service water system.

4 Amend. 56 1.2-7 Aug. 1980 l

The Heat Rejection System provides the heat sink.using the main cooling tower for waste heat loads from the turbine condensers, and from the various plant auxiliary and service systems such as sodium pump oil coolers, air conditions, air compressors, pump coolers and the turbine oil coolers.

41 44 The Emergency Plant Service Water System emergency cooling tower structure pro-vides the heat sink for the safety related components listed in Table 9.9-3. De-tails of the auxiliary system are given in Chapter 9.

1.2.8 Refueling System The reactor core is designed to be refueled annually. Under equilibrium conditions, all fuel and inner blanket assemblies are replaced as a batch every two years, with a planned mid-term interchange of 6 inner 41l blanket assemblies for 6 fresh fuel assemblies designed to add sufficient 20 excess reactivity to the system to complete the (550 fpd) burnup. The radial blanket assemblies in the first and second rows are replaced as a batch at 4 and 5 year intervals, respectively. No fuel or blanket 51 44 I shuffling is planned.

The In-Vessel Handling Subsystem (IVHS) provides for the transfer of 44l core assemblies in the reactor vessel, between their normal positions in the reactor core and storage positions outside the core accessible by the Ex-41l .

vessel Transfer Machine. The major equipment comprising the IVHS are the In-Vessel Transfer Machine (IVTM), Auxiliary Handlirg Machine (AHM), AHM Floor Valves (FV), IVTM Port Adaptors, and associated maintenance and storage facili-ties and equipment. The IVTM is installed in the small rotating plug in the reactor head after reactor shutdown. The machine raises or lowers core 44 l assemblies by neans of a grapple. Translation to a new position is by rota-tion of the rr. actor head rotatable pit gs. The AHM is used to install and re-4l l 44 l move the control rod drivelines, port pM,s, and in-vessel section of the IVTM in the reactor. The port adaptors and floor valves provide a means for closure of the reactor and storage ports during the time the port plugs are removed for i refueling operations.

l The Ex-Vessel Handling Subsystem (EVHS) provides for the transfer j of core assemblies between the reactor, the Ex-Vessel Storage Tank (EVST),

44 and the Fuel Handling Cell (FHC) located in the Reactor Service Buildin9 (RSB). The 41 I system consists of the Ex-Vessel Transfer Machine (EVTM) mounted on a Gantry-44 l Trolley (G-T), EVTM Floor Valves (FV), Core Component Pots (CCP),_ port plugs and adaptors, and associated maintenance and storage equipment and facilities.

The Ex-Vessel Storage Subsystem (EVSS) consists of the Ex-Vessel Storage Tank (EVST), and the associated maintenance equipment. The EVST is a 44 l sodium-filled tank used to store and cool spent fuel prior to shipment off-site, and preheat new core assemblies. The capacity of the EVST is about 650 41 I assemblies.

44 41l 0

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• General Arrangement O PLAN Reactor Containment Building Plan El.-733'-0" 1.2-22 k Araend. S'6 Aug. 1980

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- Aug. 1980

i Co.vaesutet bb

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