ML17187A849
| ML17187A849 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/13/1997 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | Johnson I COMMONWEALTH EDISON CO. |
| References | |
| TAC-M97983, TAC-M97984, NUDOCS 9703140136 | |
| Download: ML17187A849 (3) | |
Text
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OFC NAME I
DA:TE March 13, 1997 Ms. "Irene Johnson, Acting Manager Nuclear Regulatory Services Commonwea 1th Edi son Compa*ny Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, IL 60515
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SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. M97983 AND M97984)
Dear. Ms. Johnson:
By letter dated February 17, 1997, Commonwealth Edison Company (ComEd) requested that the NRC review and approve an application for an amendm~nt relating to a Technical Specification {TS) ~hange and an Unreviewed Saf~ty Question (USQ).
The TS change and t~e USQ involved the resolution of issues related to providing adequate net.'positive*suction-head (NPSH) for the Emergency Core Cooling System (ESSC) pumps *at the Dresden Station.
The staff has reviewed the license.amen9ment.and supporting documentation and discovered information must be provided t~,allow the NRC staff to compl~te its review.
To expedite the NRC staff revie~, ComEd should provid~ the respons~s to the enclosed request for additior:ial infor'mati.on (RAI) as-soon.. as possible.
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I Any questions concerning the-RA'I o'r other.issue~*relat~d to the license amendment please contact me at. (30,1) 415-)345; ' ' ;;.....
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~-Sincerely,, *.
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.Ori gi~a~ s1 gned by-: : "' _ :
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~--*John F~.Stang, Senio~ Project Manager
-*Projeet' Di:rectorate* HI-:2 Divisi9r of Reattci-r, Projects - III/Iv-Offtce ~f Nutlear.Reactor Regulation Docket Nos~ 50~237 and.50-249
Enclosure:
RAI cc ~/encl: See next pag~*
DISTRIBUTION:
{[Dmet..... F-.T-.lID
. J. Roe, JWR J. Stang, JFS2 P. Hiland, RI II PUBLIC E. Adensam, OGC,.015B18 C. Moore EGAl NRC FILE CENlEll COPY PDIII-2 r/f -
R. Capra, RACl ACRS, T1E26 6MNTJR\\DRESDEN\\DR97983.LTR D: POI II-2 11
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'I I. Johnson
- Commonwea 1th Edi s*on Company cc:
Michael.I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Site Vice President Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450~9765
.Station Manager Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illiriois 60450-9765 U.S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station 650ti North Dresden Road Mqrris, Illinois 60450-9766 Regional Administrator U.S. *NRC, Region III.
801 Warrenvi 11 e Road Lisle, Illinois* 60532-4351 Illinois Department of Nuclear Safety
- Office of Nuclear Facility.Safety 1035 Outer Paik Dr1~e
- Springfield, Illinois 62704 Chairman Grundy County Board
- . Administration Building 1320 Vnion Street Morris, Illinois 60450 Document Control Desk-Licensing
- Commonwea 1th* Edi son Company
- 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 Dresden Nuclear Power Station Unit Nos. 2 and 3
REQUEST FOR ADDITIONAL INFORMATION INPUT PARAMETERS USED IN ANS 5.1 DECAY HEAT MODEL, USED FOR CONTAINMENT PRESSURE AND TEMPERATURE RESPONSE ANALYSIS FOR DRESDEN STATION DOCKET NOS. 50-237 AND 50~249 I.
Provide and. justify the values for the following ANS 5.1 input par~meters. Those values with an (*) next to them have already been provided to the staff; however, the val.ue chosen should be justified.
- a. Q (total -recoverable ener~y) (MeV/fission) *
- b. 6Q (one standa~d deviation of recoverable energy, Q) (MeV/fission)
- c. P. (total power from fissioning of one nuclide) (MeV/sec)
- d. 6P (one standard deviation of power, P, frQm fissioning of nuclide)
(MeV/sec)
- e. Fractional fission produtt power for: U235,**U23a, Pu239 ~nd Pu241.
neutron capture in fission products)
- f. R-factor (the a~tinide produ~tion m~ltiplie~)
- g. G-factor (a decay heat m~ltiplier to ~ccount for the effect of neutron capture in fission products).
"*h. Si. (a /multiplier applied to. the G-factor equation) (fissions per initial fissile atom)
- i. Power.history (length of full-power operation before shutdown)
- 2.
Specify how the length of time at full power operation *before shutdown was estimated, -~nd confirm that th1s value is 1.2_6 years, as specifie.d in reference 32, "Letter to S. Mintz to J. Nash, Review* of NRC
- Information Notice. 96-39, February 7, 1997," of your February 17, 1997, license ameridment request.
Why was a value 1.26 years chosen for th~
time at full power, versus *3_4 years.
Comment on the differences between using 1.26 years versus 3.4 years.
- 3.
P.age 47 of your February J7, 1997", submittal states that ANS 5.1-1979 decay heat was used "without adders." The staff has typically required an uncertainty of two standard deviations (2-sigma) when using th~ ANS 5.1-1979 model.
Justify that your use of the ANS 5.1 model for decay
- heat. is conservative by showing that at least two standard* deviations of confidence in the decay heat is provided.
Ratio versus time of the decay calculated with ANS 5.1 relative to May-Witt, ANS 5.1 with a l~sigma uncertainty added relative to May-Witt, and ANS 5.1 with a.
2-sigma_ uncertainty added relative to May-Witt, would be particularly helpful; ENCLOSURE