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| | issue date = 03/09/1998 | | | issue date = 03/09/1998 |
| | title = Provides Mod to 971204 Request for Amend to Licnese NPF-21, Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only,As Identified by T Huang (NRR) During 980211 Site Visit | | | title = Provides Mod to 971204 Request for Amend to Licnese NPF-21, Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only,As Identified by T Huang (NRR) During 980211 Site Visit |
| | author name = BEMIS P R | | | author name = Bemis P |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:CATEGORY 1 REGULA Y INFORMATION DISTRIBUTI SYSTEM (RIDS)ACCESSION NBR:9803170386 DOC.DATE: 98/03/09 NOTARIZED: | | {{#Wiki_filter:CATEGORY 1 REGULA Y INFORMATION DISTRIBUTI SYSTEM (RIDS) |
| YES DOCKET SACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION BEMIS,P.R. | | ACCESSION NBR:9803170386 DOC.DATE: 98/03/09 NOTARIZED: YES DOCKET SACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION BEMIS,P.R. 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) | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Provides mod to 971204 recpxest for amend to Licnese NPF-21, establishing interim SLMCPR for Siemens Power Corp ATRIUM-9X fuel applicable to cycle 14 only, as identified by T Huang (NRR)during 980211 site visit.DZSTR1BUTZON CODE: AOOZD COPZES RECEZVED:LTR 1 ENCL J SZEE: TITLE: OR Submittal: | | Provides mod to 971204 recpxest for amend to Licnese NPF-21, establishing interim SLMCPR for Siemens Power Corp ATRIUM-9X fuel applicable to cycle 14 only, as identified by T Huang (NRR) during 980211 site visit. |
| General Distribution NOTES: RECIPIENT ID CODE/NAME PD4-2 LA POSLUSNY,C INTERNAL: ACRS NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD4-2 PD FILE CENTER NRR DE M B NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 D U E NOTE TO ALL"RIDS" RECIPIENTS:
| | DZSTR1BUTZON CODE: AOOZD TITLE: OR COPZES RECEZVED:LTR Submittal: General Distribution 1 ENCL J SZEE: |
| PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER.OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13 | | NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 POSLUSNY,C 1 1 INTERNAL: ACRS 1 1 FILE CENTER 1 1 NRR/DE/ECGB/A 1 1 NRR DE M B 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D |
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| | NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER.OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13 |
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| WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~Richland, Washington 99352-0968 March 9, 1998 G02-98-049 Docket No.50-397 U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Gentlemen: | | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 March 9, 1998 G02-98-049 Docket No. 50-397 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen: |
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| ==Subject:== | | ==Subject:== |
| %NP-2 OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENT OF SLMCPR-MODIFICATION OF REQUEST | | %NP-2 OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENTOF SLMCPR-MODIFICATIONOF REQUEST |
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| ==Reference:== | | ==Reference:== |
| | Letter GO2-97-219 dated December 4, 1997, P.R. Bemis (Supply System) to NRC Document Control Desk, WNP-2 Operating License NPF-21 Request for Amendment: |
| | Minimum Critical Power Ratio Safety Limits The referenced letter requests a change to the WNP-2 Technical Specifications (Section 2.1.1.2) to establish an interim safety limit (SLMCPR) for Siemens Power Corporation (SPC) ATRIUM-9Xfuel applicable to cycle 14 only. Subsequent conversations with T. Huang (NRR) during his visit to WNP-2 on February 11, 1998, identified two additional text changes which should be included with the original amendment request: |
| | ~ The approved analytical methodologies listed in Technical Specification Section 5.6.5.b do not reflect the necessary support for cycle 14 specific operating limits in Technical Specification Section 5.6.5.a. Accordihgly,"the Supply" System hereby submits ah amended list of approved methodologies to update Technical Specification Section 5.6.5.b, and; |
| | ~ The wording "for all other fuel" in Technical Specification Section 2.1.1.2 should be specific regarding the fuel type. Accordingly, the Supply System has added "for the ABB SVEA-96 fuel". |
