|
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20212H5071999-09-27027 September 1999 Application for Amends to Licenses DPR-44 & DPR-56,change Application ECR 96-01511,to Revise TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20211M7081999-09-0101 September 1999 Suppl License Change Application ECR 99-01497 for Licenses DPR-44 & DPR-56,correcting Minor Discrepancies Discovered in Pages of Attachment 2 ML20210P8811999-08-11011 August 1999 Application for Amends to Licenses DPR-44 & DPR-56 in Order to Clarify PBAPS Licensing Basis to Include Specific Info Re Allowed Containment Overpressure Credit Needed to Ensure Adequate NPSH Available for ECCS Pumps.Ufsar Changes,Encl ML20210N0711999-08-0606 August 1999 Exigent License Change Application ECR 99-01727 for Licenses DPR-44 & DPR-56,incorporating Note Into TS Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20209F7641999-07-12012 July 1999 License Change Application ECR 99-01255,revising TS Sections 2.1.1.2 & 5.6.5 by Incorporating Revised SLMCPR & Deleting Previously Added footnotes.Non-proprietary & Proprietary Info Re Slmcpr,Encl.Proprietary Info Withheld ML20209B9141999-07-0101 July 1999 Application ECR 99-01497 for Amend to Licenses DPR-44 & DPR-56,reflecting Change in Corporate Structure ML20205F6221999-03-29029 March 1999 Application for Amends to Licenses DPR-44 & DPR-56,revising TS to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2421999-03-0101 March 1999 License Amend Request ECR 98-01802 for Licenses DPR-44 & DPR-56,proposing Changes to Support PBAPS Mod P00507 Which Will Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term T/H Stability Solution Hardware ML20198N2471998-12-24024 December 1998 License Change Application ECR 96-01511,revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20236R3011998-07-10010 July 1998 Application for License Change ECR 98-01403,requesting Change to License DPR-44 Revising TS Section 2.0 & non-proprietary & Proprietary Versions of 980609 Addl Info Re 1.10 Cycle Specific Slmcpr.Proprietary Version Withheld ML20247C2481998-05-0101 May 1998 License Change Application ECR 98-00499 for Amends to Licenses DPR-44 & DPR-56,revising TS to Delete Requirements for Functional Testing of SRVs During Each Unit Startup ML20217G7481998-03-20020 March 1998 License Change Application ECR 97-02809,revising Tech Specs to Incorporate end-of-cycle Recirculation Pump Trip Sys at Units 1 & 2 ML20217Q4631998-03-0202 March 1998 Application for Amend to License DPR-12,adding Requirements to TS to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4151998-02-0404 February 1998 Application for Amends to Licenses DPR-44 & DPR-56,revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20211H9171997-09-26026 September 1997 Application for Amend to License DPR-56,deleting Submitted Page 2.0-1 to Be Replaced W/Encl Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20141G4821997-06-30030 June 1997 License Change Request ECR 96-03620,revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8501997-06-0404 June 1997 License Change Application ECR 97-00086,revising TS Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of EDGs on ECCS Initiation During Listed Events ML20141L0081997-05-23023 May 1997 License Change Application ECR 96-02324,revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0721997-05-0909 May 1997 License Change Application ECR 96-00982,revising TS SR 3.6.1.3.16 Re Replacement Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141A7861997-05-0505 May 1997 Application for Amend to Licenses DPR-44 & DPR-56,requesting Approval for Implementation of Plant Mod to ECCS Pumps in Order to Satisfy Recommendations Stipulated in NRC Bulletin 96-003 ML18102B0071997-04-30030 April 1997 Application for Amends to Licenses DPR-40,DPR-56,DPR-70 & DPR-75,requesting Consent of NRC for Indirect Transfer of Control of Interest in Plants That Will Occur Under Proposed Merger ML20137P7511997-03-31031 March 1997 License Change Request ECR 96-00627,extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20134F6091996-10-30030 