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
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 April ll, 1994 Docket Nos.
50-387 and 50-388 Hr. David A. Lochbaum 80 Tuttle Road
- Watchung, New Jersey 07060 Hr. Donald C. Prevatte 7924 Woodsbluff Run Fogelsville, Pennsylvania 18051 Gentlemen:
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1
AND 2, SPENT FUEL POOL!
COOLING ISSUE (TAC NO. H85337)
During the course of the staff's review of the issues raised in your November 27, 1992 Part 21 report, the staff has received additional information from the licensee on certain specific technical issues.
In addition, the staff has examined supporting documents during visits to the licensee's headquarters and the Susquehanna site.
In order to help keep you abreast of the staff's ongoing review, we are continuing to p'rovide
.copies of these documents to you.
By letter dated Harch 7,
- 1994, the staff requested additional information from the licensee regarding standby gas treatment performance and emergency diesel generator load capacity.
By letter dated Harch 25, 1994, the licensee provided a partial response to this request.
The Harch 25, 1994 letter is attached as Enclosure l.
Following our Harch 14, 1994 meeting with you, the staff requested that the licensee provide information regarding the development of procedure EP-IP-055, "Post Accident Reactor Building HVAC (Reactor Building Non-1E Electrical Load Shed)."
The licensee provided the requested information by letter dated Harch 21, 1994.
The Harch 21, 1994 letter is attached as Enclosure 2.
Your attention is invited to the discussion on Page 1 and Page 2 of the attachment to the Harch 21 letter.
In that discussion, the licensee clarifies previous understandings of the automatic load shed feature following a loss-of-coolant accident.
." uvvBB 9404200324 9404ii PDR ADOCK 05000387 P
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Hr. David A. Lochbaum Hr. Donald C. Prevatte April 11, 1994 I
f1 The staff is reviewing these documents a'nd will continue to pursue additional information as necessary to complete the evaluation described in the November 15, 1993 Task Action Plan.
'We have'eceived your letter dated March 21, 1994 and are reviewing. its contents.
If you have any additional comments or questions, please do not hesitate to call me at (301) 504-1428.
Sincerely,
/s/
Enclosures:
1.
Letter from R.
G.
- Byram, PPEL, to C. Hiller, NRC, dated March 25, 1994 2.
Letter from R.
G.
- Byram, PPKL, to C. Hiller, NRC, dated March 21, 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 Joseph W. Shea, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation DISTRIBUTION *w/enclosures:
Docket File*
JCalvo NRC and Local PDRs*
CHiller PDI-2 Reading HO'Brien(2)
SVar a
JShea RClark
- JWhite, RGN-I*
OGC LPrividy, RGN-I*
ACRS(10)
EWenzin er, RGN-I OFFICE NAME DATE P.
I,
'B ien 94 PDI-2/PH JShea.
/
/9 PDI-2 D
CHi
/ l~/94 OFFICIAL RE 0 COPY DOCUMENT NAME:
LKPHAR.LTR
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Hr. David A. Lochbaum Hr. Donald C. Prevatte April ll, 1994 The staff is reviewing these documents and will continue to pursue additional information as necessary to complete the evaluation described in the November-15, 1993 Task Action Plan.
We have received your letter dated March 21, 1994 and are reviewing its contents.
If you have any additional comments or questions, please do not hesitate to call me at (301) 504-1428.
Since y,
Enclosures:
1.
Letter from R.
G. Byram, PP&L, to C. Hiller, NRC, dated March 25, 1994 2.
Letter from R.
G.
- Byram, PP&L, to C. Miller, NRC, dated March 21, 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 Jo e
W. Shea, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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