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| {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR 8005070402 DOC~DATE!80/04/29 NOTARIZED! | | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO FACIL:50 387 Susquehanna Steam Electric Station~Unit ir Pennsylva S0 388 Susquehanna Steam Electric Stations Unit 2i Pennsylva AUTH BYNAME AUTHOR AFFILIATION CURT 1St N~Wo Pennsylvania Power 8 Light Co.REC IP~NAME RECIPIENT AFF ILlATION PARRgO F 0'uxiliary Systems Branch | | ACCESSION NBR 8005070402 DOC ~ DATE! 80/04/29 NOTARIZED! NO DOCKET ¹ FACIL:50 BYNAME 387 Susquehanna Steam Electric Station~ Unit ir Pennsylva S0 388 Susquehanna Steam Electric Stations Unit 2i Pennsylva tg 388 AUTH AUTHOR AFFILIATION CURT 1St Pennsylvania Power 8 Light Co. |
| | 'uxiliary N ~ Wo REC IP ~ NAME RECIPIENT AFF ILlATION PARRgO F 0 Systems Branch |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Notifies that date 8 location of meetingito resolve open items in FSAR Sections F 6 ,10rwill be provided by 800515'genda will be provided by 800615.DISTRIBUTION COOK: 80018 COPIES RECEIVED:LTR ENCL~SIZE: TITLEi PSAR/FSAR AMDTS and Related Correspondence NOTES'~+'Q | | Notifies that date 8 location of meetingito resolve open items in FSAR Sections F 6 ,10rwill be provided by 800515 will be provided by 800615. 'genda DISTRIBUTION COOK: 80018 COPIES RECEIVED:LTR ENCL ~ SIZE: |
| +%g.DOCKET¹tg 388 REC IP IENT IO COOK/NAME ACTION: 05 PM W/~Kg BC INTERNAL<01 RGG K~l.)0 I 8 K 09 GEOSCIKN BR 11 MECH ENG BR 13 MATL,.ENG BR 16 ANALYSIS BR 18 AUX SYS BR 20 I 8 C SYS BR 22 AD SITE TECH 27 EFFL TRT SYS 29 KIRKAOOO AD PLANT SYS AD SITE ANLYSIS HYDRO METEOR BR OELO EXTERNAL: 03 LPDR 30 ACRS COPIES I.TTR EN 1 1 1 3 1 1 2 2 1 1 1 1 11 1 1 2 1 1 10 1 RECIPIENT IO QQDK/AME AD L4d LA LOUR 9 02 NRC PDR 08 OPERA I.IC BR 10 QAB 12 STRUC ENG BR 15 RKAC SYS BR 17 CORE PERF BR 19 CONTAIN SYS 21 POWER SYS BR 26 ACCDNT ANLYS 28 RAD ASMT BR AD FOR ENG AD RKAC SAFETY DIRECTOR NRR MPA 04 NSIC COPIES LTTR ENCl.1 1 1 1'1 1 1 1.1 1 1 1 0 1 1 1 L&NooWE EP8 e~ae O'a~ep a~a~~~~'~~s>>>>O TOTAL NUMBER OF COPIES REQUIRED'TTR 52 ENCL PAL TWO NORTH NINTH STREET, ALLENTOWN, PA.18101 80 000VOIt~PHONEME t215)821-5151 April 29, 1980 Mr.Olan D.Parr, Chief Light Water Reactors Branch No.3 Division of Project Management U.S.Nuclear Regulatory Commission Washington, D.C.20555 SUSQUEHANNA STEAM ELECTRIC STATlON MEETING TO RESOLVE OPEN ITEMS IN FSAR SECTIONS 3.6 THROUGH 3.10 INCLUSIVE ER 100450 FILE 841-2 PLA-476 | | TITLEi PSAR/FSAR AMDTS and Related Correspondence NOTES'~+'Q + % g. |
| | REC IP IENT COPIES RECIPIENT COPIES IO COOK/NAME I.TTR EN IO QQDK/ AME LTTR ENCl. |
| | ACTION: 05 PM W/~Kg 1 AD L4d BC 1 LA LOUR 9 INTERNAL< 01 RGG K~l. ) 1 02 NRC PDR 1 0 I 8 K 3 08 OPERA I.IC BR 1 09 GEOSCIKN BR 10 QAB 1 11 MECH ENG BR 1 1 12 STRUC ENG BR 1' 13 MATL,. ENG BR 2 2 15 RKAC SYS BR 16 ANALYSIS BR 1 1 17 CORE PERF BR 1 18 AUX SYS BR 1 19 CONTAIN SYS 1 20 I 8 C SYS BR 1 21 POWER SYS BR 1 22 AD SITE TECH 1 26 ACCDNT ANLYS 1 . 1 27 EFFL TRT SYS 1 28 RAD ASMT BR 1 1 29 KIRKAOOO 1 AD FOR ENG 1 0 AD PLANT SYS 1 AD RKAC SAFETY 1 AD SITE ANLYSIS DIRECTOR NRR 1 HYDRO METEOR BR 2 MPA 1 OELO 1 EXTERNAL: 03 LPDR 1 04 NSIC 30 ACRS 10 1 L& |
| | NooWE EP8 e~ ae O'a~ep a~a ~~ ~~ '~~ |
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| | TOTAL NUMBER OF COPIES REQUIRED'TTR 52 ENCL O |
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| ==Dear Mr.Parr:== | | 80 000VOIt~ |
| With regard to your letter dated April 21, 1980 which proposes a meeting to resolve open items in FSAR Sections 3.6 through 3.10, Pennsylvania Power&Light Company fully supports this experimental approach to close out open items.It is our understanding that the intent of this meeting is to close out open items and terminate review of the FSAR sections under discussion. | | PAL TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEME t215) 821-5151 April 29, 1980 Mr. Olan D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management U. S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATlON MEETING TO RESOLVE OPEN ITEMS IN FSAR SECTIONS 3.6 THROUGH 3.10 INCLUSIVE ER 100450 FILE 841-2 PLA 476 |
| We will provide proposed meeting dates and place by May 15, 1980 and an agenda by June 15, 1980.It is our hope that.this approach will'accelerate the review process to minimize potential delays in issuance of an operating license.Very truly yours, N.W.Curtis Vice President-Engineering | | |
| &Construction PENNSYLVANIA POWER 8 L I GH T COMPANY W~o | | ==Dear Mr. Parr:== |
