ML20198Q337
| ML20198Q337 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/31/1997 |
| From: | Le N NRC (Affiliation Not Assigned) |
| To: | Sumner H SOUTHERN NUCLEAR OPERATING CO. |
| References | |
| TAC-M98303, TAC-M98304, NUDOCS 9711120177 | |
| Download: ML20198Q337 (4) | |
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4-Octcber 31, 1997 Mr. H. L. Sumner, Jr. s Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 l
Birmingham, Alabama 352011295
SUBJECT:
SPENT FUEL POOL REGULA:0RY ANALYSIS - EDWIN 1. HATCH NUCLEAR POWER PLANT, UNITS 1 AND 2 (TAC NOS. M98303 AND M98304)
Dear Mr. Sumner.
The NRC staff has completed its review of your June 23,1997, response to our request for edditional information dated May 9,1997, regarding the spent fuel regulatory analysis for the Edwin 1. Hatch Nuclear Power Plant, Units 1 and 2 (Hatch). The results of the staff's evaluation for plant Hatch, along with that of other plants that were selected by the staff for spent fuel pool regulatory analysis, have been included in the Commission Paper,
- Followup Activities On the Spent Fuel Pool Action Plan" dated September 30,1997. Enclosed for your information is a copy of the Commission Paper, if you have any question regarding this matter, please contact me at 301-4151458.
Sincerely.
ORIGINAL SIGNED BY:
Ngoc B. (Tommy) Le, Project Manager Project Directorate 112 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation g}
Docket Nos 50-321 and 50-366 DISTRIBUTION tDocket File';
Enclosure:
As stated PUBLIC OGC PDil 2 RF BBoger cc w/ encl: See next page NLe JShea
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JJohnson,Rll PSkinner,Rll g
Document Name: G: THATCH \\ REG ANA.LTR
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I Octtber 31, 1997 Mr. H. L. Sumner, Jr.
Vice President Nuclear Hatch Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 l
Birmingham, Alabama 35201-1295
SUBJECT:
SPENT FUEL POOL REGULATORY ANALYSIS EDWIN 1. HATCH NUCLEAR POWER PLANT, UNITS 1 AND 2 (TAC NOS. M98303 AND M98304)
Dear Mr. Sumnc.
The NRC staff has completed its review of your June 23,1997, response to our request for sdditionalinformation dated May 9,1997, regarding the spent fuel regulatory analysis for the
- Edwn. I. Hatch Nuclear Power Plant, Units 1 and 2 (Hatch). The results of the staff's evaluat on for plant Hatch, along with that of other plants that were selected by the staff for opent f e! pool regulatory analysis, have been included in the Commission Paper, ' Followup J
ActNmes On the Spent Fuel Pool Action Plan
- dated September 30,1997. Enclosed for your information is a copy of the Commission Paper, if you have any question regarding this matter, please contact me at 301-415-1458.
Sincerely, ORIGINAL SIGNED BY:
Ngoc B. (Tommy) Le, Project Manager Project Directorate ll 2 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 DISTRIBUTION Docket File ACRS
Enclosure:
As stated PUBLIC OGC PDil 2 RF BBoger cc w/ encl: See next page NLe JShea JJohnson,Ril PSkinner,Rll Document Name: GnHATCH\\ REG _ANA.LTR To receive a copy of this document, Indicate in the box: *c" = Copy w/ enclosure "E" = Copy w/ enclosure
- N* = No copy OFFICE PDil 2/PM PDil 2/LA nQ PDil hp)
NAME T.LE Tb L. BERRY hj fi.B M W DATE D / 3
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k UNITED STATES p:
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30H64001 October 31, 1997
%,'.....,o Mr. H. L. Sumner, Jr.
4 Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 352011295
SUBJECT:
SPENT FUEL POOL REGUt.ATORY ANALYSIS - EDWIN 1. HATCH NUCLEAR POWER PLANT, UNITS 1 AND 2 (TAC NOS. M98303 AND M98304)
Dear Mr. Sumner.
The NRC staff has completed its review of your June 23,1997, response to our request for additionalinformation dated May 9,1997, regarding the spent fuel regulatory analysis for the Edwin 1. Hatch Nuclear Power Plant, Units 1 and 2 (Hatch). The results of the staff's evaluation for plant Hatch, along with that of other plants that were selected by the staff for spent fuel pool regulatory analysis, have been included in the Commission Paper, ' Followup 4
Activities On the Spent Fuel Pool Action Plan' dated September 30,1997. Enclosed for your information is a copy of the Commission Paper, if you have any question regarding this matter, please contact me at 301415-1458.
