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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20211D1321999-08-20020 August 1999 Application for Amend to License DPR-50 to Revise TS Bases Re Degraded Undervoltage Relay Setpoint Calibration Frequency & Degraded Voltage Relay Tolerance Rev ML20210J0941999-07-29029 July 1999 Suppl TS Change Request 274 to License DPR-50,revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance Tss,As Result of NRC Generic Concerns Re CR Habitability Issues ML20196K5901999-06-29029 June 1999 LAR 285 for License DPR-50,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls Can Continue to Be Moved ML20209C0551999-06-29029 June 1999 LAR 77 for License DPR-73,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matl May Continue to Be Moved ML20195E3341999-06-0404 June 1999 TS Change Request 265 to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20209B5891999-05-26026 May 1999 LAR 281 to License DPR-50,revising TMI-1 UFSAR Chapters 5 & 14 to Permit Use of Conservative Deterministic Failure Margin Methodology for Seismic Analysis of Portions of Auxiliary Steam Line.Rept 240046-R-001 Encl.Rept Withheld ML20206R1111999-05-13013 May 1999 Application for Amend to License DPR-50,requesting That License Sections 2.a.(3) & 2.c.(7) & TS Section 3.1.1 Be Revised to Incorporate Administrative Updating & Changes to Bases Statement ML20205H0691999-04-0101 April 1999 TS Change Request 262 to License DPR-50,revising TS by Adding LCO Action Statements & Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0421999-02-0202 February 1999 TS Change Request 274 to License DPR-50,expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems ML20196G4401998-12-0303 December 1998 LAR 278 to License DPR-50,requesting Consent to Transfer & Authorize Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License.Supporting Documentation,Encl ML20196H9751998-12-0303 December 1998 LAR 279 to License DPR-50,reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G7671998-11-25025 November 1998 TS Change Request 277 to License DPR-50,changing Surveillance Specs for OTSG ISIs for TMI-1 Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only ML20154Q6201998-10-19019 October 1998 TS Change Request 248 to License DPR-50,adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18, Remote Shutdown Sys ML20154P8441998-10-19019 October 1998 Application for Amend to License DPR-50,providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage.Proprietary & non- Proprietary Calculation,Encl.Proprietary Info Withheld ML20154M3691998-10-15015 October 1998 Application for Amend to License Amend Request 276 to License DPR-50 Revising UFSAR Chapter 14 Accident Analysis Atmospheric Dispersion Factors.Ufsar Revised Pages Encl ML20249B2391998-06-11011 June 1998 TS Change Request 273 to License DPR-50,incorporating Alternate High Radiation Area Control Consistent W/Reg Guide 8.38 ML20217E5131998-03-23023 March 1998 Application for Amend to License DPR-50,revising TS Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 Efpy.Request Also Submitted in Response to NRC ML20217G0161997-10-0303 October 1997 Suppl to License Amend Request 268 to License DPR-50, Replacing Pages 4-80 & 4-81 Previously Submitted w/TMI-1 License Amend Request 268 on 970812 ML20211C3211997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re License Amend Request 269 Submitted on 970814.Suppl Includes Addl Change to TS Section 3.1.4 & Proposed Page Rev Clarifying That UFSAR Analysis Is More Conservative ML20211C2221997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re TS Change Request 266.Supplement Provides for Phased Review & Issuance of License Amends & Involves Administrative Correction to TS Decay Heat Removal Sys Leakage Rate ML20210J9951997-08-14014 August 1997 Revised License Amend Request 269 for License DPR-50, Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J3981997-08-12012 August 1997 Tech Spec Change Request 268 for License DPR-50,revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operations ML20198E7871997-07-30030 July 1997 TS Change Request 266 to License DPR-50,incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 ML20141E1311997-05-0808 May 1997 Application for Amend to License DPR-50,consisting of Change Request 264,incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2351997-04-21021 April 1997 Application for Amend to License DPR-50,requesting Rev to TS 3.3 Re Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Systems