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| {{#Wiki_filter:SUBJECT!'or war ds response to, D Kf senhut 810218 r equest.ter;addi fnto re nut eg 0694 commftments for fmplementatfon of emer'gency response facflftfes; DISTRIBUTION COOEt 8001S COPIKS RKCKIVKDSLTR ENCL TITLE: PSAR/FSAR AMDTS and Related Correspondence SIZE~t REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIOS)"ACCESSION NBR t 8104060586 DOC~DATE!81/04/02 NOTARIZED! | | {{#Wiki_filter:"ACCESSION NBR t 8104060586 REGULATORY INFORMATION DISTRIBUTION SYSTEM DATE! 81/04/02 t |
| .NO DOCKE~T¹: FACIL:50~387 Susquehanna Steam Klectrfc Statfonr Unft ii Pennsylvs 05000 8 50 388 Susquehanna Steam Electrfc Statfon>Unft 2'i Pennsylva 5000 88 AUTH',NAME'UTHOR AFFILIATION CtlRT IS i N.H.Pennsy 1 van f a Power 8 L f gh t Co~'KCIP~NAME, RECIPIENT AFFILIATION YOUNGBLOODrB,J
| | NOTARIZED! |
| ~Lfcensing Branch 1 NOTES!Send I8,E 3 copfes FSAR 8 all amends Send I8K 3 copfes FSAR&all amends;'5000387'5000388 RECIPIENT'D CODE/NAME" ACTION!A/O'ICENSNG RUSHBROOKeM | | (RIOS) |
| ~INTERNALS ACCID EVAL BR26 CHEM K9G BR 08 CORK'ERF BR 10 KMERG PREP ZZ'KOSC IENCKS 14 HYO/GKO" BR 15'8,E: 06 LIC, QUAL BR MECH KNG BR'8 NRC PDR OZl OP LIC BR PROC/TST'KV 20 R~8.8 S B R2P.', RKG FILE'1 TWO NG BR25 COPIES LTTR ENCL 0 0 1 1 1 1 1 0 1 2 2 3.3 1 1 1 1<<1 1 1 1 1 1 1 1 1 RECIPIENT'D COOK/NAME YOUNGBLOOOgB STARKrR~04 AUX SYS BR 07 CONT SYS BR 09 EFF TR SYS BR12 EQUIP QUAL BR13 HUM FACT KNG BR I8C SYS BR 16 LIC GUID BR MATL KNG BR 17 MPA OKLD POWER SYS BR io QA BR 21 RKAC SYS BR 23.SIT" ANAL BR 24 SYS INTERAC BR COPIES'TTR'NCL' 1 1 1-1 1 1 3 3 1 1 1 1 1 1 1 1 0 1 O.1 1 1 1 1 1 1 EXTERNAL!ACRS NSIC 27 05 16 16 1 LPDR 03 1 1 TOTAL NUMBER OF COPIES REQUIRED!LTTR" 57',ENCL'5i 4 PPILL TWO.NORTH NINTH STREET, ALLENTOWN, PA.18101 PHONE~(215)770-5151 NORMAN W.CURTIS Vice President. | | NO DOCKE~T ¹: |
| Engineering rL Construction-Nuclear TT0.5381 April 2, 1981 Mr.B.J.Youngblood, Chief Licensing Projects Branch 81 Division of Proj ect Management U.S.Nuclear Regulatory Commission Washington, D.C.20555 R 8 I ro SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY RESPONSE FACILITIES IMPLEMENTATION-RESPONSE TO GENERIC LETTER 81-10 ER 100450 FILE 841-12 PLA-704
| | DOC ii Pennsylvs |
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| | FACIL:50~387 Susquehanna Steam Klectrfc Statfonr Unft 05000 8 50 388 Susquehanna Steam Electrfc Statfon> Unft 2'i Pennsylva 5000 88 AUTH',NAME'UTHOR AFFILIATION CtlRT IS i N.H. Pennsy van f a Power 8 L f gh t Co 1 ~ |
| | ~ NAME, RECIPIENT AFFILIATION 'KCIP YOUNGBLOODrB,J ~ Lfcensing Branch 1 SUBJECT!'or war ds response to, D Kf senhut 810218 r equest. ter; addi fnto re nut eg 0694 commftments for fmplementatfon of emer'gency response facflftfes; DISTRIBUTION COOEt 8001S COPIKS RKCKIVKDSLTR ENCL SIZE ~ |
| | TITLE: PSAR/FSAR AMDTS and Related Correspondence NOTES!Send I8,E 3 copfes FSAR 8 all amends;'5000387'5000388 amends Send I8K 3 copfes FSAR & all RECIPIENT'D COPIES RECIPIENT'D COPIES'TTR'NCL' CODE/NAME" LTTR ENCL COOK/NAME ACTION! A/O'ICENSNG 0 YOUNGBLOOOgB RUSHBROOKeM ~ 0 STARKrR ~ 04 1 INTERNALS ACCID EVAL BR26 1 AUX SYS BR 07 1 1-CHEM K9G BR 08 1 1 CONT SYS BR 09 1 CORK'ERF BR 10 1 1 EFF TR SYS BR12 1 1 KMERG PREP 0 EQUIP QUAL BR13 3 3 IENCKS 14 HUM FACT KNG BR ZZ'KOSC 1 1 1 HYO/GKO" BR 2 2 I8C SYS BR 16 1 1 06 15'8,E: |
| | : 3. 3 LIC GUID BR 1 1 LIC, QUAL BR 1 1 MATL KNG BR 17 1 MECH KNG BR'8 1 MPA 1 0 NRC PDR OZl 1<< OKLD 1 O. |
| | OP LIC BR 1 1 POWER SYS BR io 1 1 PROC/TST'KV 20 1 1 QA BR 21 1 1 |
| | ~8.8 23. |
| | R RKG TWO FILE'1 NG S B R2P.', |
| | BR25 1 |
| | 1 1 |
| | 1 1 |
| | RKAC SYS BR SIT" ANAL BR 24 SYS INTERAC BR 1 |
| | 1 1 EXTERNAL! ACRS 27 16 16 LPDR 03 1 1 NSIC 05 1 TOTAL NUMBER OF COPIES REQUIRED! LTTR" 57 ',ENCL '5i |
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| ==Dear Mr.Youngblood:==
| | 4 PPILL TWO. NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE~ (215) 770-5151 NORMAN W. CURTIS Vice President. Engineering rL Construction-Nuclear TT0.5381 April 2, 1981 R |
