ML17158A408
| ML17158A408 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/26/1994 |
| From: | James Shea Office of Nuclear Reactor Regulation |
| To: | Chris Miller Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9408010259 | |
| Download: ML17158A408 (17) | |
Text
Gocket Nos.
50-387 and 50-388 July 26, 199 MEMORANDUM FOR:
FROM:
SUBJECT:
Charles L. Hiller, Director Project Directorate I-2 Division of Reactor Projects,- I/II Office of Nuclear Reactor Regulatioii Joseph W. Shea, Project Manager Project Directorate I-2 Division of Reactor Projects
'I/II Office of Nuclear Reactor Regulation TRACKING OF CORRESPONDENCE AND ISSUES RELATED TO LOSS OF SPENT FUEL POOL COOLING CONCERNS -
By memorandum dated November 15, 1993, the staff established an action -plan to thoroughly and systematically evaluate concerns raised by two contract engineers regarding the adequacy of spent'fuel pool cooling systems at the Susquehanna Steam Electric Station.
The action plan was divided into three separate task areas that encompassed plant specific technical issues",. geqeric activities and various project management and communications activities.
This memo concerns several specific activities related to the development of a plant-specific safety evaluation and..management of communications.
Item LC-2 of the action plan tasked'he staff to review the Part 21 report and all correspondence to identify all scenarios and related technical issues.
Attached is a list of those technical issues in the Part 21 report and correspondence for which NRR has lead responsibility. " The list is maintained as a living document.
The attached revi'sion contains all technical issues identified in documents through June 30, 1994.
A copy of this memorandum will be placed in the docket file for Susquehanna and in the public document room.
Enclosure:
List of NRR Managed Spent Fuel Pool Cooling Issues
/s/
Joseph W. Shea, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Distribution w enclosure:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 26, 1994 Docket Nos.
50-387 and 50-388 HEHORANDUH FOR:
FROH:
SUBJECT:
Charles L. Hiller, Director Project Directorate I-2 Division of Reactor Projects
, I/II Office of Nuclear Reactor Regulation Joseph W. Shea, Project Hanager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation TRACKING OF CORRESPONDENCE AND ISSUES RELATED TO LOSS OF SPENT FUEL POOL COOLING CONCERNS By memorandum dated November 15,
- 1993, the staff established an action plan to thoroughly and systematically evaluate concerns raised by two contract engineers regarding the adequacy of spent fuel pool cooling sys'tems at the Susquehanna Steam Electric Station.
The action plan was divided into three separate task areas that encompassed plant specific technical
- issues, generic activities and various project management and communications activities.
This memo concerns several specific activities related to the development of a plant-specific safety evaluation and management of communications.
Item LC-2 of the action plan tasked the staff to review the Part 21 report and all correspondence to identify all scenarios and related technical issues.
Attached is a list of those technical issues in the Part 21 report and correspondence for which NRR has lead responsibility.
The list is maintained as a living document.
The attached revision contains all technical issues identified in documents through June 30, 1
4.
A copy of this memorandum will be placed in the docket file for Susqueh and in the publ'ocument room.
Enclosure:
List of NRR Managed Spent Fuel Pool Cooling Issues J se W. Shea, Project Hanager P oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
NRR HANAGED SPENT FUEL POOL COOLING ISSUES 7 94 Item No.
Issue Recap Problem Statement Reference Nov 23 XCPT 8-14 Lead Review NRR DRP Closure Document Determine Licensing Basis for Spent Fuel Pool Cooling System re:
LOCA, LOCA/LOOP
-LOCA/Loss of SFPC is in design and licensing basis
-other FSAR sections, other regulations provide licensing basis tie of LOCA/SFP boil in Oct 1 letter NRR/DRP Har 31, 1993 ltr; Aug 13, 1993 ltr p5 Har 21, 1994 ltr, pl Review RHR ASSIST HODE pr eoperational test data and Calc H-RHR-039, Rev. 0, dated Hay 17, 1993.
Determine if NPSH Calc for RHR assist mode bounds the expected initiation temp.