ML20134M1111997-02-0707 February 1997 Application for Amend to License DPR-50,incorporating Certain Improvements from Revised STS for B&W Plants, NUREG-1430 & Addl Changes as Described in Encl TS ML20133D2651996-12-24024 December 1996 Application for Amend to License DPR-50,requesting Reinstatement of Auxiliary & Fuel Handling Bldg Ventilation Sys TS ML20132F3221996-12-16016 December 1996 Application for Amend to License DPR-50,consisting of Change Request 260,reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135C5201996-12-0202 December 1996 TS Change Request (Tscr) 75 to License DPR-73,relocating Audit Frequency Requirements to Pdms QA Plan ML20117H0181996-08-29029 August 1996 Application for Amend to License DPR-50,consisting of TS Change Request 257,incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1901996-06-28028 June 1996 Application for Amend to License DPR-50,consisting of Change Request 259,allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8751996-05-24024 May 1996 Errata to Application for Amend to License DPR-50,consisting of TS Change Request 243,replacing Pages for App a ML20101R1361996-04-10010 April 1996 Application for Amend to License DPR-50,consisting of Change Request 243,revising Addl Group of Surveillances in Which Justification Has Been Completed Following Receipt of 930623 Application ML20100J6831996-02-22022 February 1996 Application for Amend to License DPR-50,consisting of Change Request 254,revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Station Battery Cell Parameters Not Met ML20095J2261995-12-21021 December 1995 Revised TS Change Request 254,raising Low Voltage Action Level to 105 Volts DC ML20091L2831995-08-23023 August 1995 Rev to TS Change Request 223 to License DPR-50,incorporating Ref to 10CFR20.1302 ML20087F4881995-08-11011 August 1995 Rev to TS Change Request 252 to License DPR-50,removing TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements.Certificate of Svc Encl ML20086R3001995-07-24024 July 1995 Rev to LAR 250 to License DPR-50,clarifying Section III, SE Justifying Change for source-range Nuclear Instrumentation SRs ML20085N1551995-06-22022 June 1995 TS Change Request 227 to License DPR-50,replacing Pages for App A.Certificate of Svc Encl ML20084N3461995-06-0101 June 1995 TS Change Request 223 to License DPR-50,deleting Remaining Portions of RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084L4201995-06-0101 June 1995 TS Change Request 251 to DPR-50,revising TS 5.3.1.1 to Describe Use of Advanced Clad Assemblies ML20084B3261995-05-24024 May 1995 Application for Amend to License DPR-50.Amend Would Change Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7771995-05-17017 May 1995 Application for Amend to License DPR-50,consisting of Change Request 252,removing Chemical Addition Sys Requirements from TS to COLR ML20079A7771994-12-23023 December 1994 Rev to TS Change Request 221 to License DPR-50,revising TS Page 3-32a ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20069A6731994-05-20020 May 1994 TS Change Request 244 to License DPR-50,requesting Revised CR Trip Insertion Time Testing Acceptance Criterion for Remainder of Cycle 10 for 12 Specific CRs Which Initially Experienced Slow Rod Drop Times During Testing on 940317 ML20065M6681994-04-19019 April 1994 TS Change Request 237 to License DPR-50,deleting Audit Program Frequency Requirements from TS & Relocating Subj Requirements to Operational QA Plan ML20065K0381994-04-11011 April 1994 TS Change Request 238 to License DPR-50,relocating Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR ML20073C7701994-03-22022 March 1994 Application for Amend to License DPR-50 Re TS Change Request 242 Concerning Control Rod Trip Insertion Time Testing ML20064J3771994-03-11011 March 1994 Application for Amend to License DPR-50,revising TS Re Allowable Outage Time for Emergency Feedwater Pumps During Surveillance Activities 1999-08-20
