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Category:EXHIBITS (DOCKETING AND SERVICES BRANCH INFORMATION
MONTHYEARL-87-424, Applicant Exhibit A-12,consisting of Util Forwarding Response to NRC 870901 Request for Addl Info Re Use of Boraflex in Rerack & Spent Fuel Pool Filter Demineralizer,Per 870612 Application for Amend to License1989-01-26026 January 1989 Applicant Exhibit A-12,consisting of Util Forwarding Response to NRC 870901 Request for Addl Info Re Use of Boraflex in Rerack & Spent Fuel Pool Filter Demineralizer,Per 870612 Application for Amend to License L-87-245, Applicant Exhibit A-11,consisting of Util Requesting Amend to License DPR-67 to Replace Spent Fuel Pool Racks to Ensure That Sufficient Future Capacity Exists. Proposed Tech Specs Encl1989-01-26026 January 1989 Applicant Exhibit A-11,consisting of Util Requesting Amend to License DPR-67 to Replace Spent Fuel Pool Racks to Ensure That Sufficient Future Capacity Exists. Proposed Tech Specs Encl ML20246N1061989-01-25025 January 1989 Applicant Exhibit A-5,consisting of Util Forwarding Results of Exam of Poison Insert Assemblies Removed from Spent Fuel Storage Racks at Point Beach Nuclear Plant ML20246M6431989-01-25025 January 1989 Staff Exhibit S-2,consisting of Environ Assessment Re Expansion of Spent Fuel Pool ML20246M6381989-01-25025 January 1989 Staff Exhibit S-1,consisting of Safety Evaluation Re Reracking of Spent Fuel Pool at Plant Per Amend 91 to License DPR-67 ML20246M5531989-01-25025 January 1989 Applicant Exhibit A-10,consisting of Diagram Illustrating Edge Gaps in Boraflex Panels ML20246M5441989-01-25025 January 1989 Applicant Exhibit A-9,consisting of 871125 Rev 1 to Technical Rept NS-1-050, Irradiation Study of Boraflex, Interim Rept ML20246M5191989-01-25025 January 1989 Applicant Exhibit A-8,consisting of Rept, Neutron Absorber Matls for Spent Fuel Racks, Presented at Joint Power Conference in Philadelphia,Pa ML20246M5081989-01-25025 January 1989 Applicant Exhibit A-7,consisting of Util Forwarding Rev 0 to NET-042-01, Preliminary Assessment of Boraflex Performance in Quad Cities Spent Fuel Storage Racks, by Northeast Technology Corp ML20246M4711989-01-25025 January 1989 Applicant Exhibit A-6,consisting of Util to NRC Forwarding Rev 1 to Spent Fuel Storage Facility Mod Sar,Per 870612 Application for Amend to License DPR-67 ML20246N0741989-01-24024 January 1989 Applicant Exhibit A-4,consisting of Technical Rept 748-30-1, Boraflex Neutron Shielding Matl Product Performance Data, ML20246N0191989-01-24024 January 1989 Applicant Exhibit A-2,consisting of Safety Evaluation Re Fuel Enrichment Increase for Grand Gulf Unit 1 ML20246N0041989-01-24024 January 1989 Applicant Exhibit A-1,consisting of EPRI Final Rept NP-6159, Assessment of Boraflex Performance in Spent Fuel Storage Racks, Dtd Dec 1988 AECM-88-0233, Applicant Exhibit A-3,consisting of Util Forwarding Response to NRC Request for Addl Info Re Boraflex Matl Contained in Racks & Associated Boraflex Monitoring Program1989-01-24024 January 1989 Applicant Exhibit A-3,consisting of Util Forwarding Response to NRC Request for Addl Info Re Boraflex Matl Contained in Racks & Associated Boraflex Monitoring Program 1989-01-26