Establish the basis for pool boiling times including basis for initial pool temp and outage mgmt/heat load assumptions.
Determine if PP8L used inappropriate heat loads to justify time available for recovery actions.
Dec 6, 1993 LSP letter, p2; Aug 13, 1993 ltr Nov 3 PP&L Nov 23
- XCPT, 202-214 Jan 24, 94 att p
2 itm4 Jan 24 Att p3 item 6 Nov 23 Xcpt p14-24; Oct 1,93 Xcpt, p65 Har 31,93, p7; Aug 13, 1993
- ltr, 8
NRR/SPLB NRR/SPLB
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NRR HANAGED SPENT FUEL POOL COOLING ISSUES 7 94 Item No.
5,.
10 Issue Review effect of LOCA hydrodynamic loads on SFPC equipment, including related service water piping.
Review licensee's representative calculations.
Evaluate effect of SWS flooding induced by LOCA h drod namic loads.
Evaluate distribution of refueling floor condensation to both unit sumps, including carryover of airborne fission products.
Evaluate effect of recirc shutdown on reactor building temperatures and equipment.
Review procedural control of recirculation shutdown.
Evaluate applicability of GDC 44.
Assess ability of UHS to handle 2 fuel pool heat loads, post LOCA loads, and safe shutdown loads (other unit);
Evaluate statement by PP&L'that design basis UHS calcs bound any condition being examined for SFP issue.
Reference Part 21 report cover letter, et.
al.
Nov 7 L&P Nov 7, 1993 ltr;
- Har31, 1993 ltr AUQ 13, 1993 1tr 12 Nov 7 L&P Nov 23 xcpt, p82, pl14 Comments per Feb 10 telecon w DL Nov 7 L&P Jan 24, cvr ltr Nov 7 L&P, Har 31, 1993 ltr, p7; Aug 13, 1993 ltr, p8 Nov 23 Xcpt, p193-203 Lead Review NRR/EHEB NRR/SPLB NRR/PRPB NRR/SPLB NRR/SPLB NRR/SPLB NRR/SPLB NRR/SPLB Closure Document
~
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NRR MANAGED SPENT FUEL POOL COOLING ISSUES 7 94 Item No.
12 13 15 16 Issue Consider probability of an extended loss of offsite power
(>24 hrs).
Evaluate SFP systems against LOCA environmental conditions.
Evaluate presumed failure of core spray loop due to flooding during LOCA sequence.
Evaluate possibility of flooding leading to failure of addi tional ECCS 1 oops.
Review seismic qualification, lE qualification, and failure modes of SFPC/SW systems and instrumentation against required qualification.
Evaluate qualification of equipment in SGTS rooms against temperature generated by boiling pool.
Evaluate significance of:
SBGT max heater outlet temp is 180 F
based on 125 F inlet.
SBGT limiting equipment includes temperature probes and filter insert glue.
Bechtel 1979 calculation shows boiling pool results in building temperatures of 180'F.
Reference Oct 1
L&P, p8;,
Nar 31, 1993 ltr p6; Aug 13, 1993
- ltr, 4
Oct 1,
- L8P, 2
13 Oct 1
L&P, p4 -4.a Aug 13,1993 ltr, pl3 Oct 1X, 67 Oct 1
L&P p4-IV.A.1,2 Jan 24 ltr Oec 2 Xcpt, p22-32, Har 31, 1993 ltr Oct 1
L&P, p5.
Aug 13, 1993 ltr, pl3 Jan 24 Att p4, item 2 Feb 10, 1994 telecon w/DL Feb 1980 meeting notes Lead Review NRR/SPLB NRR/SPSB NRR/SPLB NRR SPSB NRR/SPLB NRR/SPLB NRR/SPLB Closure Document
NRR MANAGED SPENT FUEL POOL COOLING ISSUES 7 94 Item No.
Issue Reference Lead Review Closure Document 17 Evaluate significance of capability to send Mar 31, 1993 collected condensation in sum to radwaste.
ltr NRR/SPLB 18 19 20 21 22 Evaluate seismic qualification of RHR SFP cooling assist mode piping.
