ML17286A714

Forwards Amend to Tech Specs Providing Additions &/Or Deletions to Paragraph 6.9.3.2 of Insert B,Including Explanation of Reasons for Each Change,Per NRC Project Manager Request

ML17286A714
Person / Time
Site:	Columbia
Issue date:	04/19/1991
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17286A716	List: ML17286A714 ML17286A717
References
G2-91-81, GL-88-16, GO2-91-081, GO2-91-81, TAC-77311, NUDOCS 9104240158
Download: ML17286A714 (9)

Text

r ACCELERATED DISTRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9104240158 DOC.DATE: 91/04/19 NOTARIZED:

NO FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION SORENSEN,G.C.

Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards amend to Tech Specs providing additions 6/or deletions to paragraph 6.9.3.2 of insert B,including explanation of reasons for each change,per NRC project manager request.DISTRIBUTION CODE: A001D COPIES RECEIVED LTR r ENCL J SIZE TITLE: OR Submittal:

General Distribution NOTES DOCKET 05000397 D RECIPIENT ID CODE/NAME PD5 LA ENG,P.L.INTERNAL: ACRS NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 6 6 1 1 1 1 1 1 1 1 1 0 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD NRR/DET/ECMB 9H NRR/DOEA/OTS B1 1 NRR/DST/SELB 8D NRR/DST/SRXB 8E OC 8 LE 01 NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 1 1 D D R D NOTE TO ALL"RIDS" RECIPIENTS:

A D D PLEASE HELP US TO REDUCE WASTE!CONTAC!'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22 4 t WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 96B~3000 George Washington Way~Richland, Washington 99352 April 19, 1991 G02-91-081 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:

Subject:

NUCLEAR PLANT NO.2, OPERATING LICENSE NPF-21 RE(VEST FOR AHENDHENT TO TECHNICAL SPECIFICATIONS IHPLEHENTATION OF GENERIC LETTER 88-16, ADDITIONAL INFORHATION (TAC NO.77311)

Reference:

1)Letter, G02-90-132, GC Sorensen (SS)to NRC, same subject, dated August 2, 1990 2)Letter, G02-91-038, GC Sorensen (SS)to NRC, same subject, dated February 25, 1991 At the request of the NRC Project Hanager assigned to WNP-2, we have reviewed those technical specification change requests currently at the NRC to determine where additional guidance might be required to handle the word processing aspect of preparing the changed pages.Relative to the subject request we are providing the attached pages.This submittal suggests how to incorporate the added material, and makes additional clarifications requested by the staff.Attachment I provides additions and/or deletions to paragraph 6.9.3.2 of Insert B (Reference 1), including an explanation of the reasons for each change.Except for the changes identified in Attachment I, this submittal does not change the content of the request.The Supply System considers these changes to be administrative and do not effect the technical content of the previous submittals.

Very truly yours, C~'.C.Sorensen, Hanager Regulatory Programs Attachments cc: JB Hartin-NRC RV NS Reynolds-Winston It Strawn PL Eng-NRC DL Williams-BPA/399 NRC Site Inspector-901A 9104240158 910419 PDR ADOCK 05000397 P PDR~~@'L ATTACHMENT I REASONS FOR CHANGES TO'INSERT B DELETIONS 1.XN-NF-512(P)(A),"XN-3 Critical Power Correlation" Reason: The XN-3 correlation is not applicable to the final Cycle 7 and future designs.4.XH-HF-79-71(P)(A),"Exxon Nuclear Plant Transient Methodology" Reason: This methodology is=discussed in XH-HF-80-19(P)(A), Volume 3, Rev.2, and Volume 4, Rev.1, which is also referenced.

ADDITIONS l.ANF-1125(P)(A).and Supplements 1.and 2,"AHFB Critical.Power Correlation" April 1990 Reason: Reference expanded to include applicable revisions and supplements.

3.XN-NF-524(P)(A), Revision 2 and Supplements 1 and 2,"Exxon, Huclear Critical Power Methodology for Boiling Water Reactors", November 1990 Reason: Reference expanded;to include applicable revisions'nd supplements.

k 4..ANF-913(P)(A), Volume 1, Revision 1 and Volume 1, Supplements 2,'3 and 4,"COTRANSA 2: A Computer Program for Boiling'ater Reactor Transient Analysis";

August 1990 v Reason: Reference expanded to include applicable revisions and supplements.

I

5.ANF-CC-33(P)(A), Supplement 2,"HUXY: A Generalized Multirod fleatup Code With 10 CFR 50, Appendix K Heatup Option", January 1991 Reason: Needed.to provide spray heat transfer coefficients for 9x9-9X fuel assemblies; not approved when XN-NF-80-19 approved.6.XN-NF-80-19(P)(A), Volume 1, Supplements

.3 and 4,"Exxon Nuclear Methodology for Boiling Hater Reactors", November 1990 Reason: Reference expanded to include applicable revisions and supplements.

