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| {{#Wiki_filter:%'C'aPennsylvania Power8LightCompanyTwoNorthNinthStreet~Allentown, PA18101~215/770.5151 NormanW.CurtisVicePresident-Engineering 6Construction-Nuclear 215/770-7501 DEC61984DirectorofNuclearReactorRegulation Attention: | | {{#Wiki_filter:%'C'a Pennsylvania Power 8 Light Company Two North Ninth Street~Allentown, PA 18101~215/770.5151 Norman W.Curtis Vice President-Engineering 6 Construction-Nuclear 21 5/770-7501 DEC 6 1984 Director of Nuclear Reactor Regulation Attention: |
| Mr.A.Schwencer, ChiefLicensing BranchNo.2DivisionofLicensing U.S.NuclearRegulatory Commission Washington, DC20555SUSQUEHANNA STEAMELECTRICSTATIONPROPOSEDAMENDMENTS 57TOLICENSENPF-14AND12TOLICENSENPF-22ER100450PLA-2370DocketNos.50-38750-388 | | Mr.A.Schwencer, Chief Licensing Branch No.2 Division of Licensing U.S.Nuclear Regulatory Commission Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENTS 57 TO LICENSE NPF-14 AND 12 TO LICENSE NPF-22 ER 100450 PLA-2370 Docket Nos.50-387 50-388 |
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| ==DearMr.Schwencer:== | | ==Dear Mr.Schwencer:== |
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| Thepurposeofthisletteristoproposeamendments totheSusquehanna SESUnit1andUnit2Technical Specifications inordertoavoidtheforcedshutdownofUnit2duringtheUnit1firstrefueling outage.PROBLEM:SSESUnit2currently dependsoncertainUnit1125-voltbatteries tosupportcommonloads;theseUnit1batteries aretherefore listedintheUnit2LCOsonDCsystems.SinceUnit1batteryloadprofiletestingmustbeperformed duringthefirstrefueling outage,anACTIONstatement mustbeenteredintheUnit2Technical Specifications.
| | The purpose of this letter is to propose amendments to the Susquehanna SES Unit 1 and Unit 2 Technical Specifications in order to avoid the forced shutdown of Unit 2 during the Unit 1 first refueling outage.PROBLEM: SSES Unit 2 currently depends on certain Unit 1 125-volt batteries to support common loads;these Unit 1 batteries are therefore listed in the Unit 2 LCOs on DC systems.Since Unit 1 battery load profile testing must be performed during the first refueling outage, an ACTION statement must be entered in the Unit 2 Technical Specifications. |
| TherequiredtestingwillforcetheshutdownofUnit2,sinceitcannotbeperformed withinthetwohoursallottedintheACTIONstatement.
| | The required testing will force the shutdown of Unit 2, since it cannot be performed within the two hours allotted in the ACTION statement. |
| PROPOSEDSOLUTION:
| | PROPOSED SOLUTION: A single line diagram of Channel"A" of the Unit 1 125-volt DC system is provided in Figure 1.PP&L has developed a.common load transfer scheme which will allow common loads to be powered from a 125-volt DC source on either unit through the use of manual transfer switches (see Figure 2).In several cases, the individual feeder breakers supply not only a common load, but: also a Unit 1 load (See Figure 3).Therefore, once the loads have been transferred to the Unit 2'source, the Unit 1 loads (hereinafter called"tag along loads")will be energized from a Unit 2 source.In the revised design, non-Class 1E loads will usually be transferred between two different Unit 1 sources;some will be transferred between Unit 1 and Unit 2 sources.In order to maintain division/channel separation all Class 1E loads being transferred to support the transfer of common loads (again, this includes some tag along loads)will be transferred between the Unit 1 and corresponding Unit 2 battery.80i2i80b2i 84i20b PDR ADOCK 05000l387 P PDR Al gC~+four jP t l4 j rill rrf M ll'M r r' Hl Page 2 SSES PLA-2370 ER 100450 File 841-8 Hr.A.Schwencer PROPOSED TECHNICAL SPECIFICATION CHANGES: A mark-up of the changes needed to support the proposed revised design is attached.For t'e Unit 1 specifications, the following changes were made: pages 3/4 8-10: The Unit 2 batteries, from which common and tag along loads may now be powered, are added to the LCO.A footnote is provided to remove them as an LCO requirement under situations when they are not supporting Unit 1 operation. |
| AsinglelinediagramofChannel"A"oftheUnit1125-voltDCsystemisprovidedinFigure1.PP&Lhasdeveloped a.commonloadtransferschemewhichwillallowcommonloadstobepoweredfroma125-voltDCsourceoneitherunitthroughtheuseofmanualtransferswitches(seeFigure2).Inseveralcases,theindividual feederbreakerssupplynotonlyacommonload,but:alsoaUnit1load(SeeFigure3).Therefore, oncetheloadshavebeentransferred totheUnit2'source,theUnit1loads(hereinafter called"tagalongloads")willbeenergized fromaUnit2source.Inthereviseddesign,non-Class 1Eloadswillusuallybetransferred betweentwodifferent Unit1sources;somewillbetransferred betweenUnit1andUnit2sources.Inordertomaintaindivision/channel separation allClass1Eloadsbeingtransferred tosupportthetransferofcommonloads(again,thisincludessometagalongloads)willbetransferred betweentheUnit1andcorresponding Unit2battery.80i2i80b2i 84i20bPDRADOCK05000l387 PPDRAlgC~+fourjP tl4jrillrrfMll'Mrr' HlPage2SSESPLA-2370ER100450File841-8Hr.A.Schwencer PROPOSEDTECHNICAL SPECIFICATION CHANGES:Amark-upofthechangesneededtosupporttheproposedreviseddesignisattached.