October 1996 Application for Amend to License DPR-56,revising Slmcprs,Ts Section 2.0,by Incorporating Rev Due to GE Determination That Previous Calculation Is non-conservative ML20117L2821996-09-0606 September 1996 Application for Amends to Licenses DPR-44 & DPR-56 Adding Notes to Allow Core Spray & LPCI Pumps to Start out-of- Sequence Under Certain Conditions & Adding Notes to Selected Surveillance Requirements ML20117F9321996-08-27027 August 1996 Application for Amends to Licenses DPR-44 & DPR-56, Correcting Administrative Error in TS Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6711996-08-23023 August 1996 License Change Request 96-01 to Licenses DPR-44 & DPR-56, Revising TS Section 2.0, Safety Limits to Incorporate New Safety Limit Min Critical Power Ratios,Due to Use of GE13 Fuel Product Line ML20117M6981996-06-13013 June 1996 License Change Request ECR 96-02011 to License DPR-44, Permitting One Time Performance of SR 3.3.1.1.12 for APRM Flow Biased High Scram Function,W/Delayed Entry Into Associated TS Conditions & Required Actions for Up to Six H ML20101K7961996-03-25025 March 1996 License Change Request 96-01 to Licenses DPR-44 & DPR-56, Revising TS Section 2.0, Safety Limits ML20100J7361996-02-15015 February 1996 License Change Request 95-11 to Licenses DPR-44 & DPR-56, Reflecting Implementation of 10CFR50,App J,Option B ML20095J1251995-12-21021 December 1995 TS Change Request 95-08,eliminating Outdated Matl from FOLs & Making FOL for Unit 2 Consistent W/Fol for Unit 3 ML20095J6971995-12-19019 December 1995 TS Change Request 95-13 to Licenses DPR-44 & DPR-56, Correcting Administrative Error in Improved Tech Specs Re Ventilation Filter Testing Program ML20095A1621995-11-30030 November 1995 Application for Amends to Licenses DPR-44 & DPR-56, Consisting of Change Request 95-12,changing Minimum Allowable Control Rod Scram Accumulator Pressure & Charging Water Header Pressure from Value of 955 Psig to 940 Psig ML20094Q6541995-11-21021 November 1995 Application for Amends to Licenses DPR-44 & DPR-56,changing SR for High Pressure Test of the HPCI & RCIC Sys. Administrative Change Proposed to Eliminate Ref to Section Previously Eliminated ML20092L6251995-09-22022 September 1995 Informs of Change to Pbaps,Units 2 & 3 TS Bases,Figure 1.1-1.Change Allows PBAPS Units 2 & 3 to Maximize Generation Throughout Entire Fuel Cycle ML20092A2071995-09-0101 September 1995 Application for Amend to License DPR-56,consisting of Change Request 95-07,deleting License Condition 2.C ML20092B9361995-08-28028 August 1995 Rev E to TS Change Request (Tscr) 93-16 to Licenses DPR-44 & DPR-56 Re Implementation of Improved Ts.Rev E to Tscr 93-16 Redesignates Change Control Mechanism from 10CFR50.59,as Indicated Previously,To 10CFR50.54(a) for Six Listed Items ML20086Q4271995-07-21021 July 1995 Application for Amends to Licenses DPR-44 & DPR-56,proposing Overall Conversion of Current PBAPS TS to Improved TS as Contained in NUREG-1433, Std Ts,Ge Plants,BWR/4 ML20083Q7341995-05-16016 May 1995 Rev a to Tscr 93-16 Re Conversion to Improved TSs as Contained in NUREG-1433 ML20083K8581995-05-0909 May 1995 Application for Amend to Licenses DPR-44 & DPR-56,consisting of Change Request 93-16 Re Conversion of Current PBAPS TS to Improved TS ML20082M3191995-04-12012 April 1995 Suppl 2 to License Change Request 94-08,supporting Mod P00068-3,which Upgrades Major Components of TIP Sys to Correct Typo.Revised TS Page 186 Encl ML20087H0411995-04-10010 April 1995 Application for Amends to Licenses DPR-44 & DPR-56, Consisting of Change Requests 94-11,94-12 & 94-13,relocating Certain Review & Audit Requirements to Plant UFSAR ML20082B2121995-03-23023 March 1995 Revised Page 4 to TS Change Request 90-03 ML20082B0491995-03-22022 March 1995 License Change Request 95-04 to Licenses DPR-44 & DPR-56, Reducing Local Leak Rate Test Hold Time Duration from One H to 20 Minutes ML20081H1261995-03-16016 March 1995 Application for Amends to Licenses DPR-44 & DPR-56 Re Requirements for