| ~p AEC>~o Op Cl C 0 cA 0 w+~O++*++0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.20555 April 25, 1980 ALL POMER REACTOR LICENSEES Gentlemen: | | |
| | With regard to your letter dated April 21, 1980 which proposes a meeting to resolve open items in FSAR Sections 3.6 through 3.10, Pennsylvania Power & Light Company fully supports this experimental approach to close out open items. It is our understanding that the intent of this meeting is to close out open items and terminate review of the FSAR sections under discussion. |
| | We will provide proposed meeting dates and place by May 15, 1980 and an agenda by June 15, 1980. |
| | It is our hope that .this approach will 'accelerate process to minimize potential delays in issuance of the review an operating license. |
| | Very truly yours, W~o N. W. Curtis Vice President Engineering & Construction PENNSYLVANIA POWER 8 L I GH T COMPANY |
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| | ~o Op UNITED STATES C |
| | Cl 0 NUCLEAR REGULATORY COMMISSION cA WASHINGTON, D. C. 20555 0 |
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| | ++*++ April 25, 1980 ALL POMER REACTOR LICENSEES Gentlemen: |
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| ==SUBJECT:== | | ==SUBJECT:== |
| CLARIFICATION OF NRC REQUIREMENTS FOR EMERGENCY RESPONSE FACILITIES AT EACH SITE Over the past several months the NRC staff has been conducting, reviews of each licensee's proposal to upgrade their plant to cope with emergencies. | | CLARIFICATION OF NRC REQUIREMENTS FOR EMERGENCY RESPONSE FACILITIES AT EACH SITE Over the past several months the NRC staff has been conducting, reviews of each licensee's proposal to upgrade their plant to cope with emergencies. |
| The lessons learned and emergency planning review teams have identified areas where clarification of the NRC position is necessary. | | The lessons learned and emergency planning review teams have identified areas where clarification of the NRC position is necessary. Our previous requirements for the TSC have been modified to allow an onsite TSC in close proximity to the control room that would not meet the habitability require-ments, provided that a backup, habitable TSC is located near the site. |
| Our previous requirements for the TSC have been modified to allow an onsite TSC in close proximity to the control room that would not meet the habitability require-ments, provided that a backup, habitable TSC is located near the site.It is the purpose of this letter to set forth clarification of NRR's require-ments for the three emergency response facilities defined in my September 13, 1979 letter to"All Operating Nuclear Power Plants".Additional specific criteria for these facilities is under development. | | It is the purpose of this letter to set forth clarification of NRR's require-ments for the three emergency response facilities defined in my September 13, 1979 letter to "All Operating Nuclear Power Plants". Additional specific criteria for these facilities is under development. The schedule for implementing these requirements has not changed. |
| The schedule for implementing these requirements has not changed.If you have any questions regarding this clarification, please contact the NRC Project Manager for your facility.Sincerely, | | If you have any questions regarding this clarification, please contact the NRC Project Manager for your facility. |
| | Sincerely, rre 1 . sen , ctsng s ector Division of perating Reactors Office of Nuclear Reactor Regulation |
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| ==Enclosure:== | | ==Enclosure:== |
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| Emergency Response Facilities rre 1.sen , ctsng s ector Division of perating Reactors Office of Nuclear Reactor Regulation | | Emergency Response Facilities |
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| | EMERGENCY RESPONSE FACILITIES CONTROL ROOM OPERATIONAL SUPPORT CENTER Close ~ communications to Proximity CR, OTSC, EOF o assembly area for support personnel Technical Data ONSITE TECHNICAL . Emphasis - Reactor/Systems Status SUPPORT |
| | * Essential Radiological Data Management Presence NRC CENTER ~ Sr. Plant Management |
| | ~ Sr. Plant Engineers |
| | ~ NRC Emergency Response Team (5 persons) |
| | Communications |
| | ~ Main link to EOF and NRC Habitable (CR criteria) If TSC not habitable, backup habitable TSC must be provided on or near site. |
| | Plant Security Boundary NEARSITE Technical Data EMERGENCY OPERATIONS |