| | ACTION a was revised to affect Unit 1 equipment only.ACTION b is provided on insert A to cover the common and tag along load transfer in the event that a Unit 2 battery supporting Unit 1 operation is inoperable.'CTION;c is provided, to cover the realignment of Unit 1 loads to,their normal Unit 1 source once that source has been restored to OPERABLE status.Finally, ACTION b has been relettered. |
| Fort'eUnit1specifications, thefollowing changesweremade:pages3/48-10:TheUnit2batteries, fromwhichcommonandtagalongloadsmaynowbepowered,areaddedtotheLCO.AfootnoteisprovidedtoremovethemasanLCOrequirement undersituations whentheyarenotsupporting Unit1operation.
| | P"I 4 o page 3/4 8-11: ACTION c has been relettered. |
| ACTIONawasrevisedtoaffectUnit1equipment only.ACTIONbisprovidedoninsertAtocoverthecommonandtagalongloadtransferintheeventthataUnit2batterysupporting Unit1operation isinoperable.'CTION;c isprovided, tocovertherealignment ofUnit1loadsto,theirnormalUnit1sourceoncethatsourcehasbeenrestoredtoOPERABLEstatus.Finally,ACTIONbhasbeenrelettered.
| | o page 3/4 8-12: The load profile for the Unit 1 Channel"B" battery has been revised to provide margin for future load additions,'should they occur.Insert B provides the load profiles for the Unit 2 batteries that are now required by the revised LCO.o page 3/4 8-15: See discussion for page 3/4 8-10.o page 3/4 8-16: ACTIONS c and d have been relettered. |
| P"I4opage3/48-11:ACTIONchasbeenrelettered. | | o page 3/4 8-17: As on 3/4 8-10, required Unit 2 equipment has been added to the LCO with a footnote to govern when it is required to support Unit 1 operation. |
| opage3/48-12:TheloadprofilefortheUnit1Channel"B"batteryhasbeenrevisedtoprovidemarginforfutureloadadditions,
| | o page 3/4 8-18: See above discussion on 3/4 8-17.Also, as discussed on 3/4 8-10 for sources, appropriate ACTION statements have been proposed on insert D for the affected DC load groups.o page 3/4 8-20: See discussion on 3/4 8-17.o page 3/4 8-21: "And/or" has been revised to just"or" for consistency with the LCO requirement on page 3/4 8-20.Insert E is provided again for controls over common load transfer and restoration of normal alignment. |
| 'shouldtheyoccur.InsertBprovidestheloadprofilesfortheUnit2batteries thatarenowrequiredbytherevisedLCO.opage3/48-15:Seediscussion forpage3/48-10.opage3/48-16:ACTIONScanddhavebeenrelettered. | | For the Unit 2 specifications similar changes were made to each section.The only significant differences are on the inserts (A through E)which provide one, not two ACTION statements. |
| opage3/48-17:Ason3/48-10,requiredUnit2equipment hasbeenaddedtotheLCOwithafootnotetogovernwhenitisrequiredtosupportUnit1operation.
| | The ACTION statement provided is different than the first ACTION on each Unit 1 insert in that it does not apply to any Unit 1 (tag along)loads.This is because Unit 2 requires only the common loads to support its operation. |
| opage3/48-18:Seeabovediscussion on3/48-17.Also,asdiscussed on3/48-10forsources,appropriate ACTIONstatements havebeenproposedoninsertDfortheaffectedDCloadgroups.opage3/48-20:Seediscussion on3/48-17.opage3/48-21:"And/or"hasbeenrevisedtojust"or"forconsistency withtheLCOrequirement onpage3/48-20.InsertEisprovidedagainforcontrolsovercommonloadtransferandrestoration ofnormalalignment.
| | The second ACTION proposed in the Unit 1 inserts covers the restoration of the normal Unit 1 alignment with respect to unitized loads.Since no Unit 2 loads C 1 il'i f m t 1L II I""I I'I DEC 6 1984 Page 3 SSES PLA-2370 ER 100450 File 841-8 Mr.A.Schwencer are being transferred due to this change, such an ACTION is not required in the Unit 2 specifications. |
| FortheUnit2specifications similarchangesweremadetoeachsection.Theonlysignificant differences areontheinserts(AthroughE)whichprovideone,nottwoACTIONstatements.
| | NO SIGNIFICANT HAZARDS CONSIDERATIONS: |
| TheACTIONstatement providedisdifferent thanthefirstACTIONoneachUnit1insertinthatitdoesnotapplytoanyUnit1(tagalong)loads.ThisisbecauseUnit2requiresonlythecommonloadstosupportitsoperation.
| | I.The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated, for the following reasons: Each unit has four independent 125-volt DC power sources.The FSAR analysis shows that a unit can be safely shut down with any one 125-volt DC power source disabled (Section 8.3).Based on the revised design, one 125-volt DC source would fail due to a fault in a Unit 1 tag along load if both upstream protective devices (fuse and distribution panel breaker)failed.The more likely result of a fault on a Unit 1 tag along load would be loss of an individual circuit.Therefore, the most probable failure is less severe than the loss of an entire power source, which has been previously evaluated. |
| ThesecondACTIONproposedintheUnit1insertscoverstherestoration ofthenormalUnit1alignment withrespecttounitizedloads.SincenoUnit2loads C1il'ifmt1LIII""II'I DEC61984Page3SSESPLA-2370ER100450File841-8Mr.A.Schwencer arebeingtransferred duetothischange,suchanACTIONisnotrequiredintheUnit2specifications.