Assess significance of reactor building design heat loads excluding heat from pool.
boiling.
Boiling pool may increase reactor building heat load from 5.2 HBTU/hr by adding 26 HBTU/hr.
Evaluate acceptability of crediting nonsafety-related SFP cooling system and RHR assist mode for post-accident recovery of SFP cooling (regulatory question).
Address limitations on use of RHR Assist mode during various conditions (i.e.,
shutdown cooling and,.post-accident for-affected unit.
Determine use of if RHR on accident unit is valid for accident unit FPC assist.
For long-term LOCA/LOOP, evaluate margin available on EDGs for RHR assist mode operation.
Oct 1 LLP, p7 Nov 23, 107-112 EDR-G20020 item A (Part 21 Att 3)
Oct ISX LIP, p19 Aug 13, 1993 ltr 9
Dec 6, 1993 LRP p3 Jan 24 LEP cvr ltr Dec 6, 1993 L8P letter p2 Dec 6 LKP Dec 6, 1993 letter p2 NRR/SPLB NRR/SPLB NRR/DRP NRR/SPLB NRR/SPLB
NRR MANAGED SPENT FUEL POOL COOLING ISSUES 7 94
,Item No.
23 25 Issue Evaluate accumulation of water from SFP boiling and ESW makeup in reactor building sump and atmosphere causing unanalyzed floodin and condensation.
Evaluate qualification of safety-related equipment for boiling spent fuel pool conditions.
Evaluate SFP instrumentation qualification for boiling SFP conditions.
Reference EDR-G20020-B (Part 21 Att 3)
Oct 1X LEP p18 Part 21 cvr ltr 3
EDR-G20020; Part 21, Attachment 3, Item D
Lead Review NRR/SPLB NRR/SPLB NRR/SPLB Closure Document 26 Evaluate capability of safety-related ductwork to withstand condensation.
Oct 1
L8P p8 NRR/SPLB 27 Evaluate control of SFP heat load and pool configuration control.
Evaluate capability of cooling a SFP using adjacent unit's coolin s stems.
Oct 1X LSP p35 NRR/SPLB 28 Assess ability to cross fill pools with nonaccident unit ESW.
Evaluate concurrent failure of non-seismic portion of accident unit piping.
Oct 1X, p37 NRR/SPLB Aug 13, 1993 ltr
NRR MANAGED SPENT FUEL POOL COOLING ISSUES 7 94 Item No.
29 30 31 Issue Procedures require load shed after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Eg concerns.
Load shed initiated by tripping TB non-1E breakers.
Assess impact of this procedure on boiling SFP mitigation plans.
Evaluate effects of automatic LOCA load shed feature on the SFPCS.
Evaluate adequacy of assumed.initial pool tern erature in calculatin time to boil.
Evaluate viability of various loss of SFP cooling mitigation procedures; compare to time motion stud Reference Attachment 8,
p12 Jan 24, Atch p2, item 2 Nov 23 Handout 18 Jan 24 att, 3 item 7 Nov 23 Xcpt, p52-73 Lead Review NRR/SPLB NRR/SPLB NRR/HHFB Closure Document 32 Evaluate activity rates used in determining Part 21 offsite dose consequences of a boiling SFP.
Report Attachment 5, pl2 NRR/PRPB 33 Evaluate accessibility for action required to isolate a failed SFP piping system.
Oct 1
transcript p69 NRR/PRPB
NRR MANAGED SPENT FUEL POOL COOLING ISSUES 7 94 Item No.
35 36 Issue Assess the operator dose resulting from multiple batch additions of makeup from the ESW s stem.
Assess activity rates used in the evaluation of containment leakage.
Evaluate operator accessibility assessments, considering assumptions used in NUREG 0737 and Chapter 18 of the SSES FSAR (licensing basis).