SRMs While in Refueling Condition ML20080H0401995-02-10010 February 1995 Application for Amends to Licenses DPR-44 & DPR-56, Correcting Administrative Errors Made During Past TS Changes ML20078A0531995-01-17017 January 1995 Application for Amends to Licenses DPR-44 & DPR-56,proposing to Change Source Range Monitor to Range Neutron Monotors & Delete Intermediate Range Monitors ML20077S6191995-01-13013 January 1995 License Change Request 94-07 to Licenses DPR-44 & DPR-56, Revising Allowed Time Between Signal Calibrs of LPRM from Every 6 Wks (Approx 1,000 EFPH) to Every 2,000 Megawatt Days Per Std Ton ML20077S4691995-01-13013 January 1995 License Change Request 94-08 to Licenses DPR-44 & DPR-56, Revising TS Tables 3.7.1 & 3.7.4 to Reflect Reduction in Number of Primary Containment Power Operated Outboard Valves for TIP Probes,Per PBAPS Mod P00068 ML20078L7541994-11-21021 November 1994 TS Change Request 94-14 to License DPR-56,re One Time Schedular Exemption from 10CFR50,App J,Section III.D.1(a) Concerning 10CFR50,App J Type a Test Intervals ML20078K7601994-11-17017 November 1994 License Change Request 93-13 to Licenses DPR-44 & DPR-56, Revising TS to Support Mods 5384 & 5386,upgrading Main Stack & Vent Stack Radiation Monitoring Sys 1999-09-27
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217K9761999-10-14014 October 1999 Amend 234 to License DPR-56,changing TS in Response to 990301 Application & Suppls ,1001 & 06,to Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Monitoring Sys ML20217B4261999-10-0505 October 1999 Amend 233 to License DPR-56,changing Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Repts ML20212H5071999-09-27027 September 1999 Application for Amends to Licenses DPR-44 & DPR-56,change Application ECR 96-01511,to Revise TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20216H6891999-09-24024 September 1999 Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively, Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by TSs SR 3.9.1.1 ML20211M7081999-09-0101 September 1999 Suppl License Change Application ECR 99-01497 for Licenses DPR-44 & DPR-56,correcting Minor Discrepancies Discovered in Pages of Attachment 2 ML20211D5471999-08-23023 August 1999 Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively, Revising TSs to Correct Typo & Editorial Errors Introduced in TSs by Previous Amends ML20210P8811999-08-11011 August 1999 Application for Amends to Licenses DPR-44 & DPR-56 in Order to Clarify PBAPS Licensing Basis to Include Specific Info Re Allowed Containment Overpressure Credit Needed to Ensure Adequate NPSH Available for ECCS Pumps.Ufsar Changes,Encl ML20210N0711999-08-0606 August 1999 Exigent License Change Application ECR 99-01727 for Licenses DPR-44 & DPR-56,incorporating Note Into TS Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20209F7641999-07-12012 July 1999 License Change Application ECR 99-01255,revising TS Sections 2.1.1.2 & 5.6.5 by Incorporating Revised SLMCPR & Deleting Previously Added footnotes.Non-proprietary & Proprietary Info Re Slmcpr,Encl.Proprietary Info Withheld ML20209B9141999-07-0101 July 1999 Application ECR 99-01497 for Amend to Licenses DPR-44 & DPR-56,reflecting Change in Corporate Structure ML20205K7371999-04-0707 April 1999 Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively, Consisting of Changes to TS SRs Re Secondary Containment Doors in Response to 980204 Application,As Revised by ML20205F6221999-03-29029 March 1999 Application for Amends to Licenses DPR-44 & DPR-56,revising TS to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2421999-03-0101 March 1999 License Amend Request ECR 98-01802 for Licenses DPR-44 & DPR-56,proposing Changes to Support PBAPS Mod P00507 Which Will Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term T/H Stability Solution Hardware ML20198N2471998-12-24024 December 1998 License Change Application ECR 96-01511,revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20155C6011998-10-26026 October 1998 Amend 226 to License DPR-44,revising TSs for Safety Limit