| | 8 Mr. B. J. Youngblood, Chief I Licensing Projects Branch 81 Division of Proj ect Management U.S. Nuclear Regulatory Commission ro Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY RESPONSE FACILITIES IMPLEMENTATION-RESPONSE TO GENERIC LETTER 81-10 ER 100450 FILE 841-12 PLA-704 |
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| This letter is sent to provide the information requested in the Eisenhut letter on February 18 (Generic letter 81-10)on implementation of emergency response facilities. | | ==Dear Mr. Youngblood:== |
| The scope of information required by this letter was clarified by discussions with Mr.S.Ramos and Mr.E.Williams from the Division of Emergency Preparedness. | | |
| Based on these discussions, commitments have also been provided in response to requirements in NUREG 0694.Very truly ours, N.W.Curtis Vice President-Engineering | | This letter is sent to provide the information requested in the Eisenhut letter on February 18 (Generic letter 81-10) on implementation of emergency response facilities. The scope of information required by this letter was clarified by discussions with Mr. S. Ramos and Mr. E. Williams from the Division of Emergency Preparedness. Based on these discussions, commitments have also been provided in response to requirements in NUREG 0694. |
| &Construction-Nuclear DPM/mks cc: R.M.Stark-NRC POO~5 i/(810 40 605Vg PENNSYLVANIA POWER IL LIGHT COMPANY ATTACHMENT NUREG 0737 Commitments (Generic Letter 81-10)1.Detailed conceptual design descriptions for all emergency facilities will be submitted to the NRC by June 1, 1981 in accordance with NUREG 0737 Item III.A.1.2 issued by NRC Generic Letter 81-10.2.The Technical Support Center (TSC)will be functional by October 1, 1982 or prior to fuel load, whichever is later, in accordance with NUREG 0737 Item III.A.1.2 issued by NRC Generic Letter 81-10.NUREG 0696-Final Report will be used as a design guide.3.The Emergency Operations Facility (EOF)will be functional by October 1, 1982 or prior to fuel load, whichever is later, in accordance with NUREG 0737 Item III A.1.2 issued by NRC Generic Letter 81-10.NUREG 0696-Final Report will be used as a design guide.4.The Emergency Response Computer System (ERCS)will be implemented by the dates given or prior to fuel load, whichever is later.a)The Safety Parameter Display System (SPDS)will be operational in the control room and the TSC by October 1, 1982.The SPDS will not be operational in the EOF by October 1, 1982.This data display capability is expected to be available in the EOF by July 1, 1984.Data from the plant process computer will be provided in the EOF from October 1, 1982 until the SPDS is installed and operational. | | Very truly ours, N. W. Curtis Vice President-Engineering & Construction-Nuclear DPM/mks cc: R. M. Stark NRC POO~ |
| b)~The Nuclear Data Link (NDL)will not be operational by October 1, 1982.This data transmissi'on capability is expected to be available by July 1, 1984.c)An integrated system to support NUREG 0696-Final Report, Reg.Guide 1.97, and Reg.Guide 1.23 requirements for the SPDS, TSC, EOF, and NDL is expected to be operational by July 1, 1984.Detailed commitments for data will be provided to NRC when Reg.Guides 1.23 and 1.97 are finalized. | | 5 i/( |
| 5.The on-shift organization will be staffed and trained to meet the requirements of Table III.A.1.2-1 of NRC generic letter 81-10 (same as Table B-l to NUREG-0654, Rev.1).6.Additional personnel will be available by a call-in procedure to supplement the on-shift organization in the areas of communication, radiological assessment, technical support, repair and corrective action and radiation protection. | | PENNSYLVANIA POWER IL LIGHT COMPANY 810 40 605Vg |
| These personnel will be available within a thirty to sixty m'inute time frame. | | |
| 3'7.The Technical Support Center will be manned and fully functional within a thirty to sixty minute time frame.8.The Emergency Operations Facility will be manned and fully functional within four hours.The above commitments deviate from the requirements as follows.I 1.The ERCS will not be totally operational at the required date because of the unavailability of compatible equipment which meets all requirements. | | ATTACHMENT NUREG 0737 Commitments (Generic Letter 81-10) |
