ML17331A138
| ML17331A138 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/02/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Tillinghast J INDIANA MICHIGAN POWER CO. |
| References | |
| NUDOCS 7901100406 | |
| Download: ML17331A138 (6) | |
Text
Docket Nos..
-3 and
- 16 Driginal Signed By gPNUARY g 3 178 DISTRIBUTION t
Docket Files 50-31 5 and 50-31 6
,NRR Rdg ORB1 Rdg Local PDR I'iRC P DR V. Stello D, Eisenhut B. Grimes A. Schwencer Hr; John Tillinghast, Vice President H
OELD Indiana and Hichigan Ele'ctric CompanyC'~r'r>>h Indiana and Michigan Power Company.
Post Office, Box 18 Bowling Green Station New York, New York 1 0004
=
ACRS (1 6)
Dear Hr. Tillinghast:
As a result of our,review of your November 22, 1978 submittal, r
I "Spent Fuel Storage Capacity Expansion". ~ we have developed the enclosed request for additional information.
You are requested to provide your response by January. 'l9, 1979.
Sincer ely,
~ r r
Enclosure:
Request for Additional Iriformation cc w/encl osure See next page A. Schwencer, Chief Operating Reactors Branch 81 Division of Operating Reactors t
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January 2,
1979 cc:
Mr.; Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire
- Shaw, Pittman Potts 8 Trowbridge 1800 M Street, NW Washington, D.C.
20036 David Dinsmore Comey Executive Director Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maude Reston Palenske Memorial Library 500 Market Street St. Joseph, Michigan, 49085 Donald C.
Cook Nuclear Plant ATTN:
Mr.
D. Shaller Plant Manager P. 0.
Box 458
RE/VEST FOR ADDITIONAL INFORMATION SPENT FUEL POOL CAPACITY EXPANSION DONALD C.
COOK'NUCLEAR PLANT DOCKET 'NOS.
50-315'AND 50-316 Plant S stems Branch 2.
Provide the distribution of sizes and the median size of the boron carbide particles in the Boral plate which was used in the "Bierman" (PNL-2438) critical lattices which are specified as items 5 and 6
on Table 3.1-8 of your November 22, 1978 submittal "Spent Fuel Storage Capacity Expansion".
Provide the distribution of sizes and the median size of the boron carbide particles in the Boral plates in the proposed racks.
- Also, describe how the self-shielding of the boron carbide particIes is accounted for in determining the effective cross section of the Boral plates.
- 3. If you do not propose to vent the stainless steel envelopes containing Boral plates, state the maximum k
in the fuel pool that could be obtained from the following scenaFQ:
Leaks occur near the bottom of the Boral envelopes of several adjacent guide tubes which allow pool water to enter the envelopes and chemically react with the aluminum coating on the Boral to form aluminum oxide and hydrogen.
The resulting generation of hydrogen causes the stainless steel envelopes of several adjacent guide tubes with fuel assemblies in them to swell.
4.
Section 3.1.4, which is entitled, "Storage Array Description" does not state whether or not there will be enough space between the periphery of the racks and the pool walls to insert a fuel assembly.
If there is, provide the maximum k f that will be obtained when a fuel assembly is brought up a5 close as possible to a rack which is fully loaded with fuel assemblies.
5.
The NRC requires an on-site neutron attentuation test to verify the presence of the boron.
This is in addition to the guality Assurance Program you described in Section 3.4.1.
Provide a
description of the neutron attenuation test that you will perform at the Cook site to statistically show with 95 percent confidence that the boron is not missing from enough plates to allow the keff to go above 0.95.
6.
There appears to be a deficiency in the boron surveillance program described in Section 3.4.2.
In order for this test with sealed samples to be valid, the probability of developing a leak in the surveillance sample must be the same as the probability of develop-ing a leak in the Boral envelopes in any of the racks.
These two probabilities do not appear to be equivalent.
Provide a boron surveillance program wherein the probability of developing a leak in any of the boron envelopes in any of the racks is conservatively accounted for.
Environmental Evaluation Branch 2.
3.
Provide the data to support your statement in the November 22, 1978, submittal that realistic assumptions were used to determine that the increment in on-site occupational dose, resulting from the proposed increase in spent fuel pool storage capacity, represents a negligible dose burden.
Your response should include the expected dose rates from the spent fuel pool water, spent fuel pool elements and any items that may be stored in the pool, the number of workers that will be exposed to this dose rate from all operations. associated with fuel handling in the spent fuel pool area, occupancy factors and the annual occupational man-rem exposure.
Based on your response, justify your conclusion that the occupational exposure will add less than 7%
to the total annual occupational radiation exposure burden.
Also justify that this exposure burden is as low as is reasonably achievable (ALARA).
In accordance with Section 2.5 of your submittal, the occupational exposure expected for the spent fuel pool modification is estimated to be 20 man-rem.
Provide the data showing the derivation of this estimate.
The data should include the expected dose rate to workers (including divers, if any) during each phase of the operation and their occupancy times.
Include the exposure that will be received from removal and disposal of the present spent fuel pool racks and miscellaneous equipment presently stored in the pool and installation of the new high density racks.
Describe the method you used to determine the techniques for disposal of the present racks (i.e., crating intact racks or cutting and packaging).
Present your consideration of'costs and disposal volume as well as the exposure received by the alternative disposal methods in determining as los as reasonably achievable (ALARA) exposure to personnel.
State how the present racks will be disposed of.
4.
Discuss in detail the impact of the proposed SFP modification on radioactive gaseous effluents from the plant.
5.
Provide the history of water leakage from your spent fuel pool'.
6.
You stated on page 12 in your submittal dated November 22, 1978, that the actual pool bulk water temperature can be expected to be greater than the FSAR design value of 120'F during normal refuelings when the modified pool is filled. If the actual bulk water temperature is expected to be above the FSAR design value under realistic conditions, discuss when this will occur, f'r what period of time and the effect of this on releases of radioiodine and tritium from the pool.
7.
Provide the failed fuel fraction for each fuel cycle at D. C.
Cook Units 1
and 2.
8.
Provide the volume of the pool demineralizer resin bed and the replaceable pool filter.
9.
Discuss the instrumentation to indicate the spent fuel pool water level.
Include the capability of the instrumentation to alarm and the location of the alarms.