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARL-99-201, Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors.Fpl Followed Development of NEI Comments on Rulemaking & Endorse These Comments1999-09-0707 September 1999 Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors.Fpl Followed Development of NEI Comments on Rulemaking & Endorse These Comments ML20206H4441999-05-0303 May 1999 Comment Opposing Proposed Rules 10CFR170 & 10CFR171 Re Rev of Fy 1999 Fee Schedules ML20205J0461999-04-0101 April 1999 Comment Supporting Proposed Draft Std Review Plan on Foreign Ownership,Control & Domination.Util Supports Approach Set Forth in SRP Toward Reviewing Whether Applicant for NRC License Owned by Foreign Corp.Endorses NEI Comments ML20205B3771999-03-16016 March 1999 Comment Opposing PRM 50-64 Re Liability of Joint Owners of Npps.Util Endorses Comments of NEI & Urges Commission to Deny Petition for Rulemaking ML17355A2511999-03-0909 March 1999 Comment Supporting Amend to Policy & Procedure for NRC Enforcement Actions Re Treatment of Severity Level IV Violations at Power Reactors.Util Also Endorses Comments of NEI on Revs L-98-306, Comment Opposing Proposed Rule 10CFR50 Re Requirements for Monitoring Effectiveness of Maint at NPP1998-12-10010 December 1998 Comment Opposing Proposed Rule 10CFR50 Re Requirements for Monitoring Effectiveness of Maint at NPP L-98-272, Comment on Draft Reg Guide DG-4005, Preparation of Suppl Environ Repts for Applications to Renew Nuclear Power Plant Operating Licenses1998-10-28028 October 1998 Comment on Draft Reg Guide DG-4005, Preparation of Suppl Environ Repts for Applications to Renew Nuclear Power Plant Operating Licenses L-98-252, Comment Supporting Proposed Rules 10CFR2 & 51 Re Streamlined Hearing Process for NRC Approval of License Transfers.Fpl Also Endorses Comments of NEI on Proposed Rule1998-10-0606 October 1998 Comment Supporting Proposed Rules 10CFR2 & 51 Re Streamlined Hearing Process for NRC Approval of License Transfers.Fpl Also Endorses Comments of NEI on Proposed Rule L-98-248, Comment Supporting Statement of Policy on Conduct of Adjudicatory Proceedings.Fpl Also Endorses Comments of NEI on Policy Statement1998-10-0505 October 1998 Comment Supporting Statement of Policy on Conduct of Adjudicatory Proceedings.Fpl Also Endorses Comments of NEI on Policy Statement ML17229A7551998-05-29029 May 1998 Comment Opposing Proposed Communication Re Augmented Insp of Pressurized Water Reactor Class 1 High Pressure Safety Injection Piping ML20217P6691998-04-0202 April 1998 Comment Opposing Proposed Rule 10CFR50 Re Industry Codes & Standards,Amended Requirements ML17354A8741998-03-27027 March 1998 Comment Opposing Proposed Generic Communication,Lab Testing of nuclear-grade Activated Charcoal (M97978) ML20216C1991998-03-0303 March 1998 Comment on Proposed Generic Communication Re Yr 2000 Readiness of Computer Sys at Npps.Util Endorses Nuclear Energy Inst Comments.Comments Submitted on Behalf of Plant ML17354B1061998-02-26026 February 1998 Submits Listed Requests for NRC EA Per 10CFR2.206 to Modify OLs for All FPL NPPs Until Licensee Can Demonstrate Open Communication Channels Exist Between NRC & Licensee.Also Requests EA to Address Alleged Discriminatory Practices L-97-269, Comment on Pr 10CFR55, Initial Licensed Operator Exam Requirements1997-10-21021 October 1997 Comment on Pr 10CFR55, Initial Licensed Operator Exam Requirements L-97-265, Comment on Proposed Rules 10CFR50 & 73, Frequency of Reviews & Audits for Emergency Prepardness Programs Safeguards Contingency Plan & Security Programs for Np Reactors1997-10-14014 October 1997 Comment on Proposed Rules 10CFR50 & 73, Frequency of Reviews & Audits for Emergency Prepardness Programs Safeguards Contingency Plan & Security Programs for Np Reactors ML20217M0751997-08-13013 August 1997 Licensee Response to Supplemental 10CFR2.206 Petitions Filed by Tj Saporito & National Litigation Consultants.Petition Provides No Basis for