MCPR from Current Value of 1.11 to 1.10 for Two Recirculation Loop Operation & from 1.13 to 1.12 for Single Recirculation Loop Operation ML20154H4691998-10-0505 October 1998 Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively, Revising TSs to Permit Incorporation of EOC-RPT Sys at Plant,Units 2 & 3 ML20154J2261998-10-0505 October 1998 Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively, Revising TSs to Delete Requirements for Functional Testing of SRVs During Each Unit Startup ML20154G6551998-10-0101 October 1998 Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively, Revising Plant,Units 2 & 3 TSs to Exclude MSIV Leakage from Total Type B & Type C Local Leak Rate Test Results ML20153B9581998-09-14014 September 1998 Amend 9 to License DPR-12,adding Requirements for Control of Effluents & Annual Reporting Per 10CFR50.36a ML20238F2611998-08-24024 August 1998 Amend 222 to License DPR-44,revising Pbaps,Unit 2 TSs to Support Mod P00271,which Would Replace SRMs & IRMs W/Wrnms, During Forthcoming Outage 2R12,scheduled for Early Oct 1998 ML20236R3011998-07-10010 July 1998 Application for License Change ECR 98-01403,requesting Change to License DPR-44 Revising TS Section 2.0 & non-proprietary & Proprietary Versions of 980609 Addl Info Re 1.10 Cycle Specific Slmcpr.Proprietary Version Withheld ML20247C2481998-05-0101 May 1998 License Change Application ECR 98-00499 for Amends to Licenses DPR-44 & DPR-56,revising TS to Delete Requirements for Functional Testing of SRVs During Each Unit Startup ML20217G7481998-03-20020 March 1998 License Change Application ECR 97-02809,revising Tech Specs to Incorporate end-of-cycle Recirculation Pump Trip Sys at Units 1 & 2 ML20217Q4631998-03-0202 March 1998 Application for Amend to License DPR-12,adding Requirements to TS to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4151998-02-0404 February 1998 Application for Amends to Licenses DPR-44 & DPR-56,revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20212G8261997-10-24024 October 1997 Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively, Changing TSs to Eliminate Inconsistency Between ECCS Operability Requirements & Autostart & Protective Trip Bypass of EDGs on ECCS Initiation Signal ML20217J5571997-10-0909 October 1997 Amend 225 to License DPR-56,revising MCPR Safety Limit in Section 2.1 of TSs from 1.07 to 1.11 for Two Recirculation Loops in Operation ML20217D8101997-09-30030 September 1997 Amend 224 to License DPR-56,revises TS to Support PBAPS Mod P00271,which Would Replace Source Range & Intermediate Range Monitors W/Wide Range Neutron Monitoring System ML20211H9171997-09-26026 September 1997 Application for Amend to License DPR-56,deleting Submitted Page 2.0-1 to Be Replaced W/Encl Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20216G5321997-09-0404 September 1997 Amends 220 & 223 to Licenses DPR-44 & DPR-56,respectively, Revising TS to Extend Replacement Frequency for Inflatable Seat Seals for Primary Containment Purge & Vent Valves to 96 Months ML20217M7961997-08-19019 August 1997 Amends 219 & 222 to Licenses DPR-44 & DPR-56,respectively, Extending APRM Flow Bias Instrumentation Surveillance Interval from 18 Months to 24 Months ML20141G4821997-06-30030 June 1997 License Change Request ECR 96-03620,revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8501997-06-0404 June 1997 License Change Application ECR 97-00086,revising TS Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of EDGs on ECCS Initiation During Listed Events ML20141L0081997-05-23023 May 1997 License Change Application ECR 96-02324,revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0721997-05-0909 May 1997 License Change Application ECR 96-00982,revising TS SR 3.6.1.3.16 Re Replacement Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141A7861997-05-0505 May 1997 Application for Amend to Licenses DPR-44 & DPR-56,requesting Approval for Implementation of Plant Mod to ECCS Pumps in Order to Satisfy Recommendations Stipulated in NRC Bulletin 96-003 ML18102B0071997-04-30030 April 