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211D1321999-08-20020 August 1999 Application for Amend to License DPR-50 to Revise TS Bases Re Degraded Undervoltage Relay Setpoint Calibration Frequency & Degraded Voltage Relay Tolerance Rev ML20210J0941999-07-29029 July 1999 Suppl TS Change Request 274 to License DPR-50,revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance Tss,As Result of NRC Generic Concerns Re CR Habitability Issues ML20209D6651999-07-0808 July 1999 Corrected TS Pages 3-21,4-5a,4-9,4-38 & 6-3 to Amends 211 & 212 to License DPR-50.Pages Failed to Reflect Previously Approved Changes Granted in Amends 203 & 204 in Case of Amend 211 & 207 in Case of Amend 212 ML20196K5901999-06-29029 June 1999 LAR 285 for License DPR-50,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls Can Continue to Be Moved ML20209C0551999-06-29029 June 1999 LAR 77 for License DPR-73,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matl May Continue to Be Moved ML20195E3341999-06-0404 June 1999 TS Change Request 265 to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20209B5891999-05-26026 May 1999 LAR 281 to License DPR-50,revising TMI-1 UFSAR Chapters 5 & 14 to Permit Use of Conservative Deterministic Failure Margin Methodology for Seismic Analysis of Portions of Auxiliary Steam Line.Rept 240046-R-001 Encl.Rept Withheld ML20206R1111999-05-13013 May 1999 Application for Amend to License DPR-50,requesting That License Sections 2.a.(3) & 2.c.(7) & TS Section 3.1.1 Be Revised to Incorporate Administrative Updating & Changes to Bases Statement ML20205H0691999-04-0101 April 1999 TS Change Request 262 to License DPR-50,revising TS by Adding LCO Action Statements & Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0421999-02-0202 February 1999 TS Change Request 274 to License DPR-50,expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems ML20196H9751998-12-0303 December 1998 LAR 279 to License DPR-50,reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4401998-12-0303 December 1998 LAR 278 to License DPR-50,requesting Consent to Transfer & Authorize Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License.Supporting Documentation,Encl ML20196G7671998-11-25025 November 1998 TS Change Request 277 to License DPR-50,changing Surveillance Specs for OTSG ISIs for TMI-1 Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only ML20195C6811998-11-12012 November 1998 Amend 52 to License DPR-73,relocating Audit Frequency Requirements from TMI-2 to TMI-2 Post Defueling Monitored Storage QA Plan & Extends Max Allowed Interval Between Certain Audits from 12 Months to 24 Months ML20154P8441998-10-19019 October 1998 Application for Amend to License DPR-50,providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage.Proprietary & non- Proprietary Calculation,Encl.Proprietary Info Withheld ML20154Q6201998-10-19019 October 1998 TS Change Request 248 to License DPR-50,adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18, Remote Shutdown Sys ML20154M3691998-10-15015 October 1998 Application for Amend to License Amend Request 276 to License DPR-50 Revising UFSAR Chapter 14 Accident Analysis Atmospheric Dispersion Factors.Ufsar Revised Pages Encl ML20249B2391998-06-11011 June 1998 TS Change Request 273 to License DPR-50,incorporating Alternate High Radiation Area Control Consistent W/Reg Guide 8.38 ML20217E5131998-03-23023 March 1998 Application for Amend to License DPR-50,revising TS Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 Efpy.Request Also Submitted in Response to NRC ML20217G0161997-10-0303 October 1997 Suppl to License Amend Request 268 to License DPR-50, Replacing Pages 4-80 & 4-81 Previously Submitted w/TMI-1 License Amend Request 268 on 970812 ML20211C2221997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re TS Change Request 266.Supplement Provides for Phased Review & Issuance of License Amends & Involves Administrative Correction to TS Decay Heat Removal Sys Leakage Rate ML20211C3211997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re License Amend Request 269 Submitted on 970814.Suppl Includes Addl Change to TS Section 3.1.4 & Proposed Page Rev Clarifying That UFSAR Analysis Is More Conservative ML20210J9951997-08-14014 August 1997 Revised License Amend Request 269 for License DPR-50, Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J3981997-08-12012 August 1997 Tech Spec Change Request 268 for License DPR-50,revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operations ML20198E7871997-07-30030 July 1997 TS Change Request 266 to License DPR-50,incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 ML20141E1311997-05-0808 May 1997 Application for Amend to License DPR-50,consisting of Change Request 264,incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2351997-04-21021 April 1997 Application for Amend to License DPR-50,requesting Rev to TS 3.3 Re Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Systems ML20134M1111997-02-0707 February 1997 Application for Amend to License DPR-50,incorporating Certain Improvements from Revised STS for B&W Plants, NUREG-1430 & Addl Changes as Described in Encl TS ML20133D2651996-12-24024 December 1996 Application for Amend to License DPR-50,requesting Reinstatement of Auxiliary & Fuel Handling Bldg Ventilation Sys TS ML20132F3221996-12-16016 December 1996 Application for Amend to License DPR-50,consisting of Change Request 260,reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135C5201996-12-0202 December 1996 TS Change Request (Tscr) 75 to License DPR-73,relocating Audit Frequency Requirements to Pdms QA Plan ML20134D7761996-10-24024 October 1996 Amend 51 to License DPR-73,revising TS to Extend Surveillance Interval for Demonstrating Operability of Containment Airlock ML20128K1831996-10-0808 October 1996 Amend 50 to License DPR-73,revising TS to Incorporate Improvement from Administrative Controls Section of Revised STS for B&W Plants ML20117H0181996-08-29029 August 1996 Application for Amend to License DPR-50,consisting of TS Change Request 257,incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1901996-06-28028 June 1996 Application for Amend to License DPR-50,consisting of Change Request 259,allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8751996-05-24024 May 1996 Errata to Application for Amend to License DPR-50,consisting of TS Change Request 243,replacing Pages for App a ML20101R1361996-04-10010 April 1996 Application for Amend to License DPR-50,consisting of Change Request 243,revising Addl Group of Surveillances in Which Justification Has Been Completed Following Receipt of 930623 Application ML20100J6831996-02-22022 February 1996 Application for Amend to License DPR-50,consisting of Change Request 254,revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Station Battery Cell Parameters Not Met ML20095J2261995-12-21021 December 1995 Revised TS Change Request 254,raising Low Voltage Action Level to 105 Volts DC ML20091L2831995-08-23023 August 1995 Rev to TS Change Request 223 to License DPR-50,incorporating Ref to 10CFR20.1302 ML20087F4881995-08-11011 August 1995 Rev to TS Change Request 252 to License DPR-50,removing TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements.Certificate of Svc Encl ML20086R3001995-07-24024 July 1995 Rev to LAR 250 to License DPR-50,clarifying Section III, SE Justifying Change for source-range Nuclear Instrumentation SRs ML20085N1551995-06-22022 June 1995 TS Change Request 227 to License DPR-50,replacing Pages for App A.Certificate of Svc Encl ML20084N3461995-06-0101 June 1995 TS Change Request 223 to License DPR-50,deleting Remaining Portions of RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084L4201995-06-0101 June 1995 TS Change Request 251 to DPR-50,revising TS 5.3.1.1 to Describe Use of Advanced Clad Assemblies ML20084B3261995-05-24024 May 1995 Application for Amend to License DPR-50.Amend Would Change Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7771995-05-17017 May 1995 Application for Amend to License DPR-50,consisting of Change Request 252,removing Chemical Addition Sys Requirements from TS to COLR ML20079A7771994-12-23023 December 1994 Rev to TS Change Request 221 to License DPR-50,revising TS Page 3-32a ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20069A6731994-05-20020 May 1994 TS Change Request 244 to License DPR-50,requesting Revised CR Trip Insertion Time Testing Acceptance Criterion for Remainder of Cycle 10 for 12 Specific CRs Which Initially Experienced Slow Rod Drop Times During Testing on 940317 1999-08-20
[Table view] |
Text
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4 GPU Nuclear Ngg gf 100 Interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:
(201) 263-6500 July 18,1983 5211-83-207 Office of Nuclear Reactor Regulation Attn: Harold A. Denton, Director U. S. Nuc1 car of Regulatory Commission W a shington, D. C. 20555
Dear Sir:
Three Nile Island Nuclear Station, Unit 1 (THI-1)
Operating License No. DPR-50 Docket No. 50-289 Our letter 15211-83-149 of May 9,1983, submitted Technical Specification Change Regrscst No.125, which would permit the operation of TMI-1 following repair of the steam generators by any method other than plugging, provided that the repair methods are shown to be acceptabic by analysis and approved by the NRC. The letter also requested approval under the provisions of the changed Technical Specification of the precritical non-nuclear heat-up of the plant for testing and the subsequent plant operation using repaired steam generators. The method of repair and supporting documentation were submitted to you in the past.