Extraordinary Relief Requested. Petition Should Be Denied.W/Certificate of Svc ML17354A5181997-05-27027 May 1997 Licensee Response to 10CFR2.206 Petition Filed by Tj Saporito & National Litigation Consultants.Petition Should Be Denied,Based on Listed Info.W/Certificate of Svc ML17354A5631997-05-17017 May 1997 Second Suppl to 970423 Petition Requesting Enforcement Against Listed Util Employees by Imposing Civil Penalties, Restricting Employees from Licensed Activities & Revoking Unescorted Access ML17354A5611997-05-11011 May 1997 Suppl to 970423 Petition Requesting Enforcement Action Against Util Former Executive Vice President,Site Vice President & Maint Superintendent by Imposing Civil Monetary Penalty ML17354A5651997-04-23023 April 1997 Requests That NRC Take EA to Modify,Suspend or Revoke FPL Operating Licenses for All Four Nuclear Reactors Until Licensee Can Sufficiently Demonstrate to NRC & Public That Employees Encouraged to Freely Raise Safety Concerns ML20137R4681996-12-10010 December 1996 Transcript of 961210 Proceeding in Atlanta,Ga Re Predecisional EC Re Facility Activities.Pp 1-151.Supporting Documentation Encl L-96-137, Comments on Proposed Rule 10CFR50, Reliability & Availability Info for Risk-Significant Sys & Equipment1996-06-0606 June 1996 Comments on Proposed Rule 10CFR50, Reliability & Availability Info for Risk-Significant Sys & Equipment IR 05000335/19960031996-03-0808 March 1996 Transcript of 960308 Hearing in Atlanta,Ga Re NRC Insp Repts 50-335/96-03 & 50-389/96-03.Pp 1-101.Supporting Documentation Encl ML17228B3551995-12-0404 December 1995 Comment Opposing Proposed Generic Communication, Boraflex Degradation in SFP Storage Racks. L-95-270, Comment Supporting Proposed Rules 10CFR2,50 & 51 Re Decommission of NPPs1995-10-15015 October 1995 Comment Supporting Proposed Rules 10CFR2,50 & 51 Re Decommission of NPPs ML17228B2841995-09-12012 September 1995 Comment Supporting Rg DG-1043,Rev 2 to Rg 1.49, NPP Simulation Facilities for Use in Operator License Exams. ML17228B2221995-07-13013 July 1995 Comment Supporting Proposed Generic Communication 10CFR50.54 Re Process for Changes to Security Plans W/O Prior NRC Approval L-95-199, Comment Supporting Proposed Rule 10CFR50 Re Changes in Frequency Requirements for Emergency Planning & Preparedness Exercises from Annual to Biennial1995-07-10010 July 1995 Comment Supporting Proposed Rule 10CFR50 Re Changes in Frequency Requirements for Emergency Planning & Preparedness Exercises from Annual to Biennial ML17353A2471995-06-27027 June 1995 Comments on Proposed Rule Re, Review of NRC Insp Rept Content,Format & Style. ML17228B2101995-06-27027 June 1995 Comment Opposing Proposed GL Relocation of Pressure Temp Limit Curves & Low Temp Overpressure Protection Sys Limits. ML20134N0421995-01-18018 January 1995 Partially Deleted Transcript of Interview W/J Kunkel on 950118 at Jensen Beach,Fl.Pp 1-40 ML20134N0621995-01-18018 January 1995 Partially Deleted Transcript of Interview W/A De Soiza on 950118 at Jensen Beach,Fl.Pp 1-40.Supporting Documentation Encl ML20134N0281995-01-18018 January 1995 Partially Deleted Transcript of Interview W/Eo Poarch on 950118 at Jensen Beach,Fl.Pp 1-78 ML20134N0331995-01-18018 January 1995 Partially Deleted Transcript of Interview W/D Jacobs on 960118 in Jensen Beach,Fl.Pp 1-50 ML20134N0301995-01-18018 January 1995 Partially Deleted Transcript of Interview W/H Fagley on 950118 at Jensen Beach,Fl.Pp 1-63 ML17228A9851995-01-17017 January 1995 Comment Supporting Proposal to Issue GL Providing Guidance for Determining When analog-to-digital Replacement Can Be Performed