ML20217N385
| ML20217N385 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/20/1999 |
| From: | Stewart Bailey NRC (Affiliation Not Assigned) |
| To: | Campbell G CENTERIOR ENERGY |
| References | |
| TAC-MA5477, NUDOCS 9910290007 | |
| Download: ML20217N385 (4) | |
Text
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.c Octcber 20, 1999 2
Mr. Guy G. Campbell, Vice President - Nuclect FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CN FUEL STORAGE IN CASK PIT, DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 (TAC NO. MA5477)
Dear Mr. Campbell:
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By leder dated May 21,1999, you requested a license amendment to allow irradiated fuel to be stored in the cask pit at the Davis-Besce Nuclear Power Plant, Unit 1. V/c have reviewed your
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request and determined that we need additional information to complete our review. Please respond to the attached que,stions related to the thermal-hydraulic analysis. Other requests for j
additional information may be forthcoming as we continue our review of other aspects of your
- proposal.
These questions were discussed with Mr. D. Wookko of your staff. A response time of 60 days from the receipt of this letter was agreed to by your staff. If you have any questions about our rev;ew, or if you determine that you can not provide the requested information within 60 days, please contact me at (301) 415-1321.
Sincerely, Original Signed By Stewart Bailey, Project Manager, Section 2 Project Directorate til Division of Licensing Project Management Office of Nuclear Reactor Ragulation Docket No.50-34G DISTRIBUTION:
Docket
Enclosure:
Request for Additional Information PUBLIC PDill-2 Reading cc w/ encl: See next page AMendiola GHubbsrd OGC ACRS j
i GGrant, R!ll LBerry
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9910290007 991020 ggt (( 'i p %.it pra e w:3 3 y g gy DR ADOCK 050003 6 ua y (P
OOCUMENT NAME:~ G:\\PDill-2\\DAVISBES\\raia5477.wpd enclosures "N" = No To receive a copy of this document, indicate in the box: "C" = Copy without enclosures "E" = Copy
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copy
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OFFICE PM:PD32 IE LA PD31 E
C:SRXB CPDfil/2, NAME SBailey<4 EBarnniil.n=o) GHubbard*
('Af3endi6Q DATE 10 6e/99 10IX/99 9/20 /99 X10 Oc/99
- concur by memo dated 9/20/99 OFFICIAL RECORD COPY
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Y Mr. Guy G. Campbell Davis-Besse Nuclear Power Station, Unit 1
> FirstEnergy Nuclear Operating Company cc: _
- Mary E. O'Reilly.
Robert E. Owen, Chief FirstEnergy.
, Bureau of Radiological Health l76. South Main Street Service
' Akron, OH 44308 '
Ohio Department of Health '
P.O. Box 118 -
EJames L. Freels Columbus, OH 43266-0118 Manager - Regulatory Af' airs -
- FirstEnergy Nuclear Operating Company James R. Williams, Executive Director Davis-Besse Nuclear Power Station Ohio Emergency Management Agency 5501 North State - Route 2 2855 West Dublin Granville Road Oak Harbor, OH 43449-9760 Columbus, OH 43235-2206 Jay E. Silberg, Esq.
Director Shaw, Pittman, Potts Ohio Department of Commerce and Trowbridge' Division of Industrial Compliance 2300 N Street, NW.
Bureau of Operations & Maintenance Washington, DC 20037 6606 Tussing Road P.O. Box 4009 Regional Administrator Reynoldsburg, OH 43068 9009 U.S. Nuclear Regulatory Commission 801 Warrenville Road Ohio Environmental Protection Agency Lisle,IL 60523-4351' DERR--Compliance Unit ATTN: Zack A. Clayton Michael A. Schoppman P.O. Box 1049 Framatome Technologies incorporated Columbus, OH 43266-0149 1700 RockCile Pike, Suite 525 Rockville, MD 20852 State of Ohio Public Utilities Commiscion Resident inspector 180 East Broad Street U.S. Nuclear Regulatory Commission Columbus, OH 43266-0573 5503 North State Route 2
~ Oak Harbor, OH 43449-9760 Attorney General Department of Attorney i
James H. Lash, Plant Manager 30 East Broad Street FirstEnergy Nuclear Operating Company Columbus, OH 43216 Davis-Besse Nuclear Power Station 5501 North State Route 2 -
President, Board of County LOak Harbor, OH 43449-9760 Commissioners of Ottawa County Port Clinton, OH 43252 i
0 a
REQUEST FOR ADDITIONAL INFORMATION TECHNICAL SPEQLF10LATION CHANGE ON SPENT FUEL STORAGE F
IN CASK PIT l
DAVIS-BESSE UNIT 1 j
DOCKET NO. 50-346 1.
With regard to the thermal hydraulic analyses for the spent fuel pool (SFP), provide the i
decay heat loads from the partial (planned) core discharge and the full (unplanned) core discharge (information should clearly show the decay heat generated from each batch of
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the previously discharged spent fuel assemblies (SFAs) and from the freshly discharged partial core and full core in the SFP).
2.
With regard to the thermal hydraulic analyses for the cask pit, on page 5-15 of the Holtec report, Holtec stated that the entire fuel storage rack in the cask pit region is modeled as containing SFAs from previous discharges. Also, in Enclosure 2 (Commitment List) of the May 21,1999 submittal, FirstEnergy stated that caly relatively
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old SFAs, each with a maximum heat generation rate of 873 watts, were assumed to be i
stored in the cask pit. The duration which is required for these old/previously i
discharged SFAs to be placed in the SFP prior to being transferred to the cask pit is at least three years. FirstEnergy further stated that administrative controls will be established to ensure this three year age limitat;on for SFAs prior to being transferred to the cask pit. However, the proposed Technical Specifications (TS) Sections 3.9.13 and 4.9.131, which require tne SFAs to be pic;ed in the cask pit in accordance with the criteria shown in TS Figure 3.9-2, "Burnup vs. Enrichment Curve for Davis-Besse Cask Pit Storage Racks," will allow the entire freshly discharged core to be placed in the c=!<
pit. Please clarify these apparent discrepancies.
3.
Discuss the procedures or programs established to monitor and control the SFP and cask pit water temperatures during planned refueling octages and unplanned full core offload events. Information should include:
a.
Discuss how often the water temperatures in the SFP and the cask pit will be monitored.
b.
Provide the setpoints of the high water temperature alarms for the SFP and the cask pit.
c.
Discuss the precautious actions (i.e. prohibit fuel handing, aligning other systems to provide SFP cooling. etc.) to be taken in the event of a high SFP or cask pit water temperature alarm.
4.
The calculated minimum time from the loss-cf-pool cooling at peak SFP temperature until the pool boils based on the decay heat load for the full core off-load is 3.78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> with a maxirN.a boil-off rate of 69.57gpm. Discuss how this duration will be sufficient for the operators to intervene.
a 5.
The SFP cooling portion of the spent fuel pool cooling and cleanup system (SFPCC),
which is designed to maintain the SFP at or below 125'F with a decay heat load of 12.4 x 10' Blu/hr from all the previously discharged SFAs and a freshly discharged 1
partial (1/3) core, consists of two-half capacity cooling trains. Each cooling train is primarily equipped with one pump, one heat exchanger, and its associated valves, i
piping, instrumentation and controls. The decay heat removal (RHR) system wnich consists of two 100 percent capacity trains serves as a back-up system to the SFPCC system. Decay heat is removed from the SFP heat exchanger by the component cooling water system. Provide the following information:
a.
Prior to planned (partial) or unplanned full core offload, how msny trains of SFPCC system and RER system are required to be operable and available for SFP cooting?
b.
Discuss the provisions that have been established in the plant operating procedures to ensure that the RHR system will be aligned for SFP cooling.
6.
On page 5-2 of the Holtec report Holtec stated that to account for the future re-racking of the SFP, the bulk temperature analysis was performed using a conservative storage capacity of approximately 1,650 SFAs stored in the SFP. On page 5-13, Holtec stated that the decay heat generation rate in the cask pit racks is calculated based on the maximum heat generation rate from 1,609 SFAs. Also, in Table 5.6.1, Holtec indicated that the maximum number of SFAs assumed for SFP and cask pit analyses were 1,714 i
SFAs and 289 SFAs, respectively. Please clarify these apparent discrepancies.
7.
Please revise Table 5.8.1 of Holtec report to:
a.
Add a column to indicate 9e reactor shutdown time required prior to core discharge for each scenario, b.
Add a row for cask pit to indicate the reactor snatdowr> t;me required prios to core discharge, and the maximum bulk temperature and iti coincident decay heat load and coincident time after reactor shutdown.
c.
The note for scenarios 3A and 4A indicates that the coir. ident times for the corresponding bulk temperatures are measured from the second reactor shutdown. Please clarify what the second reactor shutdown is.
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