| | 'P803i7038b 98030'7 PDR ADQCK 05000397 P -" PDR llllllllllllllllllllllllllllllllllllllll |
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| Letter GO2-97-219 dated December 4, 1997, P.R.Bemis (Supply System)to NRC Document Control Desk, WNP-2 Operating License NPF-21 Request for Amendment:
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| Minimum Critical Power Ratio Safety Limits The referenced letter requests a change to the WNP-2 Technical Specifications (Section 2.1.1.2)to establish an interim safety limit (SLMCPR)for Siemens Power Corporation (SPC)ATRIUM-9X fuel applicable to cycle 14 only.Subsequent conversations with T.Huang (NRR)during his visit to WNP-2 on February 11, 1998, identified two additional text changes which should be included with the original amendment request:~The approved analytical methodologies listed in Technical Specification Section 5.6.5.b do not reflect the necessary support for cycle 14 specific operating limits in Technical Specification Section 5.6.5.a.Accordihgly,"the Supply" System hereby submits ah amended list of approved methodologies to update Technical Specification Section 5.6.5.b, and;~The wording"for all other fuel" in Technical Specification Section 2.1.1.2 should be specific regarding the fuel type.Accordingly, the Supply System has added"for the ABB SVEA-96 fuel".'P803i7038b 98030'7 PDR ADQCK 05000397 P-" PDR llllllllllllllllllllllllllllllllllllllll
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| ~"g Ai~t k 0 REQUEST FOR AME NT OF SLMCPR MODIFICATION OF UEST Page 2 Discussions with T.Huang (NRR)also identified that additional information is necessary to clarify the validity and application of SLMCPR to other than SPC ATRIUM-9X fuel.This information is to be provided to the Supply System by Asea Brown Boveri (ABB)and transmitted to the NRC under a separate cover.The changes proposed by this letter do not alter the previous conclusion of no significant hazards that were evaluated in accordance with 10CFR50.92(c) and documented in the referenced letter.The revised amendment request has also been evaluated against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10CFR51.21. | | 0 |
| The modified request continues to meet the eligibility criteria for a categorical exclusion as set forth in 10CFR51.22(b). | | |
| An environmental assessment of the change is not required.This request for modification of the pending Technical Specification amendment request has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.In accordance with 10CFR50.91, the state of Washington has been provided a copy of this letter.Should you have any questions or desire additional information regarding this matter, please contact me or P.J.Inserra at (509)377-4147.lly, resident, Nuclear Operations Mail Drop PE23 Attachments: | | REQUEST FOR AME NT OF SLMCPR MODIFICATIONOF UEST Page 2 Discussions with T. Huang (NRR) also identified that additional information is necessary to clarify the validity and application of SLMCPR to other than SPC ATRIUM-9Xfuel. This information is to be provided to the Supply System by Asea Brown Boveri (ABB) and transmitted to the NRC under a separate cover. |
| 1.Resolution to Comments-Cycle 14 Technical Specification SLMCPR Amendment 2.Marked up Technical Specification Pages 3.Revised Technical Specification Pages EW MerschoF-NRC MV KE Perkins, Jr.-NRC RIV, Walnut Creek Field Once C Poslusny, Jr.-NRR NRC Sr.Resident Inspector-927N DL Williams-BPA/399 PD Robinson-Winston&'Strawn DJ Ross-EFSEC | | The changes proposed by this letter do not alter the previous conclusion of no significant hazards that were evaluated in accordance with 10CFR50.92(c) and documented in the referenced letter. The revised amendment request has also been evaluated against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10CFR51.21. The modified request continues to meet the eligibility criteria for a categorical exclusion as set forth in 10CFR51.22(b). An environmental assessment of the change is not required. |
| ~l 5 STATE OF WASHINGTON | | This request for modification of the pending Technical Specification amendment request has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board. In accordance with 10CFR50.91, the state of Washington has been provided a copy ofthis letter. |
| ))COUNTY OF BENTON)
| | Should you have any questions or desire additional information regarding this matter, please contact me or P. J. Inserra at (509) 377-4147. |