Under Requirements of 10CFR50.59 L-94-325, Comment on Proposed Rule 10CFR50 Re Fracture Toughness Requirements for LWR Pressure Vessels.Endorses NEI Comments & Recommendations1994-12-29029 December 1994 Comment on Proposed Rule 10CFR50 Re Fracture Toughness Requirements for LWR Pressure Vessels.Endorses NEI Comments & Recommendations L-94-329, Comment Supporting Proposed Rule 10CFR2 Re Policy Statement Rev, Policy & Procedure for Enforcement Actions; Policy Statement,Discrimination1994-12-22022 December 1994 Comment Supporting Proposed Rule 10CFR2 Re Policy Statement Rev, Policy & Procedure for Enforcement Actions; Policy Statement,Discrimination L-94-304, Comment Supporting Proposed GL Re Reconsideration of Nuclear Power Plant Security Requirements for Internal Threat1994-12-0202 December 1994 Comment Supporting Proposed GL Re Reconsideration of Nuclear Power Plant Security Requirements for Internal Threat ML17228A8751994-10-0303 October 1994 Comment Opposing Proposed Rule Re Pilot Program for NRC Recognition of Good Performance by Nuclear Power Plants ML20072S5221994-08-25025 August 1994 Comment Opposing Petition for Rulemaking 9-2 Re Request for NRC to Revise Regulations of 10CFR9 to Provide Public Access to Info Held by Licensees But Not Submitted to NRC L-94-206, Comment Opposing Proposed Change to Rule 10CFR26, Consideration of Changes to Fitness for Duty Requirements. Util Wants Current Scope of Drug Testing in 10CFR26 to Be Retained & Current Trustworthiness Programs to Be Improved1994-08-0909 August 1994 Comment Opposing Proposed Change to Rule 10CFR26, Consideration of Changes to Fitness for Duty Requirements. Util Wants Current Scope of Drug Testing in 10CFR26 to Be Retained & Current Trustworthiness Programs to Be Improved ML20072B3251994-08-0101 August 1994 Comment Opposing Proposed Rule 10CFR26 Re Change Consideration of fitness-for-duty Requirements L-94-150, Comment Supporting Petition for Rulemaking PRM-50-60 Re Amend to 10CFR50.54 by Changing Frequency W/Which Licensees Conduct Independent Reviews of Emergency Preparedness Program from Annually to Biennially1994-06-17017 June 1994 Comment Supporting Petition for Rulemaking PRM-50-60 Re Amend to 10CFR50.54 by Changing Frequency W/Which Licensees Conduct Independent Reviews of Emergency Preparedness Program from Annually to Biennially ML17228A3121993-09-24024 September 1993 Answer of Florida Municipal Power Agency to FPL Response in Opposition to Petition for Enforcement Action. W/Vols I & II of Apps ML17228A2981993-08-27027 August 1993 Response of Florida Power & Light Co in Opposition to Petition for Enforcement Action. ML17309A7141993-07-0202 July 1993 Petition of Florida Municipal Power Agency for Declaration & Enforcement...Antitrust Licensing Conditions & to Impose Requirements by Order. W/Vols I & II of Apps to Petition ML20045F2091993-06-24024 June 1993 Comment on Proposal Re Radiological Criteria for Decommissioning NRC-licensed Facilities.Supports Proposed Criteria ML17349A8161993-04-22022 April 1993 Comment Endorsing NUMARC Comments Re Proposed Generic Communication, Availability & Adequacy of Design Bases Info. 1999-09-07
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[.p. S f RESOUNCEE,NC.
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/g g[9j,Ey' m o ctsa .n November 21, 1988 U$ tenng '89 11AR 22 P6 :55 "
S. Nuclear R gulatory Comission ,;;
00 0
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Uc l
Mail Station P1-137 20555 Washington, D. C.
Attention: Document Control Desk Gentlemen:
SUBJECT:
Grand Gulf Nuclear 5tation ) )
Unit 1 i !