| | ~ Emphasis on Radiological Info.; |
| | (meteorology) |
| | FACILITY ~ Same data as sent to NRC available Licensee Recovery Personnel |
| | ~ Licensee senior management (corporate level) |
| | ~ Recovery Manager Federal, State, Local Governments may use. |
| | NRC including Sr. NRC official Emphasis on off-site emergency plans Press Facility (periodic pool briefings) |
| | Habitability - direct radiation and isolable ventilation systems; HEPA filters in new facilities Alternate location designated |
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| | EMERGENCY RESPONSE FACILITIES Onsite Technical Su ort'Center An onsite technical support center (TSC) shall be maintained by each operating nuclear power plant. The TSC shall be separate from, but in very close proximity to, the control- room and be within the plant security boundary. Hhile care must be taken in selecting technical input available in the TSC, it appears likely that access to additional, control room data would be required during an emergency. |
| | The location of the TSC shall also be such as to facilitate occasional face-to-face contact between key control room and TSC supervisors (management presence). The emphasis in designing the TSC information displays should be on reactor systems status. Those individuals who are knowledgeable of and responsible for engineering and management support of reactor operations in the event of an accident will-report to the'SC (minimum size 25 persons including 5 NRC). Those persons who are responsible for the overall management of the utility resources including recovery following an accident (e.g., corporate managers) should report to the EOF (see below). Upon activation, the TSC will provide the main communication link between the plant and the operator's near-site Emergency Operations Facility, and the main communication link to the NRC for plant operations matters. The TSC must be habitable to the same degree as the control room for postulated accidents (SRP 6.4 as revised by NUREG-0660). Where the primary, in-plant, TSC is not made habitable because of site-specific considerations, a backup TSC which does meet the habitability requirements must be provided on or near the site. Parameters transmitted by any nuclear data link installed to meet future NRC requirements should be'ayailable.for display in the TSC and the |
| | : EOF, Onsite 0 erational- Su ort'Center (Assembl Area) |
| | The Operational Support Center shall be the place to which the operations support personnel report in an emergency situation. Communications will be provided with the control room, OTSC and EOF. |
| | Emer enc 0 erations Facilit (Near-Site) |
| | The Emergency Operations Facility (EOF) will be operated by the licensee for con-tinued evaluation and coordination of licensee activities related to an emergency having or potentially having environmental consequences. The EOF must have*the capability to display the same plant data and radiological information as will be required for transmittal to the NRC. The EOF will have sufficient space to accommodate representatives from Federal, State and local governments if desired by those agencies, including facilities for the senior NRC representative (10) on-site. In addition, the ma)'or State and local response agencies may perform data analysis jointly with the licensee. Overall management of utility resources including recovery operations following an accident (e.g., by corporate management) shall be managed from this facility. Press facilities for about 20 people shall be available at the Emergency Operations Facility (periodic use). Site meteorology should be used to the extent practical for determining the EOF location. The EOF should be located within about one mile of the reactor. The EOF should be a substantial structure, providing significant shielding factors from direct radiation and the capability to isolate ventilation systems. Filtration systems (at least HEPA filters) shall be provided in new structures. Arrangements shall be made to activate an alternate EOF in the event that the nearsite EOF becomes uninhabitable. |
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| EMERGENCY RESPONSE FACILITIES CONTROL ROOM OPERATIONAL SUPPORT CENTER Close Proximity~communications to CR, OTSC, EOF o assembly area for support personnel NRC ONSITE TECHNICAL SUPPORT*CENTER Technical Data.Emphasis-Reactor/Systems Status Essential Radiological Data Management Presence~Sr.Plant Management