1997 Application for Amends to Licenses DPR-40,DPR-56,DPR-70 & DPR-75,requesting Consent of NRC for Indirect Transfer of Control of Interest in Plants That Will Occur Under Proposed Merger ML20137P7511997-03-31031 March 1997 License Change Request ECR 96-00627,extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20135B3851997-02-19019 February 1997 Amends 218 & 221 to Licenses DPR-44 & DPR-56,respectively, Changing Min Allowable Charging Water Header Pressure from Value 955 Psig to Value of 940 Psig in TS 3.10.8 ML20134F6091996-10-30030 October 1996 Application for Amend to License DPR-56,revising Slmcprs,Ts Section 2.0,by Incorporating Rev Due to GE Determination That Previous Calculation Is non-conservative ML20117L2821996-09-0606 September 1996 Application for Amends to Licenses DPR-44 & DPR-56 Adding Notes to Allow Core Spray & LPCI Pumps to Start out-of- Sequence Under Certain Conditions & Adding Notes to Selected Surveillance Requirements ML20117F9321996-08-27027 August 1996 Application for Amends to Licenses DPR-44 & DPR-56, Correcting Administrative Error in TS Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6711996-08-23023 August 1996 License Change Request 96-01 to Licenses DPR-44 & DPR-56, Revising TS Section 2.0, Safety Limits to Incorporate New Safety Limit Min Critical Power Ratios,Due to Use of GE13 Fuel Product Line ML20117M6981996-06-13013 June 1996 License Change Request ECR 96-02011 to License DPR-44, Permitting One Time Performance of SR 3.3.1.1.12 for APRM Flow Biased High Scram Function,W/Delayed Entry Into Associated TS Conditions & Required Actions for Up to Six H ML20101K7961996-03-25025 March 1996 License Change Request 96-01 to Licenses DPR-44 & DPR-56, Revising TS Section 2.0, Safety Limits ML20100J7361996-02-15015 February 1996 License Change Request 95-11 to Licenses DPR-44 & DPR-56, Reflecting Implementation of 10CFR50,App J,Option B ML20095J1251995-12-21021 December 1995 TS Change Request 95-08,eliminating Outdated Matl from FOLs & Making FOL for Unit 2 Consistent W/Fol for Unit 3 ML20095J6971995-12-19019 December 1995 TS Change Request 95-13 to Licenses DPR-44 & DPR-56, Correcting Administrative Error in Improved Tech Specs Re Ventilation Filter Testing Program ML20095A1621995-11-30030 November 1995 Application for Amends to Licenses DPR-44 & DPR-56, Consisting of Change Request 95-12,changing Minimum Allowable Control Rod Scram Accumulator Pressure & Charging Water Header Pressure from Value of 955 Psig to 940 Psig ML20094Q6541995-11-21021 November 1995 Application for Amends to Licenses DPR-44 & DPR-56,changing SR for High Pressure Test of the HPCI & RCIC Sys. Administrative Change Proposed to Eliminate Ref to Section Previously Eliminated 1999-09-27
[Table view] |
Text
, _ . _ _.. . ____.-. _
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10.CPR 50.90 3 "Ij ' 4i
~
PH'lLADELPH'IA ELECTRIC COM PANY- '
NUCLEAR GROUP HEADQUARTERS ~ -
-1 1
955-65 CHESTERBROOK BLVD. -
WAYNE, PA 19087 5691 .
(ris) s4o-sooo
.c g ;
I November 22,'1989 ,
Docket Nos. 50-277 '
License Nos. DPR-44 DPR-56 l s
U.S.. Nuclear Regulatory Commission l
ATTN: Document Control Desk '
Washington, D. C. 20555 -
i; -
SUBJECT:
' Peach Bottom' Atomic Power-Station, Units 2 and 3 H
- Technical Specifications Change Request '
Dear Sir:
x Philadelphia Electric Company hereby submits Technical ;
p
-Specifications Change Request No.'89-15, in accordance with 10 CPR 50.90,.-requesting an amendment to the Technical Specifications (Appendix A)=of Operating License Nos. DPR-44 and DPR-56.
. Information supporting'this-Change Request is-contained in 1: Attachment 1 to this letter, and the proposed replacement pages are contained in Attachment 2.
~ This submittal' requests changes to the Technical-Specifications to incorporate a-Surveillance Requirement for the safety grade pneumatic supply system which supplies the containment purge / vent valve inflatable seals.
If you have any questions regarding this matter,.please 3 contact us.
Very trul yours, G. A. Hunger, Jr.
fu .