Docket No. 50-416 License No. NPF-29 Request for Additional Information 1 Criticality Analysis for Cycle 4 '
AECM-88/0233 l
15,1988(AECM-88/0206and 27, 1988 and November By letters dated October,SystemEnergyResources,Inc.(SERI)requestedtheNRC 0228 respectively)lity analysis for Cycle 4 fuel to be stored in the Grand Gulf j.
review Nuclear the Station, critica Unit 1 spent fuel pool storage racks prior to loading in t\
reactor. .
j Based on its review, the NRC Staff requested additional infomation l; dated November 8, 1988) regarding the Boraflex material SERI's (MAEC-88/0336, )
contained in the racks and the associated Boraflex monitoring program.
response to the NRC request for additional information is attached.
If you have additional questions please advise.
Yours truly,
% J A 0( .
b k- ,I JGC:swb Attachment ,
cc: (Seenextpage) 5 0 00$ $ ,
l P O BDx 23CM l Jacx5oN MGS$m y?22530M l (601)064WD l ^ " " " * *
1 AECM-88/0233
. Page 2 r.
1m c'c : Mr. W. T. Cottle (w/a)
Mr.T.H.Cloninger(w/a) .
Mr.
Mr, N.R.
S. B. McGehee Reynolds (w/a (w/a))
Mr. H. L. Thomas (w/o)(w/a)
Mr. H. O'. Christensen Mr. Malcolm L. Ernst (w/a)
Acting Regional Administrator U. S. Nuclear Regulatory Comission k
Region II101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 ;
.l Mr. L. L. Kintner, Project Manager (w/a) j l
Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 14B20 Washington, D.C. 20555 I i
O e I
M e
J22AECMB8111801 - 2
. _ _ ""^^-'----,_.c_
Attachment to
'.- AECM-88/0233
- Response to NRC Question Regarding GGNS Boraflex Gap Surveillance Program i
Introduction; *'
l As described in NRC Infomation Notice No. 87-43, Commonwealth Edison Company ,
(CECO) has observed gaps in the neutron-absorbing material used in the QuadT Cities high-density spent fuel storage racks.The neutron-absorbing material is a i by the Joseph Oat Corporation (OAT).
boron carbide dispersion in an elastomeric silicone matrix which is manufactured by Bisco Products, Inc. (BISCO) under the trade name Boraflex.
l On May 5, 1987, CECO presented to the NRC under Dockets No. 50-254 and 50 the results of measurements and criticality analysis relating to the observed j presence racks.
of gaps in Boraflex panels used in the Quad. Citie i the degradation of Boraflex as reported in the November 1988 presentation of the draft report RP-2813-4 to EPRI Boraflex working group member utilities. l Gap Formation As described in these reports, the formation of gaps is postulated to be caused by radiation inducedWhen shrinkage in the Boraflex panels due to crosslinking .in this shrinkage occurs in the presence of some.
the Boraflex polymer.
structural element (s) which restrict the shrinkage, local stress accum until the panel tears. l density spent fuel racks manufactured by OAT such as those installed at Quad Cities and GGNS.
Gap Measurements l
In response to NRC Information Notice 87-43, tests for the presence of gaps in the GGNS spent fuel racks were conducted during August, 1988.
l The test apparatus consisted of a Californium-252 neutron source and 4 sets of Boron tri-Flouride thermal neutron detectors enclosed in a specially designed logging tool. The detectors are shielded from the fast neutron.s produced by the Ca-252 source but detect any thermal neutrons which will be reflected A set cf from
~ four adjacent storage rack cells if gaps in the Boraflex areto present. de Boraflex panels at once. This This design minimizes uncertainties with respt the elevation of gaps. device is lowered into the storage' rack cea to be .