| Therefore the intent of requirements in NUREG 0696 will be met by using a combination of the SPDS (which will be operational by October 1, 1982)and modifications to the plant process computer.This interim system will be in operation from October 1, 1982 until the integrated system is available. | | : 1. Detailed conceptual design descriptions for all emergency facilities will be submitted to the NRC by June 1, 1981 in accordance with NUREG 0737 Item III.A.1.2 issued by NRC Generic Letter 81-10. |
| 2.NUREG 0737 (as issued by Generic Letter 81-10)requires ll people to report to the site within thirty minutes of notification and an additional 15 within sixty minutes of notification. | | : 2. The Technical Support Center (TSC) will be functional by October 1, 1982 or prior to fuel load, whichever is later, in accordance with NUREG 0737 Item III.A.1.2 issued by NRC Generic Letter 81-10. NUREG 0696-Final Report will be used as a design guide. |
| We cannot meet the ll people within thirty minutes requirement due to the general housing location of plant personnel with respect to the site.The overwhelming majority of personnel live approximately thirty to thirty-five minutes driving time from the site.Further, taking into" account the time it would take an individual to respond in the middle of the night plus possible adverse weather conditions, make it impossible to meet this requirement. | | : 3. The Emergency Operations Facility (EOF) will be functional by October 1, 1982 or prior to fuel load, whichever is later, in accordance with NUREG 0737 Item III A.1.2 issued by NRC Generic Letter 81-10. NUREG 0696 - Final Report will be used as a design guide. |
| Hence, our position is that the people as a whole will report within a thirty to sixty minute time frame.In support of this position, it should be noted that our on-shift complement presently by one and it is anticipated a full two unit staffing will exceed the requirements by approximately 3 to 5 people.3.NUREG 0737 (as issued by Generic Letter 81-10)requires the recovery manager to report to the Emergency Operations Facility within one hour of notification. | | : 4. The Emergency Response Computer System (ERCS) will be implemented by the dates given or prior to fuel load, whichever is later. |
| Our intent is that the recovery manager and his entire organization be staffed with personnel normally assigned to the Allentown General Offices.As such, the absolute minimum amount of time it would take a person to respond is in the order of two hours based on the driving time from the Allentown area to the site.Taking into account the mobilization effort required to put together the recovery organization, a middle of the night call in and potential adverse weather conditions, the most reasonable time that we can confidently commit to manning the Emergency Operations Facility is four hours.As an alternative to this position, we could commit to manning the EOF by utilizing the plant personnel. | | a) The Safety Parameter Display System (SPDS) will be operational in the control room and the TSC by October 1, 1982. The SPDS will not be operational in the EOF by October 1, 1982. This data display capability is expected to be available in the EOF by July 1, 1984. Data from the plant process computer will be provided in the EOF from October 1, 1982 until the SPDS is installed and operational. |
| However, this has a major drawback in that it would severely dilute the organization of the Emergency Director and 1'imiC his capability to place the plant in a safe shutdown condition. | | b) ~ The Nuclear Data Link (NDL) will not be operational by October 1, 1982. This data transmissi'on capability is expected to be available by July 1, 1984. |
| As such, it is felt that this alternative leads us in a less safe direction and is therefore unacceptable. | | c) An integrated system to support NUREG 0696 Final Report, Reg. Guide 1.97, and Reg. Guide 1.23 requirements for the SPDS, TSC, EOF, and NDL is expected to be operational by July 1, 1984. |