In his letter of July 13, 1983, H. Dicckamp suggested that the NRC consider the approval of the steam generator repair in two stages: the first being approval of the use of repaired steam generators for precritical non-nuclear hot functional testing, and the second being the ultimate full approval.
Such an approval process would permit GPUN to proceed with its test program in a timely fashion, while at the same time, permitting NRC to defer a decision on return to service of the OTSG's until the results of stcom generator hot testing have been reviewed.
The original Evaluation of Significant Hazards Considerations submitted with the May 9,1983, request for approval and its supporting documents is val,id for both precritical non-nuclear hot functional testing and subsequent operation. GPUN considers the conclusions drawn to be applicable to-both steps of the staged licensing process. Attachment A summarizes the informa-tion previously submitted as it relates to the no significant hazards determination.
G307220485 830718 M lk PDR ADOCK 05000289 '
P PDR
( \
I GPU Nuclear is a part of the General Public Utilities System
cm.
H:rold'A. Denton, Director July 18,1983 Page Two In addition, in our meeting with your Staff on July 13, 1983, we were asked for information on current plant conditions that could be used to evaluate the potential consequences of an accident occurring during the prectitical
- test period. Attachment B summarizes these further considerations applicable
. to the precritical hot functional test period, and are in addition to the items in Attachment A. The low core decay heat (less than 150 kw) after Ecur
_ years s uh tdown and refueling, _ the lack of significant amounts of volatile .
fission products, and the absence of need for the steam generators to provide core cooling render the ' hazards for precritical operation orders of magnitude less than the FSAR approved analysis.
Wo hope that the additiora1 information provided will be useful in your review.
Sincerely, y* -
AC/ v
. P. R. Clark Executive Vice President al cc: H. Silver J. Stolz 1 J. VanVliet - l l
l l
I L
- g. 1 ATTACHMENT A Evaluation of Significant Hazards Considerations, Plant Operational In order to con'clude that a proposed change does not involve a significant hazards consideration, it is necessary to demonstrate the following:
A. There is no increase in the piobability or consequences of an accident previously evaluated.
B. The change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
C. The change does not involve a reduction in a margin of safety.
Each of these three items is addressed individually below.
A. The following support the conclusion that there is no increase in the probability or consequencesLof an accident previously evaluated.
- 1. We have sufficient understanding of the f ailure mechanism to assure safe operation and to prevent its recurrence.
- The failure scenario postulated in the failure anlayses is consistent with all the observed features of the cracking phenomenon, the timing of the cracking, the results of metallurgical examinations of tubing taken from the OTSGs and of corrosion tests performed in the laboratory.
- Corrosion tests show that the presence of an active i sulfur species is necessary for crack initiation or l propagation. Long term corrosion testing with OTSG tubing leading actual plant operation simulating typical operating conditions shows no growth or initiation of cracks.
Eddy current testing shows that cracks have not been continuing to initiate or propagate.
The sodium thiosulfate tank has been physically removed from the system.
Sulfur is now monitored and conservative limits have been placed on its concentration.
Strict c'ontrols have been implemented on potential
! sources of chemical contamination.
- As much sulfur as possible is being removed from the RCS by chemical cleaning.
- The presence of lithiun has been shown in the laboratory to inhibit crack initiation and propagation; minimum lithium I concentration limits have been implemented.
i f
p
- a Thus, we have concluded that there is not an increased probability of an accident occurring due to new damage.
- 2. Our inspection techniques have ber adequate to find and characterize relevant damage in the steam generators, the remainder of the RCS, and in supporting systems.
Representative samples of the materials and environments in the RCS and supporting systems were inspected.
- Additional inspections were performed for materials and environments of demonstrated or suspected increased susceptibility.
- Any damaged components identified were repaired or replaced.
All of the steam generator tubing remaining in service was examined using eddy current techniques.
- The threshold of detectability of the eddy current probes has been identified using calibration standards and laboratory-grown cracks , and confirined by metallography.
The threshold of ECT detectability has been demonstrated adequate to identify defects which analysis shows theoretically could propagate to failure due to normal vibration or to transient or accident loads.
Cracks of a size that would propagate have also been demonstrated by analysis to be detectable due to leakage at operating temperatures and pressures.
