ML20070P197
| ML20070P197 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 01/25/1983 |
| From: | Longenecker J ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT |
| To: | Check P Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8301260279 | |
| Download: ML20070P197 (3) | |
Text
e Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:83:196 JAN 2 51983 Mr. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Check:
ADDITIONAL AND REVISED INFORMATION REGARDING PRELIMINARY SAFETY ANALYSIS REPORT (PSAR) SECTIONS 9.1 AND 9.16 FOR THE CLINCH RIVER BREEDER REACTOR PLANT
Reference:
Letter HQ:S:83:183, J. R. Longenecker to P. S. Check,
" Additional and Revised Information Regarding the Plant Auxiliary Systems, Preliminary Safety Analysis Report (PSAR) Chapter 9," dated January 12, 1983 In response to comments from the staff reviewer, enclosed is additional informa-tion regarding PSAR Sections 9.16 and 9.1. is provided as a replacement page to the referenced letter (Attachment 5). Also, Figures 9.16-3 through 7 of the PSAR will be changed on the next PSAR amendment to show the appropriate automatic isolation valves are fail-as-is valves, as identified on page 7.6-12 of the reference. is a modification of PSAR Section 9.1 concerning the basis used to calculate the ex-vessel storage tank heat loads. This enclosure will be incorporated into a future PSAR amendment.
Questions regarding this submittal may be directed to Mr. D. Robinson (FTS 626-6098) of the Project Office Oak Ridge staff.
Sincerely, c
9 aft 1RRO Jo n R. Longenec er Acting DirectorC ffice of Breeder Demonstration Projects Office of Nuclear Energy 2 Enclosures cc: Service List Standard Distribution g
Licensing Distribution
%I B301260279 830125 PDR ADOCK 05000537 A
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1 ENCLOSURE 1 e
Sectton 9.16, Question 7 The discussion of recirculating gas cooling system shutdown on leak detection is inconsistent between PSAR Section 9.16 and 7.6.6.
Response
Automatic shutdown of Recirculating Gas Cooling Subsystem due to moisture detection signals has been deleted - to avoid automutic shutdown due to spurious signals. The attached change to PSAR Section 7.6.6.2.1.1.2 deleted the discussion of shutdown on high water vapor, but adds a shutdown due to high temperature in the return piping. Automatic shutdown of the Recirculating Gas Cooling Subsystems due to high water level in the cooler is retained in the discussion of PSAR Section 7.6.6.2.1.1.2.
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ENCLOSURE 2 a
y 44l new cor assemblies from the in-vessel transfer positions to the core, on a
( 44l one-for-one basis.
After completion of refueling and suitable period for decay, the spent core assemblies are removed from the EVST to the fuel han-dling cell, examined if desired, and loaded into the spent fuel shipping cask for shipment to a fuel reprocessor.
The design bases, description and safety evaluation of fuel han-dling and storage equipment and facilities are given in 9.1.1 (new fuel storage), 9.1.2 (spent fuel storage), 9.1.3 (spent fuel cooling) and 9.1.4 (fuel handling equipment).
Section 9.1.4 also describes the movement of fuel assemblies through the plant in more detail.
44l All design bases were peveloped to conform with the CRBRP De-sign Criteria 53, 54, and 55 described in Section 3.1, and with the intent 44l of Regulatory Guide 1.13.
The Reactor Refueling System is designed 36 to reduce the probability of operator mishandling or of maloperations that could cause fuel damage and potential fission product release, while limit-ing the in-plant bcildup of airborne raficactivity during normal plant oper-36 '
ations, so that the exposure to plant operators is minimized.
In addition, specific attention was given in the selection of equipment design bases to ensure that no single active component failure can result in a loss-of-safety function.
Additional margin is provided for protecting the public during refueling and fuel handling operations by the low leakage design of the RSB, and maintaining the RSB and RCB when the refueling hatch is open at a minimum of 1/4" W.G. negative pressure with respect to the outside atmos-phere, with the exhaust discharged through a high efficiency filter train
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capable of efficiencies as high as 99% adsorbent efficiency and a 99.9% com-bined HEPA filter efficiency.
For design basis events, the efficiencies of ection 6.2.6.2 are applied.
36 g
9.1.1 New Fuel St_orage 59l New fuel is stored within the Reactor Service Building (RSB) in the ex-vessel storage tank (EVST), containing sodium. This storage facil-ity contains both new and spent fuel In addition to the EVST, new fuel assemblies are also temporarily retained in shipping containers on the RSB operating floor and below the operating floor in two new fuel unloading stations.
Each of these two new fuel unloading stations can temporarily contain one shipping container with a new fuel assembly until unloaded.
A conceptual drawing is provided in Figure 9.1-3.
This section will cover only new fuel storage in the unloading stations and in the shipping containers.
Storage of new fuel in the EVST will be covered in Section 9.1.2 under spent fuel storage.
[Thefissionproductandtransuraniumelementsinventoriesaredevelope k
I hmanagementschemes.from the nuclear design data and reference equilibrium core The fission product inventory and its corresponding P
I energyJ pectrum were derived using the fission yields contained in the ENDF/b*ano RIBD code library and consider the cyclic T
operation and core / blanket management of the equilibrium cycle.
Amend. 59 9.1-3
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