| 0 4.NUREG 0737 (as issued in Generic Letter 81-10)utilizes the title of Health Physics Technician for those personnel who are to respond to perform in-plant, on-site and off-site radiological surveys.It is our intent that only Health Physics Technicians or other suitably qualified plant personnel will be used for in-plant surveys.However, we intend to use personnel from our Division forces to perform on-site (out-of-plant) and off-site surveys.These people will not, be Health Physics Technicians in the context of the definitions presented in ANS 3.1 but will be people fully trained and qualified to perform on-site and off-site radiological survevs and sample collection. | | Detailed commitments for data will be provided to NRC when Reg. |
| NUREG 0694 Commitments 1.The Interim Technical Support Center will be functional by Unit Sl fuel load in accordance with NUREG 0694.2.The Operational Support Center will be functional by Unit Sl fuel load in accordance with NUREG 0694.NUREG 0696-Final Report will be used as a design guide.3.'he Interim Emergency Operations Facility will be functional by Unit Sl fuel load in accordance with NUREG 0694. | | Guides 1.23 and 1.97 are finalized. |
| t I/'}} | | : 5. The on-shift organization will be staffed and trained to meet the requirements of Table III.A.1.2-1 of NRC generic letter 81-10 (same as Table B-l to NUREG-0654, Rev. 1). |
| | : 6. Additional personnel will be available by a call-in procedure to supplement the on-shift organization in the areas of communication, radiological assessment, technical support, repair and corrective action and radiation protection. These personnel will be available within a thirty to sixty m'inute time frame. |
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| | 3 ' |
| | : 7. The Technical Support Center will be manned and fully functional within a thirty to sixty minute time frame. |
| | : 8. The Emergency Operations Facility will be manned and fully functional within four hours. |
| | The above commitments deviate from the requirements as follows. |
| | will not the required date because of I |
| | : 1. The ERCS be totally operational at the unavailability of compatible equipment which meets all requirements. |
| | Therefore the intent of requirements in NUREG 0696 will be met by using a combination of the SPDS (which will be operational by October 1, 1982) and modifications to the plant process computer. This interim system will be in operation from October 1, 1982 until the integrated system is available. |
| | : 2. NUREG 0737 (as issued by Generic Letter 81-10) requires ll people to report to the site within thirty minutes of notification and an additional 15 within sixty minutes of notification. We cannot meet the ll people within thirty minutes requirement due to the general housing location of plant personnel with respect to the site. The overwhelming majority of personnel live approximately thirty to thirty-five minutes driving time from the site. |
| | Further, taking into" account the time it would take an individual to respond in the middle of the night plus possible adverse weather conditions, make it impossible to meet this requirement. Hence, our position is that the people as a whole will report within a thirty to sixty minute time frame. In support of this position, it should be noted that our on-shift complement presently by one and it is anticipated a full two unit staffing will exceed the requirements by approximately 3 to 5 people. |
| | : 3. NUREG 0737 (as issued by Generic Letter 81-10) requires the recovery manager to report to the Emergency Operations Facility within one hour of notification. Our intent is that the recovery manager and his entire organization be staffed with personnel normally assigned to the Allentown General Offices. As such, the absolute minimum amount of time it would take a person to respond is in the order of two hours based on the driving time from the Allentown area to the site. Taking into account the mobilization effort required to put together the recovery organization, a middle of the night call in and potential adverse weather conditions, the most reasonable time that we can confidently commit to manning the Emergency Operations Facility is four hours. As an alternative to this position, we could commit to manning the EOF by utilizing the plant personnel. However, this has a major drawback in that it would severely dilute the organization of the Emergency Director and 1'imiC his capability to place the plant in a safe shutdown condition. As such, it is felt that this alternative leads us in a less safe direction and is therefore unacceptable. |