| | lly, resident, Nuclear Operations Mail Drop PE23 Attachments: |
| | : 1. Resolution to Comments - Cycle 14 Technical Specification SLMCPR Amendment |
| | : 2. Marked up Technical Specification Pages |
| | : 3. Revised Technical Specification Pages EW MerschoF- NRC MV KE Perkins, Jr. - NRC RIV, Walnut Creek Field Once C Poslusny, Jr. - NRR NRC Sr. Resident Inspector - 927N DL Williams - BPA/399 PD Robinson - Winston &'Strawn DJ Ross - EFSEC |
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| ==Subject:== | | ==Subject:== |
| Request for Amendment of SLMCPR Modification of R u t I, P.R.BEMIS, being duly sworn, subscribe to and say that I am the Vice President Nuclear Operations for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein;that I have the full authority to execute this oath;that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true.DATE MI 5K 0, 1998 P., mis Vice President, Nuclear Operations On this date personally appeared before me P.R.Bemis, to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned. | | Request for Amendment of SLMCPR |
| GIVEN under my hand and seal this I day of 1998 No Public in and for the STATE OF WASHINGTON | | ) Modification of R u t COUNTY OF BENTON ) |
| -;Residing at My Commission Expires | | I, P. R. BEMIS, being duly sworn, subscribe to and say that I am the Vice President Nuclear Operations for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have the full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true. |
| ~Z~igy$'illl II 1))g o Q wf 0 e Qp OIL&'>>Ilrll oll>~ | | DATE MI5K 0, 1998 P., mis Vice President, Nuclear Operations On this date personally appeared before me P. R. Bemis, to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned. |
| '.REQUEST FOR AME NT MESMUM CIIITICAL ERR RATIO SASETT LMITS Attachment 1, Page 1 of 1 Resolution to Comments Cycle 14 Technical Specification SLMCPR Amendment Comment: It appears that the approved methodologies listed in Technical Specification Section 5.6.5.b do not reflect the necessary support for cycle 14 specific operating limits in Technical Specification Section 5.6.5.a.The list of the approved methodologies should be updated in a timely manner.Resolution: | | GIVEN under my hand and seal this I day of 1998 No Public in and for the STATE OF WASHINGTON |
| Reference 2-Delete letter, R.C.Jones (NRC)to R.A.Copeland (ANF),"NRC Approval of ANFB Additive Constants for ANF 9x9-9X BWR Fuel," dated November 14, 1990.This reference should be removed since the additive constants to which this reference refers were generated without foHowing the procedure outlined in Reference 1 of Technical Specification Section 5.6.5.b.Reference 4-Delete XN-NF-85-67(P)(A), Revision 1,"Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986.This reference should be removed since there are no SPC 8x8 fuel bundles in the WNP-2 core.Reference 7-Delete NEDE-24011-P-A-10-US,"General Electric Standard Application for Reactor Fuel," U.S.Supplement, March 1991.This reference should be removed since it is not being used for any of the analyses supporting the COLR.Reference 10-Delete EMF-CC-074 (P)(A),"Volume 1-STAIF-A Computer Program for BWR Stability in the Frequency Domain, Volume 2--STAIF-Computer Program for BWR Stability in the Frequency Domain, Code Qualification Report," July 1994.This reference should be removed since the code is no longer being used to set the stability regions in the COLR.Comment: The wording"for all other fuel" in Technical Specification Section 2.1.1.2 should be identified more specifically for the fuel type used.Resolution:-Added"for-the ABB SVEA-96 fuel" in place of"for all other fuel" in Technical Specification Section 2.1.1.2 amendment request. | | -;Residing at My Commission Expires |
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| | '. REQUEST FOR AME NT MESMUM CIIITICAL ERR RATIO SASETT LMITS Attachment 1, Page 1 of 1 Resolution to Comments Cycle 14 Technical Specification SLMCPR Amendment Comment: It appears that the approved methodologies listed in Technical Specification Section 5.6.5.b do not reflect the necessary support for cycle 14 specific operating limits in Technical Specification Section 5.6.5.a. The list of the approved methodologies should be updated in a timely manner. |
| | Resolution: Reference 2 - Delete letter, R.C. Jones (NRC) to R.A. Copeland (ANF), |