| | ~ ~ |
| ~Sr.Plant Engineers~NRC Emergency Response Team (5 persons)Communications
| | I ~ I KlRHPl%R)~Mid%~ I ~ ~ ~ I I |
| ~Main link to EOF and NRC Habitable (CR criteria)-If TSC not habitable, backup habitable TSC must be provided on or near site.Plant Security Boundary NEARSITE EMERGENCY OPERATIONS FACILITY Technical Data~Emphasis on Radiological Info.;(meteorology)
| | ~ ~ |
| ~Same data as sent to NRC available Licensee Recovery Personnel~Licensee senior management (corporate level)~Recovery Manager Federal, State, Local Governments may use.NRC including Sr.NRC official Emphasis on off-site emergency plans Press Facility (periodic pool briefings)
| | ~ ~ ~ |
| Habitability
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| -direct radiation and isolable ventilation systems;HEPA filters in new facilities Alternate location designated EMERGENCY RESPONSE FACILITIES Onsite Technical Su ort'Center An onsite technical support center (TSC)shall be maintained by each operating nuclear power plant.The TSC shall be separate from, but in very close proximity to, the control-room and be within the plant security boundary.Hhile care must be taken in selecting technical input available in the TSC, it appears likely that access to additional, control room data would be required during an emergency.
| | ~ ~ ~ ~ |
| The location of the TSC shall also be such as to facilitate occasional face-to-face contact between key control room and TSC supervisors (management presence).
| | ~ I ~ If |
| The emphasis in designing the TSC information displays should be on reactor systems status.Those individuals who are knowledgeable of and responsible for engineering and management support of reactor operations in the event of an accident will-report to the'SC (minimum size 25 persons including 5 NRC).Those persons who are responsible for the overall management of the utility resources including recovery following an accident (e.g., corporate managers)should report to the EOF (see below).Upon activation, the TSC will provide the main communication link between the plant and the operator's near-site Emergency Operations Facility, and the main communication link to the NRC for plant operations matters.The TSC must be habitable to the same degree as the control room for postulated accidents (SRP 6.4 as revised by NUREG-0660).
| | ~ I I ~ ' ~ ~ ~ ~ |
| Where the primary, in-plant, TSC is not made habitable because of site-specific considerations, a backup TSC which does meet the habitability requirements must be provided on or near the site.Parameters transmitted by any nuclear data link installed to meet future NRC requirements should be'ayailable.for display in the TSC and the EOF, Onsite 0 erational-Su ort'Center (Assembl Area)The Operational Support Center shall be the place to which the operations support personnel report in an emergency situation.
| | II ~ I ~ |
| Communications will be provided with the control room, OTSC and EOF.Emer enc 0 erations Facilit (Near-Site)
| | I ~ |
| The Emergency Operations Facility (EOF)will be operated by the licensee for con-tinued evaluation and coordination of licensee activities related to an emergency having or potentially having environmental consequences.
| | I ~ |
| The EOF must have*the capability to display the same plant data and radiological information as will be required for transmittal to the NRC.The EOF will have sufficient space to accommodate representatives from Federal, State and local governments if desired by those agencies, including facilities for the senior NRC representative (10)on-site.In addition, the ma)'or State and local response agencies may perform data analysis jointly with the licensee.Overall management of utility resources including recovery operations following an accident (e.g., by corporate management) shall be managed from this facility.Press facilities for about 20 people shall be available at the Emergency Operations Facility (periodic use).Site meteorology should be used to the extent practical for determining the EOF location.The EOF should be located within about one mile of the reactor.The EOF should be a substantial structure, providing significant shielding factors from direct radiation and the capability to isolate ventilation systems.Filtration systems (at least HEPA filters)shall be provided in new structures.
| | ~ ~ I I I |
| Arrangements shall be made to activate an alternate EOF in the event that the nearsite EOF becomes uninhabitable.