| | |
| | 0 |
| | : 4. NUREG 0737 (as issued in Generic Letter 81-10) utilizes the title of Health Physics Technician for those personnel who are to respond to perform in-plant, on-site and off-site radiological surveys. |
| | It is our intent that only Health Physics Technicians or other suitably qualified plant personnel will be used for in-plant surveys. |
| | However, we intend to use personnel from our Division forces to perform on-site (out-of-plant) and off-site surveys. These people will not, be Health Physics Technicians in the context of the definitions presented in ANS 3.1 but will be people fully trained and qualified to perform on-site and off-site radiological survevs and sample collection. |
| | NUREG 0694 Commitments |
| | : 1. The Interim Technical Support Center will be functional by Unit Sl fuel load in accordance with NUREG 0694. |
| | : 2. The Operational Support Center will be functional by Unit Sl fuel load in accordance with NUREG 0694. NUREG 0696 - Final Report will be used as a design guide. |
| | 3.'he Interim Emergency Operations Facility will be functional by Unit Sl fuel load in accordance with NUREG 0694. |
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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
"ACCESSION NBR t 8104060586 REGULATORY INFORMATION DISTRIBUTION SYSTEM DATE! 81/04/02 t
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TITLE: PSAR/FSAR AMDTS and Related Correspondence NOTES!Send I8,E 3 copfes FSAR 8 all amends;'5000387'5000388 amends Send I8K 3 copfes FSAR & all RECIPIENT'D COPIES RECIPIENT'D COPIES'TTR'NCL' CODE/NAME" LTTR ENCL COOK/NAME ACTION! A/O'ICENSNG 0 YOUNGBLOOOgB RUSHBROOKeM ~ 0 STARKrR ~ 04 1 INTERNALS ACCID EVAL BR26 1 AUX SYS BR 07 1 1-CHEM K9G BR 08 1 1 CONT SYS BR 09 1 CORK'ERF BR 10 1 1 EFF TR SYS BR12 1 1 KMERG PREP 0 EQUIP QUAL BR13 3 3 IENCKS 14 HUM FACT KNG BR ZZ'KOSC 1 1 1 HYO/GKO" BR 2 2 I8C SYS BR 16 1 1 06 15'8,E:
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4 PPILL TWO. NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE~ (215) 770-5151 NORMAN W. CURTIS Vice President. Engineering rL Construction-Nuclear TT0.5381 April 2, 1981 R
8 Mr. B. J. Youngblood, Chief I Licensing Projects Branch 81 Division of Proj ect Management U.S. Nuclear Regulatory Commission ro Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY RESPONSE FACILITIES IMPLEMENTATION-RESPONSE TO GENERIC LETTER 81-10 ER 100450 FILE 841-12 PLA-704
Dear Mr. Youngblood:
This letter is sent to provide the information requested in the Eisenhut letter on February 18 (Generic letter 81-10) on implementation of emergency response facilities. The scope of information required by this letter was clarified by discussions with Mr. S. Ramos and Mr. E. Williams from the Division of Emergency Preparedness. Based on these discussions, commitments have also been provided in response to requirements in NUREG 0694.
Very truly ours, N. W. Curtis Vice President-Engineering & Construction-Nuclear DPM/mks cc: R. M. Stark NRC POO~
5 i/(
PENNSYLVANIA POWER IL LIGHT COMPANY 810 40 605Vg
ATTACHMENT NUREG 0737 Commitments (Generic Letter 81-10)
- 1. Detailed conceptual design descriptions for all emergency facilities will be submitted to the NRC by June 1, 1981 in accordance with NUREG 0737 Item III.A.1.2 issued by NRC Generic Letter 81-10.
- 2. The Technical Support Center (TSC) will be functional by October 1, 1982 or prior to fuel load, whichever is later, in accordance with NUREG 0737 Item III.A.1.2 issued by NRC Generic Letter 81-10. NUREG 0696-Final Report will be used as a design guide.
- 3. The Emergency Operations Facility (EOF) will be functional by October 1, 1982 or prior to fuel load, whichever is later, in accordance with NUREG 0737 Item III A.1.2 issued by NRC Generic Letter 81-10. NUREG 0696 - Final Report will be used as a design guide.
