|
---|
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
- - - - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
m METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY !
AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNITS 1
)
- Operating License No. DPR-50 1 Docket No. 50-289 Technical Specification Change Request No. 227, Supplement 1 COMMONWEALTH OF PENNSYLVANIA )
) SS: j COUNTY OF DAUPHIN )
This Technical Specification Change Request supplement is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1. As part of this request, proposed replacement pages for - ,
Appendix A are also included. l 1
GPU NUCLEAR CORPORATION f E UN h BY: I C 8m1 Me4.
Vice President and Director, TMI Sworn and Subscribed to before me this D day of One ,1995. !
O 950630oo71 950622 PDR ADOCK 0500o289 AAo bd Notary Public mw emumans. suse Hy
.r.. : = - a g
g x
, _,f-[ ,
' a. "
' UNITED STATES OF AMERICA' :
NUCLEAR REGl'_ATORY COMMISSION i
i IN THE MATTER OF DOCKET NO. 50-289 GPU NUCLEAR CORPORATION LICENSE NO. DPR-50 ,
t CERTIFICATE OF SERVICE 1 This is to cenify that a copy of Technical Specification Change Request (TSCR) No. 227,.
Supplement I to Appendix A of the Operating License for Thme Mile Island Nuclear Station -
Unit 1, has, on the date given below, been filed with executives of Iondonderry Township, ,
Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania -
Depanment of Environmental Resources, Bureau of Radiation Pmtection, by deposit in the . ;
United States mail, addressed as follows: '
i Mr. Jay Kopp, Chairman Mr. Russell L. Sheaffer, Chairman ' :
Board of Supervisors of Board of County Commissioners !
I.ondonderry Township of Dauphin County ~
R. D. #1, Geyers Church Road Dauphin County Counhouse ,
Middletown, PA 17057 Harrisburg, PA 17120 .
Dimetor, Bureau of Radiation Protection 3 PA. Depanment of Envimnmental Resources ;
Fifth Floor, Fulton Building ;
Third and Iocust Streets !
P. O. Box 2063 i Harrisburg, PA 17120 .l Attn: Mr. Roben J. Barkanic j i'
GPU NUCLEAR CORPORATION
)
BY:
fh3.WN
% C. 6 % ,(h4 h l Vice President and Director, TMI DATE: #2/fI
y
~
.g 7 - ,
c -
~
?. ' ' C311-95-2245 : .
<v ,; Enclosure 1L ,
j Page'l' I
- GPU NUCLEAR RESPONSE TO'NRC REQUEST FOR' ADDITIONAL INFORMATION _;
p FOR TMI TECHNICAL SPECIFICATION CHANGE REQUEST NO. 227 .:
l FOR INCORPORATING CERTAIN STANDARD TECHNICAL SPECIFICATIONS h1
- 1. Containment Airlocks !
STS 3.6.2.C.I requires immediate initiation of action to evaluate overall containment f L leakage ate per LCO 3.6.1 (which in turn references 10 CFR 50, Appendix J) when one ,
or more containment air locks are inoperable for reasons other than those stated in STS 3.6.2.A and 3.6.2.B. The proposed TS 3.6.12.d pmvides no specific guidance or :
criteria regarding this leakage rate evaluation and does not include reference to or the.
requirements of 10 CFR 50, Appendix J. Please provide clarification in the form a i revised TS page 3-41.b. .!
GPU Nuclear Response f i
Attached are revised TS pages which include additional verbiage taken from the Standard Technical Specifications (STS) for B&W Plants (NUREG-1430). TMI-l TS 3.6.12.d and -
the corresponding bases have been revised to provide the specific guidance and criteria i associated with this leakage rate evaluation. A reference to the requirements of 10 CFR 50, Appendix J has been added as follows:
- a. ' Page 3-41b has been revised' to clarify that the overall containment leakage rate is to [
be evaluated with respect to the requirements of 10 CFR 50, Appendix J, as 'i modified by appmved exemptions. .;
- b. Page 3-41c has been revised to include the following STS bases statement: _
" Maintaining the containment OPERABLE requires compliance with the visual ;
examinations and leakage rate test requirements of 10 CFR 50, Appendix J (Ref.1),
as modified by approved exemptions." *
- c. Page 3-41d has been revised to include a reference to 10 CFR 50, Appendix J. j
- 2. Hydroeen Recombiner System- l l
The proposed changes to TS 4.4.4.1 do not include the performance criteria for the recombiner system functional test and heater electrical circuit integrity as given in the current TMI-l TS and the STS. Please explain why the performance criteria described j above do not need to be retained in the TS. ;
1 I
i
"__ _ .- _ ., _. _____i
j' t, '
. C311-95-2245 _
2 ~ ,, Enclosure 1 -
Page'2 ;
i GPU Nuclear Response -l The revised TS page incorporates the performance criteria from TS's 4.4.4.1.b.3 and- 3 4.4.4.1.b.4 as follows:
I
- a. For the hydmgen recombiner system functional test, verify that the reaction !
chamber gas temperature is maintained 21200*F for at least four hours.' j
- b. For the resistance to gmund test of each heater phase, verification that the- i resistance to ground for any heater phase is 210,000 ohms. !
c As discussed with'the NRC in a meetin'g on March 20,1995, GPU Nuclear feels that if the performance criteria are required to be specified,- they should be part of the specification rather than the bases.