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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
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR 8005070402 DOC ~ DATE! 80/04/29 NOTARIZED! NO DOCKET ¹ FACIL:50 BYNAME 387 Susquehanna Steam Electric Station~ Unit ir Pennsylva S0 388 Susquehanna Steam Electric Stations Unit 2i Pennsylva tg 388 AUTH AUTHOR AFFILIATION CURT 1St Pennsylvania Power 8 Light Co.
'uxiliary N ~ Wo REC IP ~ NAME RECIPIENT AFF ILlATION PARRgO F 0 Systems Branch
SUBJECT:
Notifies that date 8 location of meetingito resolve open items in FSAR Sections F 6 ,10rwill be provided by 800515 will be provided by 800615. 'genda DISTRIBUTION COOK: 80018 COPIES RECEIVED:LTR ENCL ~ SIZE:
TITLEi PSAR/FSAR AMDTS and Related Correspondence NOTES'~+'Q + % g.
REC IP IENT COPIES RECIPIENT COPIES IO COOK/NAME I.TTR EN IO QQDK/ AME LTTR ENCl.
ACTION: 05 PM W/~Kg 1 AD L4d BC 1 LA LOUR 9 INTERNAL< 01 RGG K~l. ) 1 02 NRC PDR 1 0 I 8 K 3 08 OPERA I.IC BR 1 09 GEOSCIKN BR 10 QAB 1 11 MECH ENG BR 1 1 12 STRUC ENG BR 1' 13 MATL,. ENG BR 2 2 15 RKAC SYS BR 16 ANALYSIS BR 1 1 17 CORE PERF BR 1 18 AUX SYS BR 1 19 CONTAIN SYS 1 20 I 8 C SYS BR 1 21 POWER SYS BR 1 22 AD SITE TECH 1 26 ACCDNT ANLYS 1 . 1 27 EFFL TRT SYS 1 28 RAD ASMT BR 1 1 29 KIRKAOOO 1 AD FOR ENG 1 0 AD PLANT SYS 1 AD RKAC SAFETY 1 AD SITE ANLYSIS DIRECTOR NRR 1 HYDRO METEOR BR 2 MPA 1 OELO 1 EXTERNAL: 03 LPDR 1 04 NSIC 30 ACRS 10 1 L&
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TOTAL NUMBER OF COPIES REQUIRED'TTR 52 ENCL O
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PAL TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEME t215) 821-5151 April 29, 1980 Mr. Olan D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management U. S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATlON MEETING TO RESOLVE OPEN ITEMS IN FSAR SECTIONS 3.6 THROUGH 3.10 INCLUSIVE ER 100450 FILE 841-2 PLA 476
Dear Mr. Parr:
With regard to your letter dated April 21, 1980 which proposes a meeting to resolve open items in FSAR Sections 3.6 through 3.10, Pennsylvania Power & Light Company fully supports this experimental approach to close out open items. It is our understanding that the intent of this meeting is to close out open items and terminate review of the FSAR sections under discussion.
We will provide proposed meeting dates and place by May 15, 1980 and an agenda by June 15, 1980.
It is our hope that .this approach will 'accelerate process to minimize potential delays in issuance of the review an operating license.
Very truly yours, W~o N. W. Curtis Vice President Engineering & Construction PENNSYLVANIA POWER 8 L I GH T COMPANY
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++*++ April 25, 1980 ALL POMER REACTOR LICENSEES Gentlemen:
SUBJECT:
CLARIFICATION OF NRC REQUIREMENTS FOR EMERGENCY RESPONSE FACILITIES AT EACH SITE Over the past several months the NRC staff has been conducting, reviews of each licensee's proposal to upgrade their plant to cope with emergencies.
The lessons learned and emergency planning review teams have identified areas where clarification of the NRC position is necessary. Our previous requirements for the TSC have been modified to allow an onsite TSC in close proximity to the control room that would not meet the habitability require-ments, provided that a backup, habitable TSC is located near the site.