| | "NRC Approval of ANFB Additive Constants for ANF 9x9-9X BWR Fuel," |
| | dated November 14, 1990. This reference should be removed since the additive constants to which this reference refers were generated without foHowing the procedure outlined in Reference 1 of Technical Specification Section 5.6.5.b. |
| | Reference 4 - Delete XN-NF-85-67(P) (A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986. |
| | This reference should be removed since there are no SPC 8x8 fuel bundles in the WNP-2 core. |
| | Reference 7 - Delete NEDE-24011-P-A-10-US, "General Electric Standard Application for Reactor Fuel," U.S. Supplement, March 1991. This reference should be removed since it is not being used for any of the analyses supporting the COLR. |
| | Reference 10 - Delete EMF-CC-074 (P) (A), "Volume 1 STAIF - A Computer Program for BWR Stability in the Frequency Domain, Volume 2- |
| | - STAIF - Computer Program for BWR Stability in the Frequency Domain, Code Qualification Report," July 1994. This reference should be removed since the code is no longer being used to set the stability regions in the COLR. |
| | Comment: The wording "for all other fuel" in Technical Specification Section 2.1.1.2 should be identified more specifically for the fuel type used. |
| | Resolution: -Added "for-the ABB SVEA-96 fuel" in place of "for all other fuel" in Technical Specification Section 2.1.1.2 amendment request. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML20206U4501999-05-19019 May 1999 Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule ML20196K6961999-03-30030 March 1999 Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p) GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML20204F0261999-03-19019 March 1999 Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5911999-03-16016 March 1999 Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5901999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted ML17292B5681999-03-0101 March 1999 Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1 ML17292B5651999-02-22022 February 1999 Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint ML17292B5581999-02-0404 February 1999 Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999 1999-09-09
[Table view] |
Text
CATEGORY 1 REGULA Y INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:9803170386 DOC.DATE: 98/03/09 NOTARIZED: YES DOCKET SACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION BEMIS,P.R. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides mod to 971204 recpxest for amend to Licnese NPF-21, establishing interim SLMCPR for Siemens Power Corp ATRIUM-9X fuel applicable to cycle 14 only, as identified by T Huang (NRR) during 980211 site visit.
DZSTR1BUTZON CODE: AOOZD TITLE: OR COPZES RECEZVED:LTR Submittal: General Distribution 1 ENCL J SZEE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 POSLUSNY,C 1 1 INTERNAL: ACRS 1 1 FILE CENTER 1 1 NRR/DE/ECGB/A 1 1 NRR DE M B 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
U E
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER.OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 March 9, 1998 G02-98-049 Docket No. 50-397 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
%NP-2 OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENTOF SLMCPR-MODIFICATIONOF REQUEST
Reference:
Letter GO2-97-219 dated December 4, 1997, P.R. Bemis (Supply System) to NRC Document Control Desk, WNP-2 Operating License NPF-21 Request for Amendment:
Minimum Critical Power Ratio Safety Limits The referenced letter requests a change to the WNP-2 Technical Specifications (Section 2.1.1.2) to establish an interim safety limit (SLMCPR) for Siemens Power Corporation (SPC) ATRIUM-9Xfuel applicable to cycle 14 only. Subsequent conversations with T. Huang (NRR) during his visit to WNP-2 on February 11, 1998, identified two additional text changes which should be included with the original amendment request:
~ The approved analytical methodologies listed in Technical Specification Section 5.6.5.b do not reflect the necessary support for cycle 14 specific operating limits in Technical Specification Section 5.6.5.a. Accordihgly,"the Supply" System hereby submits ah amended list of approved methodologies to update Technical Specification Section 5.6.5.b, and;
~ The wording "for all other fuel" in Technical Specification Section 2.1.1.2 should be specific regarding the fuel type. Accordingly, the Supply System has added "for the ABB SVEA-96 fuel".
