Letter Sequence Other |
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Results
Other: ML17157C504, ML17158A017, ML17158A020, ML17158A024, ML17158A082, ML17158A087, ML17158A156, ML17158A164, ML17158A224, ML17158A300, ML17158A330, ML17158A670, ML17158A727, ML18017A271, ML18030A387, ML18030A574, PLA-4134, Responds to 940421 RAI Re Loss of Spent Fuel Cooling for Sses.Concludes Facility Has Multiple Means to Assure Makeup for Dba/Loca, PLA-4145, Responds to RAI Re Loss of Spent Fuel Pool Cooling Initiated by Design Basis Seismic Event
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MONTHYEARML17157C3941993-06-30030 June 1993
Forwards Util 930524 Response to NRC & Licensee Event Rept 93-018 & Expresses Appreciation for Both Individuals Attending 930318 Meeting Re Effects of Loss of SFP Cooling Following LOCA & LOOP at Plants
Project stage: Meeting
ML17157C4351993-08-0404 August 1993
Forwards Meeting Summary,Including Transcript of Meeting & Slides Presented by Util & Util Re Effects of Loss of Spent Fuel Pool Cooling Following Loss of Coolant Accident & Loss of Offsite Power
Project stage: Meeting
ML17157C4521993-08-17017 August 1993
Forwards Copy of Addl Info Requested of Util During 930708 Meeting W/Nrc Re 10CFR21 Rept on Spent Fuel Pool Cooling Issue.Meeting Tentatively Scheduled for 931001 in Rockville, MD
Project stage: Meeting
ML17157C5041993-10-0808 October 1993
Forwards NRC Info Notice 93-83 Issued on 931007 to Keep Appraised of Developments on Spent Fuel Pool Cooling Issue
Project stage: Other
ML17157C5031993-10-0808 October 1993
Expresses Appreciation Re 931001 Meeting to Provide Opportunity to Personally Present Technical Issues in 10CFR21 Rept Filed on 921127 Re Spent Fuel Pool Cooling Issue
Project stage: Meeting
ML17157C5261993-10-20020 October 1993
Forwards Request for Addl Info Re Loss of Sfpc Events for Plants
Project stage: RAI
ML17158A0241993-11-17017 November 1993
Forwards Action Plan Which Systematically & Carefully Evaluates Technical Concerns Outlined in 921127,10CFR21 Rept & Subsequent Correspondence
Project stage: Other
ML17158A0171993-11-22022 November 1993
Provides Correspondence Re Spent Fuel Pool Cooling Issue. Correspondence Will Be Provided on a Continuing Basis
Project stage: Other
ML17158A0201993-11-23023 November 1993
Requests Addl Info Re Loss of Spent Fuel Pool Cooling Events at Plant.Reply Requested by 931203
Project stage: Other
ML17158A0821994-01-11011 January 1994
Forwards Documents Re SFP Cooling Issue at Plant.Informs That Addl Info Is Being Requested to Complete Evaluation Described in 931115 Staff Action Plan
Project stage: Other
ML17158A0871994-01-14014 January 1994
Forwards Summary of Impact of Hydrodynamic Loads on Spent Fuel Cooling & Svc Water Piping
Project stage: Other
ML17158A7281994-02-0101 February 1994
Informs That Staff Received Addl Info from Licensee on Certain Specific Technical Issues During Course of Staff Review of Issues Raised in 921127 Part 21 Rept.Forwards Copies of Training Matl Provided by Util
Project stage: Approval
ML17158A1211994-02-0101 February 1994
Responds to Issues Raised in Recipient 921127 Part 21 Rept Re Spent Fuel Cooling.Licensee Safety Evaluation for Replacement of SBGT Sys Fire Damper Fusible Links & Plant EQ List & Study Encl
Project stage: Approval
ML17158A7271994-02-16016 February 1994
Forwards from NRC W/Fine Copyrighted Encls. Informs That Document Cannot Be Reproduced in Whole or in Part or Released to Nudocs Until Written Permission Received from Util
Project stage: Other
ML17158A1561994-02-28028 February 1994
Discusses 940207 Visit to Util Headquarters in Allentown, PA Re Spent Fuel Pooling Issues
Project stage: Other
ML17158A1641994-03-0707 March 1994
Requests Addl Info Re Standby Gas Treatment Sys Performance at Susquehanna Steam Electric Station,Units 1 & 2
Project stage: Other
IR 05000387/19940041994-03-25025 March 1994