It is the purpose of this letter to set forth clarification of NRR's require-ments for the three emergency response facilities defined in my September 13, 1979 letter to "All Operating Nuclear Power Plants". Additional specific criteria for these facilities is under development. The schedule for implementing these requirements has not changed.
If you have any questions regarding this clarification, please contact the NRC Project Manager for your facility.
Sincerely, rre 1 . sen , ctsng s ector Division of perating Reactors Office of Nuclear Reactor Regulation
Enclosure:
Emergency Response Facilities
EMERGENCY RESPONSE FACILITIES CONTROL ROOM OPERATIONAL SUPPORT CENTER Close ~ communications to Proximity CR, OTSC, EOF o assembly area for support personnel Technical Data ONSITE TECHNICAL . Emphasis - Reactor/Systems Status SUPPORT
- Essential Radiological Data Management Presence NRC CENTER ~ Sr. Plant Management
~ Sr. Plant Engineers
~ NRC Emergency Response Team (5 persons)
Communications
~ Main link to EOF and NRC Habitable (CR criteria) If TSC not habitable, backup habitable TSC must be provided on or near site.
Plant Security Boundary NEARSITE Technical Data EMERGENCY OPERATIONS
~ Emphasis on Radiological Info.;
(meteorology)
FACILITY ~ Same data as sent to NRC available Licensee Recovery Personnel
~ Licensee senior management (corporate level)
~ Recovery Manager Federal, State, Local Governments may use.
NRC including Sr. NRC official Emphasis on off-site emergency plans Press Facility (periodic pool briefings)
Habitability - direct radiation and isolable ventilation systems; HEPA filters in new facilities Alternate location designated
EMERGENCY RESPONSE FACILITIES Onsite Technical Su ort'Center An onsite technical support center (TSC) shall be maintained by each operating nuclear power plant. The TSC shall be separate from, but in very close proximity to, the control- room and be within the plant security boundary. Hhile care must be taken in selecting technical input available in the TSC, it appears likely that access to additional, control room data would be required during an emergency.
The location of the TSC shall also be such as to facilitate occasional face-to-face contact between key control room and TSC supervisors (management presence). The emphasis in designing the TSC information displays should be on reactor systems status. Those individuals who are knowledgeable of and responsible for engineering and management support of reactor operations in the event of an accident will-report to the'SC (minimum size 25 persons including 5 NRC). Those persons who are responsible for the overall management of the utility resources including recovery following an accident (e.g., corporate managers) should report to the EOF (see below). Upon activation, the TSC will provide the main communication link between the plant and the operator's near-site Emergency Operations Facility, and the main communication link to the NRC for plant operations matters. The TSC must be habitable to the same degree as the control room for postulated accidents (SRP 6.4 as revised by NUREG-0660). Where the primary, in-plant, TSC is not made habitable because of site-specific considerations, a backup TSC which does meet the habitability requirements must be provided on or near the site. Parameters transmitted by any nuclear data link installed to meet future NRC requirements should be'ayailable.for display in the TSC and the
- EOF, Onsite 0 erational- Su ort'Center (Assembl Area)
The Operational Support Center shall be the place to which the operations support personnel report in an emergency situation. Communications will be provided with the control room, OTSC and EOF.
Emer enc 0 erations Facilit (Near-Site)
The Emergency Operations Facility (EOF) will be operated by the licensee for con-tinued evaluation and coordination of licensee activities related to an emergency having or potentially having environmental consequences. The EOF must have*the capability to display the same plant data and radiological information as will be required for transmittal to the NRC. The EOF will have sufficient space to accommodate representatives from Federal, State and local governments if desired by those agencies, including facilities for the senior NRC representative (10) on-site. In addition, the ma)'or State and local response agencies may perform data analysis jointly with the licensee. Overall management of utility resources including recovery operations following an accident (e.g., by corporate management) shall be managed from this facility. Press facilities for about 20 people shall be available at the Emergency Operations Facility (periodic use). Site meteorology should be used to the extent practical for determining the EOF location. The EOF should be located within about one mile of the reactor. The EOF should be a substantial structure, providing significant shielding factors from direct radiation and the capability to isolate ventilation systems. Filtration systems (at least HEPA filters) shall be provided in new structures. Arrangements shall be made to activate an alternate EOF in the event that the nearsite EOF becomes uninhabitable.
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