Reference Oct 1
LLP p6 and p58 of October 1
(Calculation s described in Appendix 9A of FSAR)
(p6-7 of Attachment 2
to Part 21)
(p6 of attachment 3
EDR p5 of cover letter to Part 21 report Lead Review NRR/PRPB NRR/PRPB NRR/PRPB Cl osure Document-37 Evaluate accessibility of fuel pool instruments post-LOCA.
p4 of cover letter to part 21 report NRR/PRPB
NRR HANAGED SPENT FUEL POOL COOLING ISSUES 7 94 Item No.
38 Issue Evaluate calculated rad levels for ESW valve manipulations.
Reference p3 of cover letter to Part 21 report Lead Review NRR/PRPB Closure Document 39 40 41 42 Assess radiation levels in "buildings" during THI accident relative to RG 1.3 assumptions.
Evaluate regulatory limit for operator dose.
Evaluate operator dose to monitor fuel pool level.
Evaluate dose to ESW operator consider number of actions required and total dose.
(P34)
(p56) of October 1
meeting transcri t Aug 13 p12 item 25 Nov 7 LEP letter Nov 7 LSP letter NRR/PRPB NRR/PRPB NRR/PRPB NRR/PRPB 43 Evaluate dose to restore normal spent fuel pool cooling system.
Nov 7, LKP letter NRR/PRPB 44 Determine dose to operator for RHR actions.
Dec 6 L&P, Har 31, 93 ltr, p7 NRR/PRPB
NRR HANAGED SPENT FUEL POOL COOLING ISSUES 7 94 Item No.
46 47 49 50 51 Issue Determine applicability of requirement to use RG 1.3 source term in evaluating accessibility.
Evaluate effect of recirculation shutdown on airborne radioactivity concentrations.
Assess consequences of using RHR SFP cooling assist mode for accident unit SFP.
Evaluate regulatory requirement to use airborne source term for access evaluation.
Evaluate previous NRC Inspector findings that required consideration of airborne concentration in evaluating placement of sam le station; NRC IR 50-387 84-10 Evaluate need to assess environmental effects of SFP boiling based on calulated robabilit of boilin Evaluate adequacy of SGTS in ventilating reactor buildin Evaluate capability of RHR 5 CS pump room coolers to condense water vapor/steam.
Reference Oct 1, 1993 L&P, p3 III.A.2 Har 31, 1993 ltr Aug 13, 1993 ltr, p2 Apr 21, 1994
- ltr, 2
Nov 7 LEP letter Nov 23 xcpt, p59-62 Apr 21, 1994
- ltr, 2
Oct 1
LEP.,
letter p7, Har 31, 1993
- ltr, 7
Oct 1, transcript, P44 Dec 14, 1992 ltr Aug 13, 1993
- ltr, 3
ACRS ACRS ACRS Lead Review NRR/PRPB NRR/PRPB NRR/PRPB NRR/PRPB NRR/SPLB NRR/SPSB NRR/SPLB NRR/SPLB Closure Document
I f
(
NRR HANAGED SPENT FUEL POOL COOLING ISSUES 7 94 Item No.
52 53 54 55 56 57 Issue Evaluate time to reach specific temperature and humidity levels against qualification of components.
Assess adequacy of defining times to corn lete safet funtion for RHR.
Evaluate status of this issue relatve to ABWR.
Evaluate reliance on Emergency Oragnization to accomplish restoration or mitigating actions.
Evaluate range of new SFP level instruments Evaluate basis for using less than I/o day containment leakge in dose calculations Existing GDC and regulations require i'ssue to be treated as compliance Previous PPSL actions (1988 procedure change) make event part of licensing basis Other licensing basis discussions (Bulletin 94-01) are inconsistent with Harch 16, 1994 NRC discussion.
Reference ACRS ACRS NRR SPLB Har 31, 1993 ltr, pl0; Aug 13, 1993
- ltr, 7
Har 7, 1994
- ltr, 1
Har 7, 1994 ltr, pl Apr 21, 1994 1tr
'1 Har 21, 1994 ltr Har 21, 1994 ltr Hay 10, 1994 ltr Lead Review NRR/SPLB NRR/SPLB NRR/SPLB NRR/PRPB NRR/DRP Closure Document 10