| | Finally, the Unit 2 batteries have been analyzed and do have sufficient stored energy to operate all necessary loads for the design basis interval of four hours, after loss of AC power and assuming the loss of the battery charger.II.The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| NOSIGNIFICANT HAZARDSCONSIDERATIONS:
| | As stated above, the probable failure as a result of the revised design is within the bounds of the previous FSAR analysis, and battery capacity is sufficient to meet design commitments. |
| I.Theproposedchangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, forthefollowing reasons:Eachunithasfourindependent 125-voltDCpowersources.TheFSARanalysisshowsthataunitcanbesafelyshutdownwithanyone125-voltDCpowersourcedisabled(Section8.3).Basedonthereviseddesign,one125-voltDCsourcewouldfailduetoafaultinaUnit1tagalongloadifbothupstreamprotective devices(fuseanddistribution panelbreaker)failed.ThemorelikelyresultofafaultonaUnit1tagalongloadwouldbelossofanindividual circuit.Therefore, themostprobablefailureislessseverethanthelossofanentirepowersource,whichhasbeenpreviously evaluated. | | Therefore no new or different possibility exist.III.The proposed changes do not involve a significant reduction in a margin of safety.Based on the existence of sufficient battery capacity, the increased reliability of Unit 1 due to continuity of p'ower, and the fact that the worst case failure due to the new design is consistent with previous analysis, one can conclude that the existing margin of safety has not been reduced.Based upon the considerations presented above, this change appears to fall under an example as stated in 48FR14870, Column 3, paragraph (vi).PPSL does note that this change presents a deviation from our previous FSAR commitments to Regulatory Guide 1.81, and upon approval of this change we will take the appropriate steps to revise the FSAR accordingly. |
| Finally,theUnit2batteries havebeenanalyzedanddohavesufficient storedenergytooperateallnecessary loadsforthedesignbasisintervaloffourhours,afterlossofACpowerandassumingthelossofthebatterycharger.II.Theproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. | | ~>~~V'I DEC 6 1984 Page 4 SSES PLA-2370 ER 100450 File 841-8 Mr.A.Schwencer IMPLEMENTATION SCHEDULE: As stated at the beginning of this proposal, the most immediate problem which is being avoided as a result of this change is the shutdown of Unit 2 during the Unit 1 first refueling outage.Therefore, it is imperative that PP&L receive approval of the proposed change prior to or very early into the outage so that battery load profile testing can proceed on schedule and as a result of this modification, not force the shutdown of Unit 2.The appropriate fees pursuant t'o 10CFR170.22 have been enclosed.Any questions on this matter should be directed to Mr.R.Sgarro at (215)770-7855.We are willing to meet with you at your convenience to further discuss this matter.Very truly ours, N.W.Curtis Vice President-Engineering |
| Asstatedabove,theprobablefailureasaresultofthereviseddesigniswithintheboundsofthepreviousFSARanalysis, andbatterycapacityissufficient tomeetdesigncommitments.
| | &Construction-Nuclear Enclosures cc: M.J.Campagnone US NRC R.H.Jacobs US NRC T.M.Gerusky, Director Bureau of Radiation Protection Pa.Dept.of Environmental Resources P.0.Box 2063 Harrisburg, PA 17120 4~P H~I H\P~'!I I I e H T H I''gt t;*r e r HT~p"'ll P PI~I~~I'~~~Hl P~r~P I e d IP}} |
| Therefore nonewordifferent possibility exist.III.Theproposedchangesdonotinvolveasignificant reduction inamarginofsafety.Basedontheexistence ofsufficient batterycapacity, theincreased reliability ofUnit1duetocontinuity ofp'ower,andthefactthattheworstcasefailureduetothenewdesignisconsistent withpreviousanalysis, onecanconcludethattheexistingmarginofsafetyhasnotbeenreduced.Basedupontheconsiderations presented above,thischangeappearstofallunderanexampleasstatedin48FR14870, Column3,paragraph (vi).PPSLdoesnotethatthischangepresentsadeviation fromourpreviousFSARcommitments toRegulatory Guide1.81,anduponapprovalofthischangewewilltaketheappropriate stepstorevisetheFSARaccordingly. | |
| ~>~~V'I DEC61984Page4SSESPLA-2370ER100450File841-8Mr.A.Schwencer IMPLEMENTATION SCHEDULE: | |
| Asstatedatthebeginning ofthisproposal, themostimmediate problemwhichisbeingavoidedasaresultofthischangeistheshutdownofUnit2duringtheUnit1firstrefueling outage.Therefore, itisimperative thatPP&Lreceiveapprovaloftheproposedchangepriortoorveryearlyintotheoutagesothatbatteryloadprofiletestingcanproceedonscheduleandasaresultofthismodification, notforcetheshutdownofUnit2.Theappropriate feespursuantt'o10CFR170.22 havebeenenclosed.
| |
| Anyquestions onthismattershouldbedirectedtoMr.R.Sgarroat(215)770-7855.
