ML17292B682
| ML17292B682 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/03/1999 |
| From: | Jack Cushing NRC (Affiliation Not Assigned) |
| To: | Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| TAC-MA5212, NUDOCS 9906070178 | |
| Download: ML17292B682 (10) | |
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3une 3, 1999 Mr. J. V. Parrish Chief Executive Officer Washington Public Power Supply System P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
REQUEST FOR ADDITIONALINFORMATION(RAI) FOR THE WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 (TAC NO. MA5212)
Dear Mr. Parrish:
The NRC staff has reviewed your amendment request regarding the minimum critical power ratio safety limits dated April7, 1999. As a result of the review, the staff has determined that additional information is needed to complete the review. The information needed is detailed in the enclosure.
The enclosed request was discussed with Mr. Arbuckle of your staff on May 17, 1999. A mutually agreeable target date of June 21, 1999, was established for responding to the RAI.
If circumstances result in the need to revise the target date, please call me at your earliest opportunity at (301) 415-1424.
Sincerely',
/s/
Jack Gushing, Project Manager, Section 2 Proje'ct Directorate IV 8 Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-397 II
Enclosure:
Supplemental Request for Additional Information cc w/encl: See next'page I(
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 2055&4001 3une 3, 1999 Mr. J. V. Parrish Chief Executive Officer Washington Public Power Supply System P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
REQUEST FOR ADDITIONALiNFORMATION(RAI) FOR THE WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 (TAC NO. MA5212)
Dear Mr. Parrish:
The NRC staff has reviewed your amendment request regarding the minimum critical power ratio safety limits dated April7, 1999. As a result of the review, the staff has determined that additional information is needed to complete the review. The information needed is detailed in the enclosure.
The enclosed request was discussed with Mr. Arbuckle of your staff on May 17, 1999. A mutually agreeable target date of June 21, 1999, was established for responding to the RAI.
Ifcircumstances result in the need to revise the target date, please call me at your earliest opportunity at (301) 415-1424.
Sincerely, Docket No. 50-397 Jack Gushing, Project Manager, Section 2 Project Directorate IV 8 Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Enclosure:
Supplemental Request for Additional Information ccw/encl: See next page
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Nuclear Project No. 2 cc w/encl:
Mr. Greg O. Smith (Mail Drop 927M)
Vice President, Generation Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352-0968 Mr. Albert E. Mouncer (Mail Drop 1396)
Chief Counsel Washington Public Power Supply System
. P.O. Box 968 Richland, Washington 99352-0968 Ms. Deborah J. Ross, Chairman Energy Facility Site Evaluation Council P. O. Box 43172 Olympia, Washington 98504-3172 Mr. D. W. Coleman (Mail Drop PE20)
Regulatory Affairs Manager Washington Public Power Supply System P.O. Box 968 "Richland, Washington 99352-0968 Mr. Paul Inserra (Mail Drop PE20)
Manager, Licensing Washington Public Power Supply System P.O. Box 968 Richland, Washington 99352 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Chairman Benton County Board of Commissioners P.O. Box 69 Prosser, Washington 99350-0190 Senior Resident Inspector
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Nuclear Regulatory Commission P.O. Box 69 Richland, Washington 99352-0968 Mr. Rodney L. Webring (Mail Drop PE08)
Vice President, Operations Support/PIO Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352 Perry D. Robinson, Esq.
Winston 8 Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Mr. Bob Nichols Executive Policy Division Office of the Governor P.O. Box 43113 Olympia, Washington 98504-3113
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RE UEST FOR ADDITIONALINFORMATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 WNP-2 DOCKET NO. 50-397 (1) The NRC approved methodology documented in CENPD-300-P-A, "Reference Safety Report for Boiling Water Reactor Reload Fuel," July 1996, was used for the reload methodology. In the staffs safety evaluation report (SER) of this topical report, eight limitations or restrictions were specified. The staff requires that the licensee address and confirm that all the applicable limitations or restrictions are satisfied for cycle-15 reload analysis.
(2) TS Page B 2.0-3, 2.1.1.2 MCPR. The sentence starting with "Reference-7" does not need to be deleted.
The sentence needs to be modified to reflect the new reference 7.
(3)
Page 1 of CE NPSD-844-P, "WNP-2 Cycle 15 Reference Core Reload Design Report,"
refers to ABB code'package PHOENIX2/POLCA4. PHOENIX and POLCA were approved by the staff in 1988.
Confirm that the newer versions of the codes, PHOENIX2 and POLCA4, are approved by the staff. Identify the staff approved topical reports which describe these new versions of the codes.
(4)
Provide justification, based on the analyses, for the substantial differences in the values of the SLMCPR for both fuel types and identify the cause of these changes, especially, for SVEA-96 fuel. Is the analysis based on the actual mixed core condition?
(5)
The following questions refer to the ABB letter dated February 19, 1999, page two, paragraph three.
(a)
Define the term nominal interassembly gaps used in this analysis.
(b)
Describe how the SVEA-96 fuel is monitored by the core supervision system.
(c)
Provide justification for the use of nominal interassembly gaps in the monitored CPR and its relationship with the 0.4 mm mean channel bow assumption in terms of CPR calculation.
(6)
Describe the relationship between the XL-S96 CPR correlation and the improved ABBD1.0 CPR correlation and identify their differences with respect to their data bases, correlations and applicable ranges of the application.
Provide the reason why ABBD1.0 is used to verify the results determined with XL-S96. Also, provide justification that 2.5 percent uncertainty used in ABBD1.0 correlation is sufficient for this SLMCPR calculation.
(7)
Provide justification on the adequacy of the following assumptions made for Cycle 15 thermal operating limits in the Section 3.3 of CE NPSD-844-P (WNP-2 Cycle 15 Reference Core Reload Design Report):
ENCLOSURE
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(a) the APLHGR and LHGR operating limits are the same as in Cycle 14; (b) 1.34 OLMCPR for cycle exposures less than 9600MWd/tu and a OLMCPR 1.38 for cycle exposure equal to or greater than 9600MWd/tu; (c)
CPR performance evaluated based on R-factors generated with 0.04 mm box bowing.
(8)
In Section 5.4 of NPSD-844-P it is stated, "....not all thermal margin requirements specified in reference 2 are satisfied." Please clarify the thermal margins that are not satisfied.
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