ML17292B671
| ML17292B671 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/24/1999 |
| From: | Jack Cushing NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-MA5212, NUDOCS 9905270198 | |
| Download: ML17292B671 (7) | |
Text
Nay 24, 1999 MEMORANDUMFOR:
~ Docket File FROM:
SUBJECT:
Jack Gushing, Project Manager, Section 2 /s/
Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS)
NUCLEAR PROJECT NO.2 (WNP-2) - FACSIMILETRANSMISSION; QUESTIONS ON THE LICENSEE'S AMENDMENTREQUEST FOR A CHANGE IN THE MINIMUMCRITICALPOWER RATIO SAFETY LIMITS(TAC NO. MA5212)
The attached questions were transmitted by fax on May 6, 1999, to Mr. Arbuckle of WNP-2 to prepare him and others for an upcoming telephone call. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-397
Attachment:
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e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 May 24,.1999 MEMORANDUMFOR:
Docket File FROM:
SUBJECT:
Jack Gushing, Project Manager, Sectio Project Directorate IV 8 Decommissionin Division of Licensing Project Manageme Office of Nuclear Reactor Regulation WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS)
NUCLEAR PROJECT NO.2 (WNP-2) - FACSIMILETRANSMISSION, QUESTIONS ON THE LICENSEE'S AMENDMENTREQUEST FOR A CHANGE IN THE MINIMUMCRITICALPOWER RATIO SAFETY LIMITS(TAC NO. MA5212)
The attached questions were transmitted by fax on May 6, 1999, to Mr. Arbuckle of WNP-2 to prepare him and others for an upcoming telephone call. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-397
Attachment:
As stated
RE VEST 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 Staff SER of this topical report, eight limitations or restrictions were specified. We require 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" need not be deleted. Reference 7 is valid. Delete only the term "interim" and change "Cycle 14" to "Cycle 15" from the sentence since interim additive constant is no longer used.
(3)
Page 1 of CE NPSD-844-P, "WNP-2 Cycle 15 Reference Core Reload Design Report,"
refer 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 2, paragraph 3.
(a)
Define the term nominal interassembly gaps used in this analysis.
I (b)
Describe how the SVEA-96 fuel is monitored by the core supervision system.
1 (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, correlation itself 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% uncertainty used in ABBD1.0 correlation is sufficient for this SLMCPR calculation.
ATTACHMENT (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):
(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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