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| Wearewillingtomeetwithyouatyourconvenience tofurtherdiscussthismatter.Verytrulyours,N.W.CurtisVicePresident-Engineering
| |
| &Construction-Nuclear Enclosures cc:M.J.Campagnone USNRCR.H.JacobsUSNRCT.M.Gerusky,DirectorBureauofRadiation Protection Pa.Dept.ofEnvironmental Resources P.0.Box2063Harrisburg, PA17120 4~PH~IH\P~'!IIIeHTHI''gtt;*rerHT~p"'llPPI~I~~I'~~~HlP~r~PIedIP}} | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999
Forwards Change J to SSES Security Training & Qualification Plan.Without Encl
ML18040B2951999-09-0808 September 1999
Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early
PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999
Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl
ML18040A9741999-07-0808 July 1999
Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant
ML20207G5051999-06-0707 June 1999
Informs That NRC Office of NRR Reorganized Effective 990328.As Part of Reorganization,Divison of Licensing Project Management Created
PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999
Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21
ML18040A9731999-05-24024 May 1999
Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant
ML20195B2181999-05-20020 May 1999
Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790
ML18040B2901999-04-30030 April 1999
Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed
PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999
Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790
ML17164A9891999-03-12012 March 1999
Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl
ML18040A9691999-03-12012 March 1999
Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML18040A9721999-03-11011 March 1999
Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031
PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999
Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790
ML20203G5821999-02-17017 February 1999
Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Released in Entirety. Documents Listed in App D Being Withheld in Part (Ref FOIA Exemption 5)
ML20202F4761999-01-29029 January 1999
First Partial Response to FOIA Request for Documents.Records in App a Encl & Being Released in Entirety.App B Records Being Withheld in Part (Ref FOIA Exemption 7C)
ML18040A9671999-01-29029 January 1999
Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125
ML18040A9681999-01-29029 January 1999
Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031
ML18040A9651999-01-12012 January 1999
Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML18030A1021998-12-16016 December 1998
Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs
ML18030A4331998-11-25025 November 1998
Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50
ML20195J9101998-11-18018 November 1998
Forwards Notice of Withdrawal of Application for Amends to Facility Operating Licenses (Notice).Notice Has Been Filed with Ofc of Fr.Amends Would Have Revised TS to Eliminate HPCI Pump auto-transfer on High Suppression Pool Level
ML20155F7201998-11-0303 November 1998
Final Response to FOIA Request for Documents.Documents Listed in App B Being Encl & Being Released in Entirety. Documents Listed in App C Being Withheld in Part (Ref Exemption 7C)
ML18026A2941998-10-19019 October 1998
Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage
PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998
Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21
ML18030A1001998-10-12012 October 1998
Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs
ML18030A4321998-10-12012 October 1998
Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized
ML18030A4311998-09-29029 September 1998
Forwards Rev 27 & 28 to SSES Emergency Plan
ML20151W4951998-09-10010 September 1998
Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs for Region I
IR 05000387/19980081998-09-0808 September 1998
Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved
ML18030A0991998-09-0808 September 1998
Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved
ML18026A4961998-08-31031 August 1998
Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations
IR 05000387/19980031998-08-31031 August 1998
Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations
ML20202F5501998-07-17017 July 1998
Responds to PP&L Corp Auditing Repts 739459-97,739459-1-97 & 739459-2-98 Re SSES Investigations Into Missed Alarm Tests
ML20236P9451998-07-15015 July 1998
Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258)
ML18030A4291998-07-0808 July 1998
Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue
ML18017A2181998-07-0808 July 1998
Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance
ML18026A2901998-06-0909 June 1998
Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed
ML18026A2891998-05-22022 May 1998
Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods
ML18026A4941998-05-12012 May 1998
Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document
ML20202H1331998-04-16016 April 1998
Partially Deleted Ltr Re Concerns Raised to NRC Concerning PP&L Susquehanna Facility
NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable1998-04-15015 April 1998
Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable
ML20216B6811998-04-0101 April 1998
First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Being Released in Entirety
ML17159A2341998-03-30030 March 1998
Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event
PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998
Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790
ML17159A1781998-03-0202 March 1998
Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4.
PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998
Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl
PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998
Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213
ML20203M5071998-02-26026 February 1998
Final Response to FOIA Request for Documents.Records in App a Being Placed in PDR & Encl.Records in App B Partially Withheld (Ref FOIA Exemption 6)
ML20203B5931998-02-23023 February 1998
Ack Receipt of & Wire in Amount of $55,000 in Payment for Civil Penatly Proposed by NRC Ltr . Corrective Actions Will Be Examined During Future Inspections
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999
Forwards Change J to SSES Security Training & Qualification Plan.Without Encl
ML18040B2951999-09-0808 September 1999
Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early
PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999
Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl
ML18040A9741999-07-0808 July 1999
Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant
PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999
Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21
ML18040A9731999-05-24024 May 1999
Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant
ML20195B2181999-05-20020 May 1999
Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790
ML18040B2901999-04-30030 April 1999
Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed
PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999
Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790
ML18040A9691999-03-12012 March 1999
Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML17164A9891999-03-12012 March 1999
Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl
ML18040A9721999-03-11011 March 1999
Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031
PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999
Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790
ML18040A9681999-01-29029 January 1999
Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031
ML18040A9671999-01-29029 January 1999
Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125
ML18040A9651999-01-12012 January 1999
Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML18030A1021998-12-16016 December 1998
Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs
ML18030A4331998-11-25025 November 1998
Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50
ML18026A2941998-10-19019 October 1998
Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage
ML18030A4321998-10-12012 October 1998
Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized
ML18030A1001998-10-12012 October 1998
Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs
PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998
Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21
ML18030A4311998-09-29029 September 1998
Forwards Rev 27 & 28 to SSES Emergency Plan
ML18030A0991998-09-0808 September 1998
Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved
IR 05000387/19980081998-09-0808 September 1998
Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved
ML18026A4961998-08-31031 August 1998
Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations
IR 05000387/19980031998-08-31031 August 1998
Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations
ML18017A2181998-07-0808 July 1998
Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance
ML18030A4291998-07-0808 July 1998
Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue
ML18026A2901998-06-0909 June 1998
Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed
ML18026A2891998-05-22022 May 1998
Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods
ML18026A4941998-05-12012 May 1998
Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document
ML17159A2341998-03-30030 March 1998
Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event
PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998
Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790
PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998
Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl
ML17159A1781998-03-0202 March 1998
Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4.
PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998
Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213
ML20216B7031998-02-22022 February 1998
Partially Deleted Ltr Requesting Copy of OI Rept on Plant, Unit 2,case 1-96-039
PLA-4851, Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing1998-02-18018 February 1998
Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing
ML20203M5791998-02-10010 February 1998
Enters Appeal Due to Lack of Response to FOIA Request 97-473
ML18030A0971998-02-0202 February 1998
Forwards Proprietary Response to RAI Re Proposed License Amend 209 to TS Supporting Cycle 11 Reload.Proprietary Info Withheld,Per 10CFR2.790
ML20203G6071998-01-26026 January 1998
Forwards Redacted Version of Pp&L,Inc Corporate Auditings Interim Rept 739459-97,dtd 971015 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept
IR 05000387/19970031998-01-0606 January 1998
Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998
ML18030A4071998-01-0606 January 1998
Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998
ML18017A2931998-01-0606 January 1998
Provides Responses to Improved TS Section 3.8 Per 970324 NRC Rai.Schedule 980628 for Improved TS Implementation. Submittal of Revised Specifications Is Planned for Jan 1998
PLA-4828, Expresses Appreciation for Support Received by Former Project Manager C Poslusny1997-12-29029 December 1997
Expresses Appreciation for Support Received by Former Project Manager C Poslusny
IR 05000387/19970041997-12-22022 December 1997
Resolves Commitments Made in Response to NOV Issued As Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval
ML18026A4901997-12-22022 December 1997
Resolves Commitments Made in Response to NOV Issued as Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval
ML20203M5741997-12-0505 December 1997
FOIA Request for Copy of Latest OI Rept on Susquehanna Ses Including All Exhibits & for Any Other Communication Between NRC & Susquehanna Ses/Pp&L
PLA-4818, Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept1997-12-0404 December 1997
Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARML18026A3941990-09-0101 September 1990
Requests Waiver of Compliance from Tech Spec 3.8.1.1 to Evaluate Increase in Action from 72 H to 15 Days Re Ac Sources Based on 900829 Borescopic Insp of Emergency Diesel Generator
ML17157A2741990-08-0808 August 1990
Forwards Topical Rept PL-NF-90-001, Application of Reactor Analysis Methods for BWR Design & Analysis.
IR 05000387/19900801990-08-0303 August 1990
Responds to Violations Noted in Insp Repts 50-387/90-80 & 50-388/90-80.Corrective Actions:Util Conducted Operator Training on How to Implement Eops If Suppression Chamber Pressure Not Available
ML18030A0741990-08-0303 August 1990
Responds to Violations Noted in Insp Repts 50-387/90-80 & 50-388/90-80.Corrective Actions:Util Conducted Operator Training on How to Implement EOPs If Suppression Chamber Pressure Not Available
ML18026A2351990-07-0202 July 1990
Forwards Application for Proposed Amend 132 to License NPF-14,revising Tech Spec to Support Cycle 6 Reload
ML18030A0721990-06-19019 June 1990
Forwards Rev 1 to SEA-EE-183, Evaluation of Unit 1 Computer Class 1E - Non-Class 1E Interfaces & Rev 1 to SEA-EE-184, Evaluation of Unit 1 Annunciator Class 1E - Non-Class 1E Interfaces.
ML18026A3931990-06-0707 June 1990
Requests NRC Approval to Install Mod at Plant Determined to Constitute Unreviewed Safety Question When Evaluated.Util Will Implement Administrative Controls to Ensure Larger Min Vol Met for Diesel E Prior to Tech Spec Change
ML18030A3671990-05-14014 May 1990
Forwards Proprietary Conclusions of Investigation Re Two False Negative Analytical Results from Two Blind Spike Urine Samples.Investigation Satisfactorily Evaluated Samples. Encl Withheld (Ref 10CFR2.790)
ML20043A2461990-05-11011 May 1990
Forwards Draft of Proposed Decommissioning Financial Assurance Plan,Per 10CFR50.33 & 50.75,for Review.Telcon Scheduled for 900515 to Discuss Comments
ML18030A0711990-03-19019 March 1990
Responds to Questions Delineated in 900131 Ltr Re Diesel Generator Events That Occurred During Sept & Oct 1989.Draft Procedures for Proposed Intake Air Temp Test Program Transmitted to NRC on 900205.Revised Procedures Encl
ML18017A1871990-02-15015 February 1990
Forwards Books 1 & 2 to, Unit 2 Third Refueling & Insp Outage;Outage Summary Rept.