Increased leakage monitoring is planned and new administrative limits on leakage have been imposed to require investigation of leakage which could be from cracks.
All identified cracks which could propagate or are greater than 40% through wall have been removed from service by plugging the tube or by the kinetic expansion repair techniques.
Thus, we have concluded that the probability of an accident occuring due to undetected damage has not been increased.
- 3. The kinetic expansion repair technique is adequate to remove from service all significant defects at 8" or higher above the lower face of the upper tube sheet. The repair' creates a new tube-to-tubesheet joint belcw this point which meets the licensing bases of the original joint and which ef fectively removes degraded portions of tubing at 8" or above.
- In a qualification test program using tubes and tubesheet moc k-ups , the kinetic expansion joint was demonstrated
- a adequate to carry the maximum design basis axial load.
The joint was demonstrated in the qualification program using mock-ups to continue to meet the licensing bases af ter simulation of 5 years of thermal and pressure cycling.
Longer . term testing is continuing.
- The joint was demonstrated in the qualification program usi'ng mockups and in full-scale testing in a steam generator at B&W to have minimal and acceptable effect on tube preload, the tube-to-tubesheet weld, the tubesheet , and the adj acent tubes.
- The joint was demonstrated in the qualification program using mockups to create a sufficiently leak-tight seal such that aggregate leakage will not exceed a small fraction of the technicci specification limit on leakage.
- The residual stress in the tubing at the transition to the new joint has been demonstrated by laboratory testing and measurement and by analyses to be less than that of the original joint transition.
- The expansion process has been shown in the laboratory testing of tube samples from TMI-l and of tube sections with laboratory grown cracks to cause no growth of cracks.
The expansion process _has been shown in full scale testing to have no adverse physical effects on the remainder of the steam generator or other components.
- The expansion process has been shown by analysis and testing to have no adverse chemical effects.
Thus, we have concluded that there is no increased probability of an accident occurring due to failure of the tube-to-tubesheet joint, and further that the act of creating the new tube-to-tubesheet joint has not increased the probability of any other component failure.
- 4. Use of the repaired steam generator will not change any of the assumptions used to evaluate the consequences of any analyzed accident.
- The qualification program for the new joint has shown, using mock-ups, that the aggregate leakage f rom all the '
d joints will be a small fraction of that assumed in . ent analyses.
- The new administrative limits on leakage will prevent operation with leakage greater than a fraction of that assumed in accident analyses.
- The number and distribution of tubes plugged has been analysed and found to be such that the performance of the steam generator as a heat sink remains within the licensing
-&-- - -+ ,eme e- n ~w,,-r-- - - - - ,
f 9
basis, during normal, transient and accident conditions.
Thus, the consequences of any analyzed accident are considered not to have been increased by the use of the repaired steam generator.
B. IIaving concluded that the change will involve no increase in the probability or consequences of an accident, we next consider whether the change creates the possibility of a new or different kind of accident. The following support the conclusion that it has not.
- 1. The kinetic expansion repair creates a new tube-to-tubesheet joint which meets the licensing bases of the original joint and removes the degraded portion of the tubing from the primary pressure boundary.
The qualification and test programs described above in item A.3 support the conclusion that the new tube-to-tubesheet joint had no greater probability of failure than the old.
The new tube-to-tubesheet joint replaces a previous tube-toatubesheet joint, and does not introduce any new component which could fail in a previously unconsidered manner. .
The potential for future degradation of plugged tubes has been evaluated, and high risk tubes stabilized as well as plugged to prevent interaction of a damaged tube with tubes still in service.
Thus, it is concluded that neither a repaired tube nor a plugged tube introduces either a new type of failure, or a component which is more likely to fail as a result of another transient or accident.
- 2. As concluded in-item A.1, we have sufficient understanding of the failure mechanism to assure safe operation and prevent its recurrence, and we have concluded that the probability of an accident occurring due to new damage is not increased. Thus, it is further concluded that we have not created the potential for any new accidents involving multiple failures of components due to continuing damage.
- 3. As concluded in item A.2, our inspection techniques have been adequate to find and characterize any relevant damage in the steam generators ,in the remainder of the RCS and in the supporting systems. The probability of an accident occurring due to undetected damage is found to have not increased.