7.XN-NF-80-19(P)(A), Volume 4, Revision 1,"Exxon Nuclear Methodology for Boiling Hater Reactors: Application of the ENC Methodology to BHR Reloads", June 1986'Reason: Reference.expanded to include applicable

.revisions and supplements.

8.XN-NF-80-19(P)(A),'Volume 3, Revision 2,"Exxon Nuclear Methodology for Boiling Hater Reactors THERMEX: Thermal Limits Methodology Summary Description",.January 1987 Reason: Reference.expanded to include applicable revisions and supplements.

9.XN-NF-85-67(P)(A), Revision 1,"Generic Mechanical Design for Exxon Nuclear Jet Pump Boiling Hater Reactor Reload Fuel", September 1986 E Reason: Reference expanded'to include.applicable revisions and supplements 10.ANF-89-014(P),"Generic Mechanical Design for ANF 9x9-IX and 9x9-9X BHR Reload Fuel"., May 1989 Reason: Date added.

11.ANF-89-014(P), Supplement 1,"Generic Mechanical Design of ANF 9x9-IX and 9x9-9X BMR Reload Fuel", June 1990 Reason: Reference expanded to include applicable revisions and supplements 12.(SER for 9x9 mechanical design)Reason: Added to reserve space for NRC SER, which approves'References 10 and ll above.13..XN-NF-81-22(P)(A),"Generic Stati'stical Uncertainty Analysis Methodology", November 1983 Reason: Date added.14.'EDE-24011-P-A-6,"General Electric Standard Application for Reactor Fuel", April 1983 Reason: Added to.provide.LHGR and NPLHGR values for re-inserted initial core fuel.

INSERT B Core 0 eratin Limits Re ort 6.9.3.1 Core operating 1 imi ts shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

a.The AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGR)for Specifications 3.2.1 and 3.4.1.b.The MINIMUM CRITICAL POWER RATIO (MCPR)for Specification 3.2.3.c.The LINEAR HEAT GENERATION RATE (LHGR)for Specification 3.2.4.and shall be documented in the CORE OPERATING LIMITS REPORT.6.9.3.2 The analytical methods used to determine the core operating limits shall be those topical reports and those revisions and/or supplements of the topical report previously reviewed and approved by the HRC, which describe the methodology applicable to the current cycle.For WNP-2 the topical reports are: 1.ANF-1125(P)(A), and Supplements 1 and 2,"AHFB Critical Power Correlation", April 1990 2.Letter, R.C.Jones (NRC)to R.A.Copeland (AHF),,"HRC Approval of ANFB Additive Constants for ANF 9x9-9X BWR Fuel", dated November 14, 1990 3.XN-HF-524(P)(A), Revision 2 and Supplements 1 and 2,"Exxon Nuclear Critical Power Methodology for Boiling Water Reactors", November 1990 4.ANF-913(P)(A), Volume 1, Revision 1 and Volume 1, Supplements 2, 3 and 4,"COTRAHSA 2: A Computer Program for Boiling Water Reactor Transient Analysis", August 1990 5.AHF-CC-33(P)(A), Supplement 2,"HUXY: A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option", January 1991.6.XN-HF-80-19(P)(A), Volume 1, Supplements 3 and 4,"Exxon Nuclear Methodology for Boiling Water Reactors", November 1990 7.XN-NF-80-19(P)(A), Volume 4, Revision 1,"Exxon Nuclear Methodology for Boiling Water Reactors: Application of.the EHC Methodology to BWR Reloads", June 1986 8.XN-NF-80-19(P)(A), Volume 3, Revision 2,"Exxon Nuclear Methodology for Boiling Hater Reactors THERMEX: Thermal Limits Methodology Summary Description", January 1987 9.XN-NF-85-67(P)(A), Revision 1,"Generic Mechanical Design for Exxon Nuclear Jet Pump Boiling Hater Reactor Reload Fuel", September 1986 10.ANF-89-014(P),"Generic Mechanical Design for ANF 9x9-IX and'9x9-9X BWR Reload Fuel", May 1989 ll.ANF-89-014(P), Supplement.

1,"Generic Mechanical Design of ANF 9x9-IX and 9x9-9X BHR Reload Fuel", June 1990 I 12.(SER for 9x9 mechanical design)13.XN-NF-81-22(P)(A),"Generic Statistical Uncertainty Analysis Methodology", November 1983 14.NEDE-24011-P-A-6,"General Electric Standard Application for Reactor Fuel",'pril 1983