Director Licensing Section 9911300017 PDR ADOCK $000 77 Nuclear Services Department 1
POC P
Attachments cc:- W. T. Russell, Administrator, Region I, USNRC 00N i
J. J. Lyash, USNRC Senior Resident Inspector * '
{
G. Y. Suh, Project Manager, USNRC se ww- e e w fYa= w* Ww 71- p 3 =ge vp1* b Dv -m Se3-r 1rI- W- T F T 7 8*-e-e i7g- --7p v 9-w$77-Tr P FW"T"W
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COMMONWEALTH OF PENNSYLVANIA : .
- as. . .
COUNTY OF CHESTER :
LD.~R. Helwig, being first duly sworn, deposes and says: f t
That he is Vice'-President of Philadelphia Electric Company;
~that he has read Technical Specifications Change Request No. 89-15, i and knows the contents thereof; and that the statements and matters
. set forth therein are true and correct to the best of his knowledge,-
information and belief.
L
,+- '
A -
Vice President
' Subscribed and sworn to
.before me thisal #day
-of'kWod1989. t do.d D Ah.
Notary-Public NOTARIAL SEAL -
CATHERINE A. MENDEZ. Notary Public Tredvffnn Two. Chester County My Comrrieston Excites Sect. 4.1993 -
m, .
n ,
I i
ATTACHMENT 1 ,
4 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND'3 ..
Docket-Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 I i
TECHNICAL' SPECIFICATIONS CHANGE REQUEST NO. 89-15
" Incorporate'a Surveillance Requirement for the Safety
- Grade-Pneumatic Supply System which Supplies the Containment Purge / Vent Valve Inflatable Seals" I
1, I
l*.
l l
14 N4 !
.. 50-278 't License Nos. DPR-44 ,
DPR-56 '
Philadelphia Electric Company (PECo), Licensee under
-Facility Operating Licenses DPR-44 and DPR-56 for Peach Bottom I
- Atomic PowerLStation,: Units 2-and 3, hereby requests thatLthe Technical Specifications contained in Appendix A to the License be amended as indicated by a vertical bar in the margin of the pages in Attachment 2 and'11sted here:-172, 175, and 178a.
Description of Changes-Licensee proposes to incorporate into the Technical
' Specifications a surveillance requirement for the safety-grade pneumatic supply to the containment purge / vent valve inflatable- 1 seals.
In a l'etteridated November 21, 1984 concerning containment
_ purge and vent valves, the NRC stated its position that a Technical Specification.is required to demonstrate the. leak tight integrity of '
the-safety grade seal air supply system. ;
Philadelphia Electric Company responded to this issue in a letter dated November 6, 1985 in which we proposed that in lieu of leakage testing requirements for the safety-grade seal air supply system which would rely on backup bottled nitrogen supplies, PECO
.would modify the system to connect the seal air supply system for the Containment Atmospheric Dilution System (CADS) and Containment E
Atmospheric Control System (CACS) valves to the existing CADS 6000 i !
v.: 3 s
, Docket No2.c50-277 i
-' 50-278 License Nos. DPR-44 DPR-56 !
e
>; gallon;11guld nitrogen storage tank.- This hard-piped safety grade pneumatic supply would beEinstalled to each of the valves and would .
1 replace: the individual bottle supplies. Additionally, we proposed that a surveillance requirement which-demonstrates. operability of .
the safety grade pneumatic supply be incorporated into the Technical .
-Specifications.
7,n Technical Specification Amendment No. 144 and 146 dated May 8, 1989, which incorporated specifications for large primary ~ t containment purge / vent isolation valves, the NRC staff found the- ,
. proposed. modification for the safety grade pneumatic supply as <
~
discussed in the November 6, 1.985 letter acceptable and requested that PEco submit to the NRC a proposed Technical Specification which addresses the surveillance requirement. .:
This Technical Specification Change Request satisfies the request of-the May 8, 1989 letter. The additional surveillance-requirement originally proposed by PECo'in the November 15, 1985 letter has been modified in this change request to more clearly specify the surveillance to be performed. A change to an existing surveillance requirement is also requested as a result of the l
safety grade pneumatic supply modification.
Also included in the May 8, 1989 Amendment was a typographical error in which the word "or" was missing from l Surveillance Requirement 4.7.B.2.b of the Unit 3 Technical a
l l
5r-yf q-l
( y . ,, 3 :. a Y
hhiN[
m D-Dockst No3. 50-277. d 50-278
.g{]; ' License Nos. DPR-44 DPR-56~ ,
l .
m.