IR 05000387/19890331990-02-0505 February 1990
Responds to NRC 900105 Ltr Re Violations Noted in Insp Repts 50-387/89-33 & 50-388/89-31.Corrective Actions:Rhr Svc Water Pump 2P506B Remains in Inoperable Status Until Cause of Deviation Determined & Condition Corrected
ML18030A0701990-02-0505 February 1990
Responds to NRC 900105 Ltr Re Violations Noted in Insp Repts 50-387/89-33 & 50-388/89-31.Corrective Actions:Rhr Svc Water Pump 2P506B Remains in Inoperable Status Until Cause of Deviation Determined & Condition Corrected
ML18040A9601990-02-0202 February 1990
Forwards Schedules That Provide Details of Tasks Required to Complete Activities Re Diesel Generators & Advises of Plan to Have Spare Parts on Site in Timely Manner to Support Each Diesel Insp
ML20006B4501990-01-25025 January 1990
Forwards Preliminary Scope & Schedule for Security Upgrade Project.Encl Withheld (Ref 10CFR73.21)
ML17156B6031990-01-25025 January 1990
Forwards NPDES Discharge Monitoring Rept for Dec 1989 & State of Pa,Dept of Environ Resources Monthly Facility Rept Form (01-112).Noncompliances for Zinc on Cooling Tower Blowdown on 891228 & for Missed Sample Noted
ML18040B2671990-01-0505 January 1990
Forwards Rev 0 to SEA-CW-037, Analysis of B & C 1989 Diesels Failure. Rept Details Util Analysis of Overpressurization Incidents Which Occurred in Sept & Oct 1989 of Diesel Generators
ML18040B2651989-11-27027 November 1989
Forwards Response to Generic Ltr 89-21.Table of USIs for Which Technical Resolution Has Been Achieved Encl
ML19325F1991989-11-0909 November 1989
Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Util Has Developed & Issued Procedure Which Includes Safeguards Contingency Planning Using Approach Noted in Generic Ltr
ML19325D7411989-10-19019 October 1989
Forwards Application for Amends 126 & 77 to Licenses NPF-14 & NPF-22,respectively,requesting Emergency Temporary Relief from Certain Requirements of Tech Specs 3.2.2 on One Time Basis for Period of 3 Months
ML19325C3771989-10-11011 October 1989
Forwards Change DD to Physical Security Plan.Change Withheld (Ref 10CFR73.21)
ML18040B2581989-10-0202 October 1989
Forwards Final Response to Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Listed Items Included in Previous & Current Ref Responses
ML18040A9441989-09-12012 September 1989
Responds to Remaining Questions Raised During NRC Insp of Training Programs.Training Procedure Re Technical Exam Bank Instrumentation & Control Training Exams.Health Physics Technicians Trained Re High Radiation Levels
PLA-3251, Forwards Response to Regulatory Effectiveness Review Rept. Util Established Team to Evaluate Appropriate Scope for Planned Major Project to Upgrade Security.Scope of Project to Be Finalized & Approved in Nov 1989.Response Withheld1989-08-31031 August 1989
Forwards Response to Regulatory Effectiveness Review Rept. Util Established Team to Evaluate Appropriate Scope for Planned Major Project to Upgrade Security.Scope of Project to Be Finalized & Approved in Nov 1989.Response Withheld
ML18040A9421989-08-22022 August 1989
Requests Concurrence W/Scheduling of 1990 Annual NRC Observed Emergency Preparedness Exercise at Plant on 900502. Concurrence Requested by 890930
ML18040B2531989-08-10010 August 1989
Discusses Insp of Operational Status of Emergency Preparedness Program.Susquehanna Review Committee 1987 & 1988 Emergency Plan Audits Encl W/Other Supporting Documentation
ML20246A0191989-06-30030 June 1989
Submits Comments on Containment Performance Improvement Program (Cpi).Believes Program Will Be Generic Approach to Improving Containment Performance During Severe Accident
PLA-3218, Submits Info Re Settlement Agreements for Discrimination Matters Arising Under Energy Reorganization Act of 1974. No Settlements Made Between Licensee & Any Employees in Section 210 Proceedings1989-06-27027 June 1989
Submits Info Re Settlement Agreements for Discrimination Matters Arising Under Energy Reorganization Act of 1974. No Settlements Made Between Licensee & Any Employees in Section 210 Proceedings
ML18040B2501989-06-20020 June 1989
Forwards Summary Rept of Safety Evaluations Approved During 1988.Changes Include Backseating Control Box to Electrically Backset HV-202168 to Reduce Steam Leakage & Rerouting Condensate Supply Line to Main Condenser Keepfill
PLA-3194, Forwards Change CC to Physical Security Plan.Change Withheld (Ref 10CFR73.21)1989-05-30030 May 1989
Forwards Change CC to Physical Security Plan.Change Withheld (Ref 10CFR73.21)
ML18040A9301989-04-28028 April 1989
Responds to 890322 Request for Addl Info Re Plant Fire Protection Review Rept.Analysis of Circuits Having Potential for Being Impacted by Fire Resulting in Multiple High Impedence Faults Will Be Completed by Last Quarter 1989
ML18040B2441989-04-14014 April 1989
Forwards Application for Amends to Licenses NPF-14 & NPF-22, Resulting from Mods Performed to Essential Svc Water Sys,Per 10CFR50,App R,Consisting of Proposed Amends 23 & 70
PLA-3173, Forwards Change Bb to Physical Security Plan.Encl Withheld (Ref 10CFR73.21)1989-03-22022 March 1989
Forwards Change Bb to Physical Security Plan.Encl Withheld (Ref 10CFR73.21)
ML18040A9271989-03-10010 March 1989
Forwards Rev 6 to ISI-T-100.0 for Unit 1 & Rev 3 to ISI-T-200.0 for Unit 2 Pump & Valve Inservice Insp Testing Program.