Sincerely, Or**
i Ngoc B. (Tommy) Le, Project Mana9er Project Directorate 112 Division of Reactor Projects -1/11 Office of Nuclear Reactor Regulation Docket Nos. 50 321 and 50-36*
Enclosure:
As stated cc w/ encl: See next page j
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Edwin 1. Hatch Nuclear Plant cc:
Mr. Ernest L. Blake, Jr.
Charles A. Patrizia, Esquire Shaw, Pittman, Potts Paul, Hastings, Janofsky & Walker and Trowbridge 10th Floor 2300 N Street, NW.
12gg Pennsylvania Avenue Washington,DC 20037 Washington, DC 20004 g500 Mr. D. M. Crowe Cha!rman Manager, Lkansing Appling County Ccmmissioners Southem Nuclear Operating County Courthouse Company, Inc.-
Baxley, Georgia 31513 P. O. Box 12g5 Birmingham, Alabama 35201-12g5 Mr. J. D. Woodard Executive Vice President Residentinspector Southern Nuclear Operating Plant Hatch Company, Inc.
11030 Hatch Parkway N.
P. O. Box 12g5 Baxley, Georgia 31531 Birmingham, Alabama 35201-12g5 Regional Administrator, Region ll Mr. P. W. Wells U.S. Nuclear Regulatory Commission General Manager, Edwin 1. Hatch L Atlanta Federal CJnter Nuclear Plant 61 Forsyth Street, SW, Suite 23T85 Southem Nuclear Operating Atlanta, Georgia 30303 Company, Inc.
U.S. Highway 1 North Mr. Charles H. Badger P. O. Box 2010 Office of Planning and Budget Baxley, Georgia 31515 Room 610 270 Washington Street, SW.
Mr. R. D, Barker a
Atlanta, Georgia 30334 Program Manager Fossil & Nuclear Operations Harold Rehels, Director Oglethorpe Power Corporation Department of Natural Resources 2100 East Exchange Place 205 Butler Street, SE., Suite 1252 P. O. Box 134g Atlanta, Georgia 30334 Tucker, Georgia 30085134g i
Steven M. Jackson Senior Engineer-Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW -
Atlanta, Georgia 303284684
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UNITED STATES g
NUCLEAR RE TULATORY COMMISS10N o
WASHINOToN, D.C. 80%.001
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l Septemoer 30, 1997 l
HEMORANDUM TO: Chairman Jackson Comissioner Dlar Comissioner Dicus Comissioner McGaffigan p
FRON:
1.. Joseph Callan 0)erations /
18 L
Executive Director f C
SUBJECT:
FOLLOWUP ACTIVITIES 0 iE SPENT FUEL POOL ACTION PLAN In a memorandum to the Commission dated July 26, 1995, the staff reported the findings from the Spent Fuel Pool (SFP) action plan.
In that memorandum, the staff concluded that existing structures, systems and components related to the storage of irradiated fuel provide adequate protection for public health and safety. Concurrent with activities associated with the SFP action plan, the staff performed an independent review of all operating reactor licensees and found that each licensee was operating its spent fuel storage system in compliance with its operating license or could be before the next refueling outage. The results of this compliance review are documented in a memorandum to the Commission dated May 21, 1996. Notwithstanding these findings, the staff proposed to perform plant-specific evaluations or regulatory analyses to determine whether safety enhancement backfits could be justified at certain plants. The purpose of this memoranduu is to report the results of the plant-specific evaluations and regulatory analyses performed for this study.
On February 28, 1997, the staff informed the Commission that our followup activities would also include a review of refueling cavity seals at certain plants. The addition of this review was the result of findings from the Office for Analysis and Evaluation of Operational Data (AE00) study,
" Assessment of Spent Fuel Pool Cooling," dated October 3,1996.
The staff has completed the plant-specific evaluations and retulatory analyses for the eleven design issues identified in the staff's July 26 report and the memorandum to the Commission dated February 28, 1997. During our review, twelve licensees proposed certain voluntary actions to address the design issues identified in the staff's re) orts. A list of the licensees and their proposed actions is presented in Ta)1e 2 of the attached report. The staff will track the completion of these voluntary actions using the Comitment Tracking System.
CONTACT: ChristopherGratton,SPLB/DSSA/NRR (301) 415-1055 9
i a
The Commissioners 2
In the July 26 repor;, the staff concluded that regulatory analyses should be perforced for seven design issues to assess whether safety enhancements were warranted. The staff performed probabilistic screening analyses and found that, in most cases, event frequencies for sequences associated with these design issues were sufficiently low that further analyses were not warranted.
In one instance where the probabilistic screening criteria was met the staff performed a dtterministic evaluation of the issue using plant-spec}fic information and found that safety enhancements were not warranted. At LaSalle, the staff found unique design and operational features associated with the spent fuel pool cooling systems that require further analysis to i
determine whether safety enhancements are warranted. The staff concluded that, based on the results of these probabilistic evaluations r.nd with the exception of the outstanding issues at LaSalle, safety enhancements at plants with these sr.,ven design issues could not be justified and nu further actions will be taken. The staff also gathered and reviewed additional information about the four remaining design issues to determine the neef for safety enhancements. Based on a review of this additionni information, the staff determinei that safety enhancements at these plants are not justified and that no further analysis is required. Details of the staff's evaluations for all issues can be found in the attached report.
Other actions identified in the staff's July 26 report to address spent fuel storage issues, which include rulemaking and revising staff guidance for SFP evaluations, are still under development. The staff has issued SECY-97-168,
" Issuance for Public Comment of Proposed Rulemaking Package for Shutdown and Fuel Storage Pool Operation," requesting Comission approval to release for public comment the proposed rule on shutdown operations.
Revision of the staff's SFP evaluation guidance documents will be completed by October 1998, as described in our response to the Staff Requirements Memorandum dated October 2, 1996.
Attachment:
Report On Followup Actions From the Spent Fuel Storage Pool Action Plan cc: SECY OGC OCA OPA 4
CFO CIO
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ATTACHMENT REPORT ON FOLLOWUP ACTIONS FROM i
THE SPENT FUEL STORAGE POOL ACTION PLAN I
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1.0 BACKGROUND
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l The NRC staff developed and implemented a generic action plan for ensuring the safety of spent fuel storage pools in response to two separate postulated i
event sequences involving the spent fuel pools The principal safety concerns addressed by the actio(SFPs) at two plants.
j n plan involve the potential for a sustained loss of SFP cooling and the potential for a substantial loss l
of spent fuel coolant inventory that could expose irradiated fuel.
The first postulated event sequence was reported to the NRC staff in November 1992 by two engineers, who formerly worked under contract for the Pennsylvania l
Power and Light Company (PP&L.
thedesignoftheSusquehanna)stationfailedtomeetregulatoryrequirementsIn the i
with respect to sustained loss of the coolin function to the SFP that could
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result from a loss-of-coolant-accident (LOCA or a loss of offsite power i
(LOOP). The heat and water vapor added to t e reactor building atmosphere by subsequent !FP boiling could cause failure of accident mitigatLon or other safety equipment and an associated increase in the consequences of the-l initiating event. Using probabilistic and deterministic methods, the staff evaluated these issues as they related to Susquehanna and determined that i
public health and safety were adequately protected on the basis of existing' design features and operating practices at Susquehanna. However, the staff 4
also concluded that a broader evaluation of the potential for this type of i
eventtooccuratotherfacilitieswasjustified.
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The second postulated event sequence was based on an actual event that occurred at Dresden 1, which is permanently shutdown. This plant experienced contain:aent flooding because of freeze damage'to the service water system ~
inside the containment building on January $5, 1994. Commonwealth Edison reported that the configuration of the spent fuel transfer system between the SFP and the containment similarly threatened SFP coolant inventory control.
At Dresden Unit 1, portions of the spent fuel. transfer system piping inside the containment could have burst due to freezing at an elevation that would i
drain the spent fuel coolant to a, level below the top of stored irradiated--
I fuel.in the SFP. A substantial loss of SFP coolant inventory could lead to such consecuences as high local radiation levels due to loss of shielding, o
unmonitorec release of radiologically contaminated coolant, and inadequate
' cooling of stored fuel. -The staff concluded that the potential for this type j
of event to occur at other facilities should be evaluated.
Finally, the action plan itself called for a review of events related to wet storage of irradiated fuel. From the review of events related to wet storage l
of irradiated fuel and information from the two postulated event sequences that prompted development of the action plan, the staff identified areas to i
evaluate for further reguist' v action. Design information to support the SFP j
action plan's evaluation wt
< eloped through four onsite assessments, a i
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safety analysis report review for several operating reactors, and the staff's survey of refueling practices completed in May 1996.