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REQUEST FOR AME NT OF SLMCPR MODIFICATIONOF UEST Page 2 Discussions with T. Huang (NRR) also identified that additional information is necessary to clarify the validity and application of SLMCPR to other than SPC ATRIUM-9Xfuel. This information is to be provided to the Supply System by Asea Brown Boveri (ABB) and transmitted to the NRC under a separate cover.
The changes proposed by this letter do not alter the previous conclusion of no significant hazards that were evaluated in accordance with 10CFR50.92(c) and documented in the referenced letter. The revised amendment request has also been evaluated against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10CFR51.21. The modified request continues to meet the eligibility criteria for a categorical exclusion as set forth in 10CFR51.22(b). An environmental assessment of the change is not required.
This request for modification of the pending Technical Specification amendment request has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board. In accordance with 10CFR50.91, the state of Washington has been provided a copy ofthis letter.
Should you have any questions or desire additional information regarding this matter, please contact me or P. J. Inserra at (509) 377-4147.
lly, resident, Nuclear Operations Mail Drop PE23 Attachments:
- 1. Resolution to Comments - Cycle 14 Technical Specification SLMCPR Amendment
- 2. Marked up Technical Specification Pages
- 3. Revised Technical Specification Pages EW MerschoF- NRC MV KE Perkins, Jr. - NRC RIV, Walnut Creek Field Once C Poslusny, Jr. - NRR NRC Sr. Resident Inspector - 927N DL Williams - BPA/399 PD Robinson - Winston &'Strawn DJ Ross - EFSEC
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STATE OF WASHINGTON )
Subject:
Request for Amendment of SLMCPR
) Modification of R u t COUNTY OF BENTON )
I, P. R. BEMIS, being duly sworn, subscribe to and say that I am the Vice President Nuclear Operations for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have the full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true.
DATE MI5K 0, 1998 P., mis Vice President, Nuclear Operations On this date personally appeared before me P. R. Bemis, to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.
GIVEN under my hand and seal this I day of 1998 No Public in and for the STATE OF WASHINGTON
-;Residing at My Commission Expires
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'. REQUEST FOR AME NT MESMUM CIIITICAL ERR RATIO SASETT LMITS Attachment 1, Page 1 of 1 Resolution to Comments Cycle 14 Technical Specification SLMCPR Amendment Comment: It appears that the approved methodologies listed in Technical Specification Section 5.6.5.b do not reflect the necessary support for cycle 14 specific operating limits in Technical Specification Section 5.6.5.a. The list of the approved methodologies should be updated in a timely manner.
Resolution: Reference 2 - Delete letter, R.C. Jones (NRC) to R.A. Copeland (ANF),
"NRC Approval of ANFB Additive Constants for ANF 9x9-9X BWR Fuel,"
dated November 14, 1990. This reference should be removed since the additive constants to which this reference refers were generated without foHowing the procedure outlined in Reference 1 of Technical Specification Section 5.6.5.b.
Reference 4 - Delete XN-NF-85-67(P) (A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986.
This reference should be removed since there are no SPC 8x8 fuel bundles in the WNP-2 core.
Reference 7 - Delete NEDE-24011-P-A-10-US, "General Electric Standard Application for Reactor Fuel," U.S. Supplement, March 1991. This reference should be removed since it is not being used for any of the analyses supporting the COLR.
Reference 10 - Delete EMF-CC-074 (P) (A), "Volume 1 STAIF - A Computer Program for BWR Stability in the Frequency Domain, Volume 2-
- STAIF - Computer Program for BWR Stability in the Frequency Domain, Code Qualification Report," July 1994. This reference should be removed since the code is no longer being used to set the stability regions in the COLR.
Comment: The wording "for all other fuel" in Technical Specification Section 2.1.1.2 should be identified more specifically for the fuel type used.
Resolution: -Added "for-the ABB SVEA-96 fuel" in place of "for all other fuel" in Technical Specification Section 2.1.1.2 amendment request.
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