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| issue date = 04/19/1991
| issue date = 04/19/1991
| title = 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
| title = 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
| author name = SORENSEN G C
| author name = Sorensen G
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:r ACCELERATED DISTRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9104240158 DOC.DATE: 91/04/19 NOTARIZED:
{{#Wiki_filter:r ACCELERATED DISTRIBUTION DEMONS                                   TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
NO FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION SORENSEN,G.C.
ACCESSION NBR: 9104240158               DOC. DATE: 91/04/19     NOTARIZED: NO         DOCKET FACIL:50-397     WPPSS   Nuclear Project, Unit 2, Washington Public Powe           05000397 AUTH. NAME           AUTHOR AFFILIATION SORENSEN,G.C.         Washington Public Power Supply System RECIP.NAME           RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==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:
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                           D manager request.
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:
DISTRIBUTION CODE: A001D TITLE:    OR COPIES RECEIVED LTR Submittal: General Distribution r ENCL J   SIZE NOTES RECIPIENT               COPIES          RECIPIENT          COPIES ID  CODE/NAME            LTTR ENCL      ID CODE/NAME       LTTR ENCL          D PD5 LA                       1    1    PD5 PD                  1    1 ENG,P.L.                     2    2                                              D INTERNAL: ACRS                           6    6    NRR/DET/ECMB 9H        1   1 NRR/DET/ESGB                1    1    NRR/DOEA/OTS B1 1       1    1 NRR/DST        8E2          1    1    NRR/DST/SELB 8D         1    1 NRR/DST/SICB 7E              1    1    NRR/DST/SRXB 8E         1   1 NUDOCS-ABSTRACT              1     1     OC  8                  1   0 OGC/HDS1                    1     0            LE      01      1   1 RES/DSIR/EIB                1     1 EXTERNAL: NRC PDR                        1     1     NSIC                    1   1 R
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:
D A
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTAC!'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR 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:==
==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)
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:==
==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
~~@'L 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


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.
ATTACHMENT   I REASONS FOR CHANGES TO 'INSERT B DELETIONS
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.
: 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.
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.
: 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,
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";
Rev. 2, and Volume 4, Rev. 1, which is also referenced.
August 1990 v Reason: Reference expanded to include applicable revisions and supplements.
ADDITIONS
I  
: 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.


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
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:
.3 and 4,"Exxon Nuclear Methodology for Boiling Hater Reactors", November 1990 Reason: Reference expanded to include applicable revisions and supplements.
: a. The   AVERAGE PLANAR   LINEAR HEAT GENERATION RATES     (APLHGR) for Specifications 3.2.1   and 3.4.1.
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
: b. The MINIMUM CRITICAL   POWER RATIO (MCPR) for Specification 3.2.3.
.revisions and supplements.
: c. The LINEAR HEAT GENERATION RATE (LHGR)     for Specification 3.2.4.
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.
and shall be documented in the   CORE OPERATING   LIMITS REPORT.
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.
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:
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.
: 1. ANF-1125(P)(A), and Supplements     1 and 2,   "AHFB Critical Power Correlation", April   1990
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:
: 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
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.
: 3. XN-HF-524(P)(A), Revision 2 and Supplements 1 and 2, "Exxon Nuclear Critical Power Methodology for Boiling Water Reactors",
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}}
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}}

Latest revision as of 13:14, 29 October 2019

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 Energy Northwest icon.png
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:
References
G2-91-81, GL-88-16, GO2-91-081, GO2-91-81, TAC-77311, NUDOCS 9104240158
Download: ML17286A714 (9)
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Text

r ACCELERATED DISTRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 9104240158 DOC. DATE: 91/04/19 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 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 D manager request.

DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED LTR Submittal: General Distribution r ENCL J SIZE NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD5 LA 1 1 PD5 PD 1 1 ENG,P.L. 2 2 D INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H 1 1 NRR/DET/ESGB 1 1 NRR/DOEA/OTS B1 1 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC 8 1 0 OGC/HDS1 1 0 LE 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 R

D A

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTAC!'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR 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

~~@'L 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

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
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