Insp Repts 50-387/94-04 & 50-388/94-04 on 940101-0226. Noncited Violations Identified.Major Areas Inspected:Plant Operation,Radiation Protection,Surveillance & Maint, Engineering & Technical Support & Safety Assessment
Project stage: Request
ML17158A2241994-04-11011 April 1994
Forwards Documents Re Issues Raised in 921127 Part 21 Rept Concerning Spent Fuel Pool Cooling.Nrc Reviewing Documents & Will Continue to Pursue Addl Info as Necessary to Complete Evaluation Described in 931115 Task Action Plan
Project stage: Other
ML20266G6001994-05-0404 May 1994
Inservice Inspection Isometric Hanger Identification ISI-GBC-101-24-H.Sheet 1
Project stage: Request
PLA-4134, Responds to 940421 RAI Re Loss of Spent Fuel Cooling for Sses.Concludes Facility Has Multiple Means to Assure Makeup for Dba/Loca1994-05-0505 May 1994
Responds to 940421 RAI Re Loss of Spent Fuel Cooling for Sses.Concludes Facility Has Multiple Means to Assure Makeup for Dba/Loca
Project stage: Other
ML17158A2871994-05-17017 May 1994
Forwards Info Re NRC RAI Concerning Loss of Spent Fuel Pool Cooling Issues & Standby Gas Treatment Sys Performance Following Seismic Event
Project stage: RAI
ML17158A3001994-05-19019 May 1994
Requests Addl Info Re Util Capability to Mitigate,In Manner Consistent W/Licensing Basis of Plant,Effects of Loss of SFP Cooling Initiated by Design Basis Seismic Event
Project stage: Other
PLA-4145, Responds to RAI Re Loss of Spent Fuel Pool Cooling Initiated by Design Basis Seismic Event1994-06-0101 June 1994
Responds to RAI Re Loss of Spent Fuel Pool Cooling Initiated by Design Basis Seismic Event
Project stage: Other
ML17158A3301994-06-0909 June 1994
Forwards Various Documents Received by NRC Staff Re Issues Raised in Addressee Rept Filed on 921127 Per 10CFR21 Concerning Procedures for Implementation of RHR Sys Sf Pool Cooling Assist Mode.Plant Operating Procedure in Encl 1
Project stage: Other
ML18017A2711994-07-0505 July 1994
Provides Copy of Transcripts from 940506 Briefing to ACRS Re Loss of Sfpc Issues.Pages 358 Through 460 & Attachment Encl
Project stage: Other
ML18030A3871994-10-24024 October 1994
Forwards Task Action Plan to Evaluate Spent Fuel Storage Pool Safety Issues Identified as Result of Problems Found at Dresden 1,issues Raised at Susquehanna & Other Issues Raised in Rept Filed,Per 10CFR21 on 921117
Project stage: Other
ML18017A2751994-10-25025 October 1994
Forwards Draft Safety Evaluation Re Spent Fuel Pool Cooling Issues,For Review & Comment
Project stage: Draft Approval
ML18017A2761994-11-0303 November 1994
Informs NRC Has Completed Draft Final SE Re Spent Fuel Pool Cooling Issues at Plant.Se Submitted in Response to Rept,Dtd 921127,filed Per 10CFR21.Forwards Draft SE for Review & Comment
Project stage: Draft Approval
ML17164A4701994-12-23023 December 1994
Forwards Comments to NRC on Draft SE Rept Re Potential Loss of Spent Fuel Pool Cooling at Plant,Per 941208 Briefing
Project stage: Draft Approval
ML17164A4981994-12-29029 December 1994
Ack Receipt of Comments on Draft SE Re Spent Fuel Pool Cooling Issues at Plant,Per .Informs That Staff Considering Comments in Preparation to Finalize Draft SE
Project stage: Draft Approval
ML18030A5741995-04-20020 April 1995
Forwards Risk Evaluation Rept Related to Loss of Spent Fuel Pool Cooling Events at Plant
Project stage: Other
ML17158A6701995-05-17017 May 1995
Discusses Which Forwarded Staff, Task Action Plan for Spent Fuel Storage Pool Safety, for Sses.Forwards Completed Assessment Repts for Brunswick & Monticello Sites
Project stage: Other
ML17158A7491995-06-19019 June 1995
Forwards Final SE Which Concludes That Sys Used to Cool Spent Fuel Storage Pool,Adequate to Prevent Unacceptable Challenges to Safety Related Sys Protecting Health & Safety of Public
Project stage: Approval
1994-02-01
[Table View] |
Text
I
~ 7
~PS RECT O
I 0~*~4 Docket Nos.