1 pq, 3
.-Specifications... Correction of this error is being requested by this' l-
- Technical Specification Change Request. ,
List'of Proposed Page Changes: .
~
Page (Unit) Change =
i Page'178a.'(Unit 2 and 3) -Add proposed-Surveillance-
, Requirement:4.7.E.3 which- [
states: "The valve operator-and inflatable seal safety-
, grade backup pneumatic: supply -
system shall'be demonstrated operable for the isolation L.
valves with backup nitrogen supply from the Containment i3 Atmospheric Dilution System i y (CADS) nitrogen storage tank ;
-by:
1:
- a. Verifying at least once per day that the CADS nitrogen storage tank L contains a minimum of 2500 gallons.
L l~
g
. . .. - . - ... . . . . . ~ ... - .- ..
P' [ -
Dockst No2. 50-277
, 50-278 l License Nos. DPR-44
- b. Once per operating cycle, conduct a functional test that. demonstrates the operability of the backup (CADS _ tank) nitrogen supply ~
system upon loss of the normal supply. system."
Page 172-(Units 2 and 3) Change the minimum liquid Specification 3.7.A.6.b nitrogen requirement for ,
the post-LOCA Containment Atmosphere Dilution System from 2000-gallons-to
, 2500 gallons.
Specification-4.7.A.6.b Revise the surveillance requirement for recording the level in the liquid nitrogen storage tank on a weekly basis to refer to the proposed specification 4.7.E.3.a which requires daily verification of the nitrogen storage tank volume.
f The revised specification
~
l T . __.a .._ . _ ._
l 91 !
' Dockot Nos. 50-277- '
3', 50-278-License:Nos. DPR-44 DPR-56 will read "The level in the' s
liquid nitrogen storage tank shall be verified'in' accordance with Specification j
4.7.E.3.a." !
Page-175 (Unit 3)- Add the word-"or" such
,': Surveillaace Requirement 4.7.B.2.b that the statement : reads .
" Cold DOP testing shall be performed -'
after each complete or partial replacement of the HEPA filter bank or after any structural .
maintenance on the system housing."-
Safety Assessment:
The proposed Technical Specification incorporates a
' surveillance requirement which will demonstrate the operability of the safety-grade pneumatic supply system for the containment purge / vent inflatable seals. The acceptability of this new system
'is discussed in Technical Specification Amendment Nos. 144 and 146, dated May 8, 1989. In the May 8, 1989 letter, the NRC requested PECo'to submit a proposed Technical Specification that addresses the '
surveillance requirement.
, Docket No2. 50-277
' 50-278 j License Nos. DPR-44 -
DPR-56 -
p During accident; conditions,-the air supply to the CADS and ,
CACS. valve inflatable seals is maintained by either the normal
, instrument air system or the_new safety grade backup CADS supply.
- All but minor leaks would be evident by observation or loss of' CADS
- nitrogen inventory.- Minor leaks are not a safety concern during ,
accident conditions since the storage tank is accessible and can be recharged.from liquid nitrogen tanker delivery trucks. The surveillance requirement proposed in this amendment ensures that the-nitrogen: supply is monitored on a daily basis and that a once per operating cycle functional test which demonstrates operability of
'the new system ir performed. . The proposed minimum CADS tank liquid nitrogen inventory of 2500 gallons for Technical Specifications
- 3.7.A.6.b and 4.7.E.3 is based upon the following.
1)' 2000 gallons - The total volume of liquid nitrogen required for combustible gas dilution in containment for the first eight (8) days following a Loss of Coolant Accident (LOCA), .
and
- 2) 500' gallons - The total volume of liquid nitrogen required to account for the safety grade pneumatic supply system leakage during a four (4) hour failure of the pressure control valve, the volume required for the safety grade pneumatic supply system operation for a seven day accident period, and an additional twenty-five (25) percent safety margin.
, Docket Nos. 50-277
, 50-278 Lice'nse Nos. DPR-44 DPR-56 The proposed change.to Technical Specification 4.7.A.6.b, which currently requires weekly verification of the nitrogen storage tank. level,.is to refer to the new proposed Technical Specification _.