- 3. Reactor Building '
A proposed change has been made to TS page 3-41 (TS 3.6.7) that would delete the requirement to bring the reactor to hot shutdown within seven days when the hydrogen ;
recombiner is inoperable. Please pmvide justification for the change to TS 3.6.7.
GPU Nuclear Response Deletion of the requirement to bring the reactor to hot shutdown within seven days when the hydmgen recombiner is inoperable was not intended. The intent had been to revise ,
TS 3.6.7 to match the STS requirement. The attached revised TS page 3-41 _
incorporates the STS and changes TS 3.6.7 which currently reads "... restore the recombiner to operable status or bring the reactor to HOT SHUTDOWN within seven (7) days" to read "... restore the inoperable hydmgen recombiner to operable status ;
within 7 days or be in HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />."
- 4. Emereency Contml Room Air Treatment System I
This submittal proposed a change in TS 4.12.1.2.d to incorporate a variation of !
STS 3.7.10.1 (i.e., operate each [ Control Room Emergency Ventilation System (CREVS)] train for 2 15 minutes every 31 days) which is intended only for control mom emergency ventilation systems without heaters upstream of the charcoal beds. l However, the TMI-1 Emergency Control Room Air Treatment System does contain .
heaters upstream of the charcoal beds. In that case, the STS specifies opemting each ;l train of the system for 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> every 31 days. This surveillance is specified in Regulatory Guide 1.52, Revision 2 (which is referenced in the TS bases). As stated in the STS bases, and RG 1.52, operation of the heaters on a monthly basis is intended to
C311-95-2245
.. Page 3 dry out (or reduce) moisture that has built up in the charcoal adsorbers because of humidity in the ambient air. The amendment request stated that the heaters are not needed for humidity control because the inlet air flow to the system is a combination of about 75% return air and 25% outside air, with maximum relative humidities of 50%
and 100%, respectively. It was therefom stated that the resultant inlet flow should never exceed 70% relative humidity without operation of heaters, which is the reference humidity specified in Table 2 of RG 1.52, "Labomtory Tests for Activated Carbon."
Although the argument has some merit and the proposed change would result in a .
burden reduction, the GPUN submittal does not provide adequate information for the staff to allow deviation from the STS requirements nor does it provide any compensatory measures, which might include laboratory test verification data, that would justify or substantiate the GPUN statement that mnning the monthly operational test for only 15 minutes and without energizing the electric heating coils will not degrade the performance of the system. Please provide additionaljustification for your request.
GPU Nuclear Resnonse ;
Reference:
TMI-l P&ID 302-842, Sheet 1 of 2 Thermostatically controlled preheat heating coils (AH-C-5A/B), are located in the ponion of the TMI-l Control Building Ventilation System (CBVS) upstream of the Control Room Emergency Ventilation System (CREVS) loop. These heaters are provided for habitability and are not required or relied upon for operability of the CREVS. They are not designed for nor are they needed for humidity control and their ,
operation is not required by the current TMI-l Technical Specifications during testing.
A single temperature controller in each train (TC-737 or TC-738) controls the operation of both the preheaters upstream and the coolers (AH-C-6A/B) downstream of the i emergency supply fans (AH-E-18A/B) to provide either heating or cooling as necessary l to maintain the desired temperature. Therefore, during surveillance tests of the CREVS i performed to date, the heaters would have only been energized during cold weather I
conditions. During warm weather conditions (and often high humidity conditions) the heaters are not energized. I Listed below are the results from laboratory analysis of the CREVS charcoal for the last five years. TMI-l TS mquires laboratory carbon sample analysis results 2:90 %,
radioactive methyl iodide decontamination efficiency when tested at 125 F and 95%
relative humidity. Additional tests at 30 C and 95% relative humidity are performed for additional information. These results demonstrate that performance of the surveillance tests without energizing the heaters for a large percentage of the year has not resulted in degradation of the charcoal bed performance.
l
C311-95-2245 Page,4 .
CONTROL ROOM EMERGENCY VENTILATION SYSTEM LABORATORY CHARCOAL ANALYSIS Train Test Charcoal Efficiency (%) Charcoal Efficiency (%)
Date (TMI-1 Tech spec Test - (TMI-1 Information only Test -
@ 125'F & 95% Relative Humidity) @ 30*C & 95% Relative Humidity)
A 6/94 99.19 97.23 B 6/94 98.99 97.04 A 7/93 98.54 94.61 B 7/93 98.36 96.54 A 7/92 99.29 95.31 B 7/92 99.22 96.77 A 8/91 99.84 92.75 B 8/91 99.98 96.64 A 8/90 99.97 98.84 B 8/90 99.84 99.79 Opemting the two CBVS fan / filter circuits in the emergency mode for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> each month creates unnecessary hardship during warm weather conditions in that the emergency mode shuts off the majority of the cool air supply to the first floor of the Control Building. This first floor contains plant chemistry sample rooms and labs, health physics offices, and check in/ check out points. After a period of time, elevated temperatures cause personnel discomfort and unnecessary heating of the equipment in these areas.
GPU Nuclear has concluded that operation of the CREVS fan / filter circuits for 15 minutes each month is adequate to demonstrate operability and will not result in a buildup of moisture in the charcoal beds sufficient to adversely affect system performance.
_ - _ _ _ - - - _ _ - - _ - - _ _ - _ _ _ - _ _ _ _ - _ _ _ - _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _