ML17290A944
| ML17290A944 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/26/1994 |
| From: | Clifford J Office of Nuclear Reactor Regulation |
| To: | Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| TAC-M87076, NUDOCS 9402020369 | |
| Download: ML17290A944 (4) | |
Text
January 26, 1994 Docket No. 50-397 Mr. J.
V. Parrish (Mail Drop 1023)
Assistant Managing Director, Operations Washington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352-0958
Dear Mr. Parrish:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION, POWER UPRATE REVIEW (TAC M87076)
We are continuing our review of your July 9, 1993, submittal that proposed amendment of the WNP-2 license and associated Technical Specifications to increase the licensed power level for the facility.
Our Plant Systems Branch requires additional information as requested in Enclosure 1.
Sincerely, Original Signed By:
James W. Clifford, Senior Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosures:
See next page DISTRIBUTION:
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H. Swail es WNP-2 Plant Manager Washington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352-0968 G.
E.
C. Doupe, Esq.
(Hail Drop 396)
Washington Public Power Supply System 3000 George Washington May P. 0.
Box 968
- Richland, Washington 99352-0968 Hr. Warren Bishop, Chairman Energy Facility Site Evaluation Council P. 0.
Box 43172 Olympia, Mashington 98504-3172 Hr. H. K. Kook (Hail Drop PE20)
MNP-2 Licensing Manager Washington Public Power Supply System P. 0.
Box 968
- Richland, Mashington 99352-0968 Hr. D. Coleman (Hail Drop PE20)
Acting Regulatory Programs Hanager Mashington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352-0968 Regional Administrator, Region V
U.S. Nuclear Regulatory Commission 1450 Haria Lane, Suite 210 Walnut Creek, California 94596 Chairman Benton County Board of Commissioners P. 0.
Box 190
- Prosser, Mashington 99350-0190 Hr. R.
C. Barr U. S. Nuclear Regulatory Commission P. 0.
Box 69
- Richland, Washington 99352-0968 H. H. Philips, Jr.,
Esq.
Winston 8 Strawn 1400 L Street, N.M.
Washington, D.C.
20005-3502
Enclosure RE(VEST FOR ADDITIONAL INFORMATION WNP-2 POWER UPRATE Power Uprate Section 6.3 FUEL POOL COOLING AND CLEANUP SYSTEM (FPCCS)
Section 9.1.3.2.1 of thy WNP-2 FSAR states that the FPCCS can maintain the fuel pool less than 155 F assuming a normal heat load (presented in Table 9.)-3 of the FSAR),
a maximum heat exchanger cooling water temperature of 95 F, and having only one FPCCS pump and heat exchanger in operation.
How does the proposed power uprate affect the capability of the FPCCS to cool the fuel pool under the conditions described in the FSAR2 Power Uprate Section 6.4.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM (RBCCW)
The WNP-2 FSAR states that the RBCCW system contains three half-capacity heat exchangers based on the maximum normal cooling requirements.
Describe in detail the heat load under the maximum normal cooling conditions, and what effect the increase from the FPCCS heat exchangers, the RWCU non-regenerative heat exchangers, and the drywell air coolers will have on the RBCCW heat
'xchanger capacity.
Power Uprate Section 6.4.4 ULTIMATE HEAT SINK (UHS)
In the analysis of the UHS, reference is made to a reactor decay heat model that is more refined than the one used to conduct the original analysis in the FSAR, resulting in a nominal decrease in the spray pond temperature following a DBA-LOCA.
Has the new decay heat model been accepted by the NRC for its use in this analysis2 If it has not, justify your use of the model for this analysis.
Power Uprate Section 6.6 POWER DEPENDENT HVAC Section 6.6 of the power uprate submittal states that some Turbine Building (TB) space temperatures may exceed their design by as much as 5 F as a result of the power uprate.
It is further stated that these temperatures will not significantly affect the environment in the TB.
Provide assurance that equipment in the spaces exposed to temperatures exceeding design temperature will not be "significantly" affected.