' 4.7.E.3.a which requires daily' surveillance of the tank inventory. J
' This change would eliminate a redundant surveillance and reduce the opportunity for misinterpretation of a surveillance requirement.
The. proposed change to a more frequent surveillance is more restrictive than the current requirement and therefore does not decrease safe operation of~the plant.
The change to Surveillance Requirement 4.7.B.2.b regarding testing _of the Standby Gas Treatment System was approved as requested in Amendment No. 144 for Unit 2. The word "or", however, was'omitted from the Unit 3 Surveillance Requirement which was issued on the same date in' Amendment No. 146. Inclusion of the word "or" in Surveillance Requirement 4.7.B.2.b which has been previously approved by the NRC is an administrative correction of an error and l
will not affect safe operation of the nuclear unit.
Information Supporting a Finding of No l
Significant Bazards Consideration l
The Commission has provided guidance concerning the
- l. application of the standards for determining whether license
[ amendments involve significant hazards considerations by providing l-certain examples (51 FR 7751). One of the examples of amendments I
i
-r
-- ~ -"
T. *
[
' Dockst Nos. 50-277.
, 50-278-License Nos. DPR-44
DPR .
that are considered not likely to involve significant hazards consideration is "(11) a change that constitutes an additional limitation, restriction or control not presently included in the !
technical specifications, e.g., a more stringent surveillance requirement." The proposed changes to the Technical Specifications 3.7.A.6.b, 4.7.A.6.b, and 4.7.E.3 impose additional control not presently included'in the_ Technical Specifications. Another example
'(Example i) of a change that involves no significant hazards $
considerations is a " purely administrative change to technical specifications:-for example, a change-to achieve consistency throughout the technical specifications, correction of an error, or-
- a. change in nomenclature". The proposed change to Technical Specification 4.7.B.2.b to add the word "or" is a purely
. administrative change to correct an error.as discussed'in the Safety e Assessment.
The proposed changes to the Peach Bottom operating licenses -
E do not constitute a significant hazards consideration in that they
.do not: '
l i) Involve a significant increase in the probability or I-consequences of an accident previously evaluated.
L L
The proposed Technical Specification changes provide L additional means of ensuring operability of the new safety
[ grade pneumatic supply system and correct an administrative L
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._ , .. .~,. _ _ ___ . _-. _
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'g
, Dockot-Nos.1 50-277
' 278- l License Nos. DPR '
DPR-56
. error. .These changes serve to enhance plant safety and would not involve a significant increase in the probability or consequences of an accident as previously evaluated in Chapter 14 of the PBAPS Updated Final Safety Analysis Report.
, . 11) Create the possibility of a new or different kind of accident from any accident'previously evaluated.
The implementation of the new safety grade pneumatic supply 1 1
system was reviewed and accepted by the NRC. 2
-Implementation of-a surveillance requirement to demonstrate an adequatefsupply of liquid nitrogen and operability.of ;
P the system will not create the possibility of a new or.
different kind of accident from any previously evaluated.
The correction of an administrative error will not' create the possibility of a new or different kind of accident from any previously evaluated.
l iii) Involve a significant reduction in a margin of safety.
} The proposed surveillance provides additional assurance i-
- e. that the new safety grade pneumatic supply system will l-1:
function as designed; thus, there is no reduction in a margin of safety. The correction of an administrative error does not reduce a margin of safety.
1
4 "
Docket Nos. 50-277
,_ 50-278 License Nos. DPR-44 DPR-56 i
Information Supporting an Environmental Impact Assessment:
An environmental impact assessment is not required for the
. changes proposed by this Application because the changes conform to ,
the criteria for " actions eligible for categorical exclusion" as ,
specified in 10 CPR 51.22(c)(9). The Application involves no significant hazards consideration as demonstrated in the preceding section. The Application involves no significant change in the
. types or significant increase in the amounts of any effluents that may be released offsite, and there is no significant increase in.
I individual or cumulative occupational ~ radiation exposure.
Conclusion The Peach Bottom Plant Operations Review Committee and the Nuclear Review Board have reviewed the proposed changes to the Technical Specifications-and have concluded that they do not involve an unreviewed safety question and will not endanger the health'and ,
safety of the public.
l