ML18040A9261989-03-0707 March 1989
Discusses Util Position Re Completion & Implementation of NRC Requested Actions Specified in Suppl 1 to NRC Bulletin 88-007, Power Oscillations in Bwrs.
ML17156B0131989-02-0202 February 1989
Forwards Proprietary Rept & Affidavit Supporting Proposed Amend 119 to License NPF-14
ML17156A9771988-12-15015 December 1988
Forwards Rev 11 to Susquehanna Units 1 & 2 Emergency Plan
ML18040B2331988-11-22022 November 1988
Forwards Listed Addl Info Re Plant Fire Protection Review rept.W/16 Oversize Drawings
ML17156A9211988-11-0909 November 1988
Forwards Proprietary GE Rept, Tech Spec Improvement Analysis for Reactor Protection Sys for Susquehanna Steam Electric Station,Units 1 & 2. Rept Withheld (Ref 10CFR2.790)
ML18040A9111988-09-15015 September 1988
Informs That Mods Re Fire Barrier Upgrades,Hvac Fan Switches,Ct Secondaries & Raceway Wrapping Completed Except as Listed
ML18040A9101988-08-10010 August 1988
Forwards Application for Amend to License NPF-14,extending Operation During Cycle 4 W/One Circulation Loop Out of Svc. Fee Paid
ML18040B2221988-08-10010 August 1988
Responds to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Staff Position on Matls, Water Chemistry,Crack Evaluation & Repair Criteria & Insp Schedules Among Topics Addressed.Flaw Evaluations Encl
ML18040B2201988-07-27027 July 1988
Forwards Comments to Each Specific SALP Category,Per 880707 Meeting W/Nrc.Presentations from Meeting Also Encl
ML18040A9061988-07-21021 July 1988
Forwards GE Rept, Susquehanna Unit 1 CRD Housing Cap Screw Corrosion. Rept Completes Action on Item
ML18040A9031988-07-19019 July 1988
Forwards Approved Version of Topical Rept PL-NF-87-001-A, Qualification of Steady State Core Physics Methods for BWR Design & Analysis, Per 880428 Ltr
ML18040A9041988-07-19019 July 1988
Forwards Rev 39 to Updated FSAR for Susquehanna Steam Electric Station Units 1 & 2 Per 10CFR50.71
ML18040B2131988-06-24024 June 1988
Forwards 1987 Annual Rept for Allegheny Electric Cooperative,Inc
ML18040A9021988-06-15015 June 1988
Provides Revised Response to NRC 871130 Ltr Re Violations Noted in Insp Repts 50-387/87-19 & 50-388/87-19.Corrective Actions:Incumbent Will Be Removed from Emergency Plan Position of Radiation Protection Coordinator
PLA-3028, Responds to Suppl 1 to Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. No Revs to Design Review for Original Bulletin Required as Result of Suppl1988-05-31031 May 1988
Responds to Suppl 1 to Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. No Revs to Design Review for Original Bulletin Required as Result of Suppl
ML18040A8691988-04-0606 April 1988
Forwards Application for Proposed Amends 110 & 61 to Licenses NPF-14 & NPF-22,respectively,revising Tech Specs Re Radiation Monitoring Instrumentation.Fee Paid
1990-09-01
[Table view] |
Text
%'C'a Pennsylvania Power 8 Light Company Two North Ninth Street~Allentown, PA 18101~215/770.5151 Norman W.Curtis Vice President-Engineering 6 Construction-Nuclear 21 5/770-7501 DEC 6 1984 Director of Nuclear Reactor Regulation Attention:
Mr.A.Schwencer, Chief Licensing Branch No.2 Division of Licensing U.S.Nuclear Regulatory Commission Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENTS 57 TO LICENSE NPF-14 AND 12 TO LICENSE NPF-22 ER 100450 PLA-2370 Docket Nos.50-387 50-388
Dear Mr.Schwencer:
The purpose of this letter is to propose amendments to the Susquehanna SES Unit 1 and Unit 2 Technical Specifications in order to avoid the forced shutdown of Unit 2 during the Unit 1 first refueling outage.PROBLEM: SSES Unit 2 currently depends on certain Unit 1 125-volt batteries to support common loads;these Unit 1 batteries are therefore listed in the Unit 2 LCOs on DC systems.Since Unit 1 battery load profile testing must be performed during the first refueling outage, an ACTION statement must be entered in the Unit 2 Technical Specifications.
The required testing will force the shutdown of Unit 2, since it cannot be performed within the two hours allotted in the ACTION statement.
PROPOSED SOLUTION: A single line diagram of Channel"A" of the Unit 1 125-volt DC system is provided in Figure 1.PP&L has developed a.common load transfer scheme which will allow common loads to be powered from a 125-volt DC source on either unit through the use of manual transfer switches (see Figure 2).In several cases, the individual feeder breakers supply not only a common load, but: also a Unit 1 load (See Figure 3).Therefore, once the loads have been transferred to the Unit 2'source, the Unit 1 loads (hereinafter called"tag along loads")will be energized from a Unit 2 source.In the revised design, non-Class 1E loads will usually be transferred between two different Unit 1 sources;some will be transferred between Unit 1 and Unit 2 sources.In order to maintain division/channel separation all Class 1E loads being transferred to support the transfer of common loads (again, this includes some tag along loads)will be transferred between the Unit 1 and corresponding Unit 2 battery.80i2i80b2i 84i20b PDR ADOCK 05000l387 P PDR Al gC~+four jP t l4 j rill rrf M ll'M r r' Hl Page 2 SSES PLA-2370 ER 100450 File 841-8 Hr.A.Schwencer PROPOSED TECHNICAL SPECIFICATION CHANGES: A mark-up of the changes needed to support the proposed revised design is attached.For t'e Unit 1 specifications, the following changes were made: pages 3/4 8-10: The Unit 2 batteries, from which common and tag along loads may now be powered, are added to the LCO.A footnote is provided to remove them as an LCO requirement under situations when they are not supporting Unit 1 operation.