50-387 and 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555<001 June 9, 1994 Hr. David A. Lochbaum 80 Tuttle Road
- Watchung, New Jersey 07060 Hr. Donald C. Prevatte 7924 Woodsbluff Run Fogelsville, Pennsylvania 18051 Gentlemen:
SUBJECT:
SUS(UEHANNA STEAN ELECTRIC STATION, UNITS 1
AND 2, SPENT FUEL POOL COOLING ISSUE (TAC NO. H85337)
The purpose of this letter is to forward various documents recently received by the staff that are related to the ongoing review of the issues raised in your report, filed pursuant to 10 CFR Part 2].,
on November 27, 1992.
During a teleconference with tlIe licensee on Hay 26, 1994, the staff inquired if procedures for implenIentation of the residual heat removal (RHR) sytem fuel pool cooling assist mode had been revised to refTect the newly installed spent fuel pool level and temperature instrumentation.
The licensee indicated that relevant procedures had been revised and provided a copy of OP-249-003, Rev.
13, "RHR Operation in Fuel Pool Cooling Mode," and ON-235-001, Rev.
13, "Loss of Fuel Pool Cooling/Coolant Inventory."
Copies of these procedures are attached as Enclosures 1 and 2.
During the Hay 26, 1994 teleconference, the staff requested clarification regarding test procedure TP-235-011, Rev. 0, "Fuel Pool Decay Heat Removal," which was referenced in the licensee's Hay 5, 1994 submittal.
The licensee provided a copy of the referenced procedure and a copy is attached as Enclosure 3.
The staff issued a request for additional information (RAI) to the licensee on Hay 19, 1994.
By letter dated June 1,
1994, the licensee responded to the 940M50183 940609 PDR
= ADDCK'5000387 PDR +~
g I
Hr. David A. Lochbaum Hr. Donald C. Prevatte June 9, 1994 RAI.
A copy of the June 1,
1994 response by the licensee is attached as Enclosure 4.
If you have any additional comments or questions, please do not hesitate to call me at (301) 504-1428.
Sincerely,
/s/
Joseph W. Shea, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
- 1. Plant Procedure OP-249-003, Rev.
13, "RHR Operation In Fuel Pool Cooling Mode"
- 2. Plant Procedure ON-235-001, Rev.
13, "Loss Of Fuel Pool CoolingiCoolant Inventory"
- 3. Plant Procedure TP-235-011, Rev. 0, "Fuel Pool Decay Heat Removal"
- 4. Letter from R.
G.
- Byram, PP&L, to C. Hiller, NRC, dated June 1,
1994 cc w/o enclosures:
Hr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company f
2 North Ninth Street Allentown, Pennsylvania 18101 A
DISTRIBUTION *w/enclosures Docket File*
JCalvo NRC and Local PDRs*
CHiller PDI-2 Reading*
MO'Brien SVar a
JShe l
CPoslusny OGC ACRS(10)
EWenzin er, RGN-I
- JWhite, RGN-I*
LPrividy, RGN-I*
OFFICE NAME DATE l
ie 94 PD 2
PH c
94 PDI-2 D
CMi1 1 OFF ICIAL OR COPY DOCUMENT NAME:
LRPJUN.LTR
Hr. David A. Lochbaum Hr. Donald C. Prevatte June 9, 1994 RAI.
A copy of the June 1,
1994 response by the licensee is attached as Enclosure 4.
If you have any additional comments or questions, please do not hesitate to call me at (301) 504-1428.
Sine rely,
Enclosures:
- 1. Plant Procedure OP-249-003, Rev.
13, "RHR Operation In Fuel Pool Cooling Mode"
- 2. Plant Procedure ON-235-001, Rev.
13, "Loss Of Fuel Pool Cooling~Coolant Inventory"
- 3. Plant Procedure TP-235-011, Rev. 0, "Fuel Pool Decay Heat Removal"
- 4. Letter from R.
G.
- Byram, PP&L, to C. Hiller, NRC, dated June 1,
1994 cc w/o enclosures:
Hr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 J seph W. Shea, Project Manager Pro 'ect Directorate I-2 J
Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