This tested and slowly moved up the channel at approximately 1 foot / minute. i process allows detection of gaps greater than 1/2 inch, '
The results of this test were provided to SERI in October,1988. -The testsThese were performed on 101 storage rack cells (total of 404 Boraflex panels).
cell locations have typical radiation histories for the GGNS spent fuel storage No ,
racks. Of these, 48 had not previously been used to store irradiated fuel. i In the irradiated cells 87 gaps gaps were found in the unirradiated cells. The were observed in 85 ' panels with 127 panels showing no evidence of gaps.
average gap size was approximately 0.8 inch, with a maximum gap size of 1.4 J14 MISC 88111802 - 1
i V' Attachment to AECM-88/0233 i
Gap Impact Assessment 3-D KEN 0 models were developed to assess the impact of the. observed gaps on the spent fuel rack criticality analysis. These models included gaps in the mid-plane of all Boraflex panels. equal to the maximum observed gap size plus the associated measurement uncertainty. An infinite number of cells, in this ..
configuration, was assumed to be present in the radial direction. This is a very conservative treatment since the GGNS and Quad Cities measurements indicate that the gaps are essentially randomly distributed except for a slight bias towards the mid-plane. No storage cells in the GGNS racks were observed to have 4 gaps in the same plane.
I Results of analyses using the .3-D KENO models demonstrated that if the presence of the maximum observed gap size had been explicitly accounted for in'the Cycle l
4 spent fuel criticality analyses [SERI letters to NRC serial AECM-88/0206 and ,
l AECM-88/0228], the reported reactivity would not have increased. An analysis
' of a 3 inch gap in the mid-plane of all Boraflex panels demonstrated significant margin to the 0.95 k-effective acceptance criteria. Additionally, if a more realistic treatment of the distribution of gap sizes and locations had been included, gaps substantially larger than those observed would not result in an increase in the reported rack reactivity. . Since the fomation and' growth of gaps is slow, no imediate concern for the integrity of the GGNS racks exists.
However, the potential for continued growth and gap fomation exists. In order to assess the long term impact of.the degradation of the Boraflex panels upon spent fuel rack criticality, a detailed evaluation of the available industry data is currently in progress. The objective of this evaluation is to establish a maximum credible gap size and distribution for the GGNS racks. In conjunction with this assessment, a more detailed criticality analysis is underway in order to determine the long tem impact of the femation of gaps on the criticality of the spent fuel racks at GGNS. These analyses are currently scheduled for completion on or about February 15, 1988.
Surface Degradation In July of 1986, Wisconsin Electric Company, the licensee of Point Beach 1 and 2 reported significant degradation in test coupons of Boraflex material.
As reported in NRC Information Notice 87-43, subsequent examination of full length panels disclosed 1-2 percent of the surface showed a gray discoloration at the edges. No evidence of this degradation has been observed in the GGNS test coupons. ,
Ponitorinr: program Since little industry data is available concerning the fomation of gaps in the Boraflex for 0AT racks, SERI intends to continue monitoring the GGNS spent fuel racks until gap sizes and the distribution of gaps are no longer ;
significantly changing. The monitoring will use methods equivalent to those .
previously described. Due to the observed slow formation and growth of these gaps, one set of measurements each cycle is considered adequate.
i J14 MISC 88111802 - 2 i
v Attachment to
! AECM-88/0233 1
The Approximately 50 storage rack cells are planned for monitoring each cycle.
cells will be loaded with discharged fuel during each refueling outage. After significant additional irradiation, the fuel in the specified cells will be moved and ajditional measurements will be performed. This process will maximize th'e formation of gaps. This process will provide an early indication ..
of any sign'ificant changes in the behavior of the Boraflex and a confirmation of any assumptions used in the criticality analyses.
The Boraflex coupon surveillance program described in the original licensing basis for the racks (SERI letter to NRC serial AECM-85/0143) will continue and provide ,
a basis-to monitor for the possible surface degradation of the panels. 1 Summary While the presence of small gaps in the GGNS spent fuel rack Boraflex has been- '
detected, they have no impact upon the criticality safety analysis currently under review by the NRC Staff. Since larger gaps have been observed at other ,
l sites, a detailed assessment of the long term impact is on schedule for-completion in February, 1989. In order to assure that the. basis for this . l assessment remains valid, periodic measurements of the specified storage rack cells will be performed until gap sizes and the gap locations are no longer significantly changing.
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l 1
1 0
J14 MISC 88111802 - 3
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