ACTION a was revised to affect Unit 1 equipment only.ACTION b is provided on insert A to cover the common and tag along load transfer in the event that a Unit 2 battery supporting Unit 1 operation is inoperable.'CTION;c is provided, to cover the realignment of Unit 1 loads to,their normal Unit 1 source once that source has been restored to OPERABLE status.Finally, ACTION b has been relettered.
P"I 4 o page 3/4 8-11: ACTION c has been relettered.
o page 3/4 8-12: The load profile for the Unit 1 Channel"B" battery has been revised to provide margin for future load additions,'should they occur.Insert B provides the load profiles for the Unit 2 batteries that are now required by the revised LCO.o page 3/4 8-15: See discussion for page 3/4 8-10.o page 3/4 8-16: ACTIONS c and d have been relettered.
o page 3/4 8-17: As on 3/4 8-10, required Unit 2 equipment has been added to the LCO with a footnote to govern when it is required to support Unit 1 operation.
o page 3/4 8-18: See above discussion on 3/4 8-17.Also, as discussed on 3/4 8-10 for sources, appropriate ACTION statements have been proposed on insert D for the affected DC load groups.o page 3/4 8-20: See discussion on 3/4 8-17.o page 3/4 8-21: "And/or" has been revised to just"or" for consistency with the LCO requirement on page 3/4 8-20.Insert E is provided again for controls over common load transfer and restoration of normal alignment.
For the Unit 2 specifications similar changes were made to each section.The only significant differences are on the inserts (A through E)which provide one, not two ACTION statements.
The ACTION statement provided is different than the first ACTION on each Unit 1 insert in that it does not apply to any Unit 1 (tag along)loads.This is because Unit 2 requires only the common loads to support its operation.
The second ACTION proposed in the Unit 1 inserts covers the restoration of the normal Unit 1 alignment with respect to unitized loads.Since no Unit 2 loads C 1 il'i f m t 1L II I""I I'I DEC 6 1984 Page 3 SSES PLA-2370 ER 100450 File 841-8 Mr.A.Schwencer are being transferred due to this change, such an ACTION is not required in the Unit 2 specifications.
NO SIGNIFICANT HAZARDS CONSIDERATIONS:
I.The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated, for the following reasons: Each unit has four independent 125-volt DC power sources.The FSAR analysis shows that a unit can be safely shut down with any one 125-volt DC power source disabled (Section 8.3).Based on the revised design, one 125-volt DC source would fail due to a fault in a Unit 1 tag along load if both upstream protective devices (fuse and distribution panel breaker)failed.The more likely result of a fault on a Unit 1 tag along load would be loss of an individual circuit.Therefore, the most probable failure is less severe than the loss of an entire power source, which has been previously evaluated.
Finally, the Unit 2 batteries have been analyzed and do have sufficient stored energy to operate all necessary loads for the design basis interval of four hours, after loss of AC power and assuming the loss of the battery charger.II.The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
As stated above, the probable failure as a result of the revised design is within the bounds of the previous FSAR analysis, and battery capacity is sufficient to meet design commitments.
Therefore no new or different possibility exist.III.The proposed changes do not involve a significant reduction in a margin of safety.Based on the existence of sufficient battery capacity, the increased reliability of Unit 1 due to continuity of p'ower, and the fact that the worst case failure due to the new design is consistent with previous analysis, one can conclude that the existing margin of safety has not been reduced.Based upon the considerations presented above, this change appears to fall under an example as stated in 48FR14870, Column 3, paragraph (vi).PPSL does note that this change presents a deviation from our previous FSAR commitments to Regulatory Guide 1.81, and upon approval of this change we will take the appropriate steps to revise the FSAR accordingly.
~>~~V'I DEC 6 1984 Page 4 SSES PLA-2370 ER 100450 File 841-8 Mr.A.Schwencer IMPLEMENTATION SCHEDULE: As stated at the beginning of this proposal, the most immediate problem which is being avoided as a result of this change is the shutdown of Unit 2 during the Unit 1 first refueling outage.Therefore, it is imperative that PP&L receive approval of the proposed change prior to or very early into the outage so that battery load profile testing can proceed on schedule and as a result of this modification, not force the shutdown of Unit 2.The appropriate fees pursuant t'o 10CFR170.22 have been enclosed.Any questions on this matter should be directed to Mr.R.Sgarro at (215)770-7855.We are willing to meet with you at your convenience to further discuss this matter.Very truly ours, N.W.Curtis Vice President-Engineering
&Construction-Nuclear Enclosures cc: M.J.Campagnone US NRC R.H.Jacobs US NRC T.M.Gerusky, Director Bureau of Radiation Protection Pa.Dept.of Environmental Resources P.0.Box 2063 Harrisburg, PA 17120 4~P H~I H\P~'!I I I e H T H Igt t;*r e r HT~p"'ll P PI~I~~I'~~~Hl P~r~P I e d IP