Thus, the possibility of an unanalyzed accident caused by undetected damage to multiple components is concluded not, to have been created.
C. The following supports the conclusion that the change does not cause a reduction in any margins of safety.
- 1. As discussed in item A.3 above, the new joint meets the licensing bases of the old joint. Thus, margins of safety inherent in the licensing of the joint as part of the primary pressure boundary are maintained,
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- 2. As discussed in item A.2 above, the tubing remaining in service has been confirmed to be acceptable for use under normal vibration and loading, and transient and accident loading. Thus, margins of safety inherent in the licensing of the tubing as part of the primary pressure boundary are maintained.
- 3. As discussed in i tem A. 2 above, all tubing and other components with significant identified defects have been repaired or removed from service.
Thus, no safety margins have been reduced by the use of less effective equip-ment
- 4. As discussed in item A.4 above, operation with the repaired steam generators does not affect any of the assumptions used in determining acceptability of the plant in the licensing bases . Thus, the margins of safety inherent in the FSAR accident and transient analyses are not red uced .
- 5. In ad d i t ion , the following steps have been taken to effectively increase the margins of safety:
Strict admini s tra tive limits have been placed on primary to secondary leak rate and changes in leak rate over time.
- Improved chemical controls have been implemented.
- Tube rupture procedures have been reviewed and improved.
- Procedural limits have been placed on steam generator tube-to- shell differential temperature to limit stress on the tubing.
We believe that the information summarized above leads to the conclusion that operation of the plant with repaired steam generators does not:
- 1. Increase the probability or consequences of any analyzed accident.
- 2. Create the possibility of a new or different kind of accident from any previously analyzed.
- 3. Reduce any margin of safety.
Thus, CPUN concludes that the change does not involve a significant hazard s
, consideration.
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4 ATTACHMENT B Evaluation of Significant' Hazards Considerations Precritical Non Nuclear Hot Functional Testing Due. to the extended outage, the consequences of any analyzed accident which might
- occur during-the precritical hot functional test period would be considerably less than those calculated in licensing basis documents.
- Decay _ heat being produced is ' currently less than 150 kw. The decay heat _ assumed ,
in design basis analyses is over 1000 times greater than this at the time of scram.
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- Ambient heat loss' from the vessel under operating conditions is on the order of 500 kw which is greater.than the current decay beat production. Thus a complete loss of heat sink for an extended period of time would not result in core damage.
In the event of loss of the steam' generator cooling function in its totality, the low levels of decay heat would allow the core to be cooled for extended periods
( .of time with~ simply the core vessel water inventory and normal thermal losses to ambient. In addition, the decay heat systems are available. While not analyzed 7
in detail, it is also expected that air cooling of the core would maintain the Integrity of -the fuel element l cladding.
l In addition, transients and accidents would be much less severe in scope since
_ decay heat would not be a factor in maintaining RCS- temperature and pressure.
The volatile fission product inventory in the fuel element gap is also extremely small with Xenon-133 and lodine-131 decayed to'almost zero. . The total current core inventory of lodine-129 is less than 2 curies or more than 5 orders of mag-nitude below the normal core lodine inventory for FSAR analysis.
- .- The fission product inventory in the RCS is also considerably less than that con-l= ,sidered in evaluating the consequences of an analyzed accident. The failed' fuel
, . percentage is a small fraction of the 1% used in FSAR calculations. In addition,
[ ~many of the isotopes (e.g., 1-131, Xe-133) contributing to FSAR analyzed doses i have decayed to insignificant concentrations during the extended outage.
- The following isotopes _ represent the only significant isotopes remaining in the p _ primary coolant, as measured
Isotope Concentration (uCl/cc)
Co-60 8.88E-5'
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Cs-134 1.84E-4 l
t- Cs-137 7 90E-4' l
L Sb-125 1.59E-5 For any transient or accident involving a release to the environment, the ex-
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tremely .lcw concentration of iodine would essentially preclude a thyroid dose, and ~ whole. body doses.would be greatly diminished. A direct release to the en-l- vironment of 500'gpm from the primary system as steam, assuming adverse meteor-ological conditions, would result in a projected whole body dose of less than l ' x 10-5 mR/hr at . the si te boundary.
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