- 4. The Emergency Response Computer System (ERCS) will be implemented by the dates given or prior to fuel load, whichever is later.
a) The Safety Parameter Display System (SPDS) will be operational in the control room and the TSC by October 1, 1982. The SPDS will not be operational in the EOF by October 1, 1982. This data display capability is expected to be available in the EOF by July 1, 1984. Data from the plant process computer will be provided in the EOF from October 1, 1982 until the SPDS is installed and operational.
b) ~ The Nuclear Data Link (NDL) will not be operational by October 1, 1982. This data transmissi'on capability is expected to be available by July 1, 1984.
c) An integrated system to support NUREG 0696 Final Report, Reg. Guide 1.97, and Reg. Guide 1.23 requirements for the SPDS, TSC, EOF, and NDL is expected to be operational by July 1, 1984.
Detailed commitments for data will be provided to NRC when Reg.
Guides 1.23 and 1.97 are finalized.
- 5. The on-shift organization will be staffed and trained to meet the requirements of Table III.A.1.2-1 of NRC generic letter 81-10 (same as Table B-l to NUREG-0654, Rev. 1).
- 6. Additional personnel will be available by a call-in procedure to supplement the on-shift organization in the areas of communication, radiological assessment, technical support, repair and corrective action and radiation protection. These personnel will be available within a thirty to sixty m'inute time frame.
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- 7. The Technical Support Center will be manned and fully functional within a thirty to sixty minute time frame.
- 8. The Emergency Operations Facility will be manned and fully functional within four hours.
The above commitments deviate from the requirements as follows.
will not the required date because of I
- 1. The ERCS be totally operational at the unavailability of compatible equipment which meets all requirements.
Therefore the intent of requirements in NUREG 0696 will be met by using a combination of the SPDS (which will be operational by October 1, 1982) and modifications to the plant process computer. This interim system will be in operation from October 1, 1982 until the integrated system is available.
- 2. NUREG 0737 (as issued by Generic Letter 81-10) requires ll people to report to the site within thirty minutes of notification and an additional 15 within sixty minutes of notification. We cannot meet the ll people within thirty minutes requirement due to the general housing location of plant personnel with respect to the site. The overwhelming majority of personnel live approximately thirty to thirty-five minutes driving time from the site.
Further, taking into" account the time it would take an individual to respond in the middle of the night plus possible adverse weather conditions, make it impossible to meet this requirement. Hence, our position is that the people as a whole will report within a thirty to sixty minute time frame. In support of this position, it should be noted that our on-shift complement presently by one and it is anticipated a full two unit staffing will exceed the requirements by approximately 3 to 5 people.
- 3. NUREG 0737 (as issued by Generic Letter 81-10) requires the recovery manager to report to the Emergency Operations Facility within one hour of notification. Our intent is that the recovery manager and his entire organization be staffed with personnel normally assigned to the Allentown General Offices. As such, the absolute minimum amount of time it would take a person to respond is in the order of two hours based on the driving time from the Allentown area to the site. Taking into account the mobilization effort required to put together the recovery organization, a middle of the night call in and potential adverse weather conditions, the most reasonable time that we can confidently commit to manning the Emergency Operations Facility is four hours. As an alternative to this position, we could commit to manning the EOF by utilizing the plant personnel. However, this has a major drawback in that it would severely dilute the organization of the Emergency Director and 1'imiC his capability to place the plant in a safe shutdown condition. As such, it is felt that this alternative leads us in a less safe direction and is therefore unacceptable.
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- 4. NUREG 0737 (as issued in Generic Letter 81-10) utilizes the title of Health Physics Technician for those personnel who are to respond to perform in-plant, on-site and off-site radiological surveys.
It is our intent that only Health Physics Technicians or other suitably qualified plant personnel will be used for in-plant surveys.
However, we intend to use personnel from our Division forces to perform on-site (out-of-plant) and off-site surveys. These people will not, be Health Physics Technicians in the context of the definitions presented in ANS 3.1 but will be people fully trained and qualified to perform on-site and off-site radiological survevs and sample collection.
NUREG 0694 Commitments
- 1. The Interim Technical Support Center will be functional by Unit Sl fuel load in accordance with NUREG 0694.
- 2. The Operational Support Center will be functional by Unit Sl fuel load in accordance with NUREG 0694. NUREG 0696 - Final Report will be used as a design guide.
3.'he Interim Emergency Operations Facility will be functional by Unit Sl fuel load in accordance with NUREG 0694.
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