ML17037C430
| ML17037C430 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/01/1977 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | Rhode G Niagara Mohawk Power Corp |
| References | |
| Download: ML17037C430 (8) | |
Text
SEP I Docket No. 50-220 Niagara Hohawk Power Corporation ATTN:
Hr. Gerald K. Rhode Vice President - Engineering 300 Erie Boulevard'West
- Syracuse, New York 13202 Gentlemen:
DISTRI8UTION:
Docket NRC PDR Local PDR ORB¹3 Rdg GLear Cparrish SNowicki
- VStello, KRGoller OELD OI8E (3)-
DEisenhut TBAbernathy JRBuchanan ACRS (16)
File Me are continuing our revie~ of your December 7, 1976 request for Technical Specification changes for the Nine Nile Point Unit Ho.
1 Spent Fuel Pool Modifications.
Me have concluded that we need additional information to complete our review.
Please provide responses to our request for additional information set forth in the enclosure within 30 days or sooner to permit timely review.
If you have any questions,
.please contact us.
Sincerely,
Enclosure:
Request for Additional Information (g-3)
Oriynat sfgnad by George Lear, Chief Operating Reactors Branch ¹3 Division of Operating Reactors ccrc See next page ORRICR~
SURNAME~
ORB¹3 x./
SNowick'.acr ORB¹3 GLear OATR~
..BL..ZL........I..77.
NRC EORM 318 (9.76) NRCM 0240 A U, 2, OOVRRNMRNT RRINTINO OFRICCI IOdd d2d d24
4 lt Ii I
I 4
I II JFt I
4 Jh i
~ il Ne IJJQJJ 4.I) j I
l
'I 4
4 P
I 4 e
v
~ 4 I
I 4
I'irritl 4
- f 4
lt II il hr ~ p I l'
II ere I Jf r
4
~44 4,
~ 4 4
4 I
."el
/)re
~ 'I ee Ifei 4
I I)441 je<)( I',
eh rle
Niagara t1ohawk Power Corporation
<<r cc:
Eugene B. Thomas, Jr., Esquire
- LeBoeuf, Lamb, Leiby 5 t1acRae l757 H Street, 1l.
'H.
Mashington, 0.
C.
20036 "
Anthony Z. Roisman, Esquire
- Roisman, Kessler and Cashdan 1025 15th Street, H.
W.
5th Floor Washington, D.
C.
20005 Oswego City Library 46 E. Bridge. Street
- Oswego, New York l3126
ENCLOSURE RE UEST FOR ADDITIONAL INFORMATION
-3 SPENT FUEL POOL MODIFICATION DOCKET NO. 50-220 1.
Provide the average burnup expected for the spent fuel in the spent fuel pool (SFP).
2.
Discuss any expected change in the radiological liquid effluents from the Liquid Radioactive Waste Disposal System (LRWDS) because of the proposed modification.
Discuss the impact of the filter precoat being transferred from the Spent Fuel Storage Pool Filtering System to the LRWDS.
3.
Discuss the disposition of the material to be removed from the spent fuel pool (e.g.,
spent fuel racks, seismic restraints) during the proposed modification. If the material to be removed will be dis-posed of as solid radwaste, provide the volume of the packaged waste.
4.
Provide the volume of solid waste to be generated by the replacement of the filter precoat in the Spent Fuel Storage Pool Filtering System.
Provide the current frequency of operation of and the normal flow rate through the filter.
Provide the current frequency of replacing the filter precoat.
Discuss and quantify any expected changes in the above due to the proposed modification;
5.
Explain why no equipment modifications for the Spent Fuel Storage Pool Filtering System (SFSPFS) were proposed.
Consider that the proposed SFP modification may result in a factor of approximately eight times mo'e fuel movements during the modification than during I
a normal refueling which may increase the level of crud in the pool above that expected during a normal refueling.
Justify why SFSPFS is adequate to maintain low fuel pool concentrations of radioactivity including crud so that there are reasonably low exposure levels in and around the fuel pool area during and after the modification.
6.
Provide a discussion of the increases in the doses to personnel from t
radionuclide concentrations in the SFP due to the expansion of the capacity of the SFP, including the following:
(a)
Identify the principal radionuclides and their respective con-centrations in the spent fuel pool water found by gamma isotopic analysis during all operations.
Identify the sample with respect to a specific operation (i.e. refueling, fuel handling, etc.).
(b)
Provide an estimate of the man-"rem exposure that will be received during removal of the old racks and installation of new ones.
(c)
Provide an estimate of the dose rates above the"spent fuel pool from the concentrations of the radionuclides identified in (a),
I and the concomitant occupational
- exposure, in annual man-rem, due to all operations associated with fuel handling in the spent fuel pool area.
Describe the impact of the proposed modifications on these estimates.
Include in your analysis the expected exposure from more frequent changing of the filter precoat.
0
'4 I