Because the safety of fuel storage in the $FP is principally determined by coolant inventory, coolant temperature and reactivity, the staff divided its evaluation into those areas. Coolant Inventory-effects the capability to cool the stored fuel, the degree of shielding provided for the operatcrs, and the consequences of postulated fuel handling accidents. Coolant temperature affects operator performance during fuel handling control of coolant chemistry and radionuclide concentration, generatlon of thermal stress within structures, and environmental conditions surrounding the $FP. SFPs are designed to maintain a substantial reactivity marcin to criticality under all postulated storage conditions. In order for operators to promptly identify unsuitable fuel storane conditions, the spent fuel storage f acility must have SFP. propriate means So notify operators of changes to tie conditions in the an ap The report detailing the resolution of the $FP action plan was issued in a memorandum to the Commission dated July 26, 1996. Three courses of action were identified to address the concerns raised in the report: specific evaluations and (1 plant-(2)rulemaking,and(3 revision of staff guidance for SFP evaluation. Staff actionstoaddressrule)makingandrevisiontoguidancedocumentsarestill under development. The staff has issued SECY 97-168, " Issuance for Public Comment of Proposed Rulemaking Package for She Lwn and Fuel Storage Pool Operation," requesting Commission approval tc release for public comment the proposed rule on shutdown operetions. Revision of the staff's SFP evaluation guidance documents will be completed by October 1998, as described in our response to the Staff Requirements Memorandum dated October 2, 1996.
Concurrent with the SFP action plan, the staff conducted a compliance review of all licensees' spent fuel storage activities. The results were documented in a memorandum to the Commission dated May 21, 1996. At the time of the review, all plants were found to be in compliance with their licensing basis, or would be before their next refueling outage. The staff also concluded that SFP system design features and licensee operating practices were adequate in assuring protection for public health and safety. However, instances of incomplete or inaccurate documentation in licensee Final Safety Analysis Reports (FSAR) were-identified. The staff is developing specific enforcement guidance to address these instances of non-compliance regarding licensees' FSARs.
On February 10- 1996, the Executive Director for Operations directed the Office for Analysis and Evaluation of Operational Data (AE00) to perform an independent study of the likelihood and consequences of an extended loss of-spent fuel pool cooling. The report included a review of the potential for and the consequences of SFP coolant inventory loss due to the failure of the refueling cavity seal. The results of the AE00 study were reported to the Commission in a memorandum dated October 3, 1996. Office of Nucivar Reactor Regulation
-that they we(NRR) staff reviewed the results of the AE00 study and concluded re consistent with the findings of the SFP action plan. However, NRR decided to expand the scope of their SFP action plan followup activities
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to include a new category for the review of refueling cavity seals.
In a memorandum dated February 28,1997, the staff inforraed the Commission that additional information regarding the refueling cavity seal designs at certain plants would be gathered to detemine whether additional regulatory actions were warranted.
l This report provides the results of the plant-specific evaluations and reculatory analyses 1erformed for the 11 design features identified in the Juiy26reportandtiestaff'sfollowupmemorandumdatedFebruary l
28, 1997.
Overall, 48 of the 108 operating reactors have at least 1 of the following 11 design features of concern:
(1)
Absence of Passive Antisiphon Devices on Piping Extending Below the Top of the Stored Fuel (2)
TransferTebe(s)WithintheSFPRatherThanaSeparateTransfer Canal (3)
Piping Entering the Pool Below the Top of the Stored Fuel (4)
Limited Instrumentation for Loss-of-Coolant Events (5)
Absence of Leak Detection Capability or Absence of Isolation Valves in Leakage Detection System Piping (6)
Shared Systems and Structures at Multi-Unit Sites (7)
Absence of Onsite Power Supply for Systems Capable of SFP Cooling (8)
Limited SFP Decay Heat Rem 9 val Capability (9)
Infrequently Used Backup SFP Cooling Systems (10)
Limited Instrumentation for loss-of-Cooling Events (11)
Refueling Cavity Seals with Pneumatic Components Table 1 contains a list of the categories evaluated for this fo11cwup activity, the typ of evaluation performed i.e., regulatory analysis or evaluation), the plants' identified for each(category, and the source document of the design concern (i.e., NRR SFP action plan or the AEOD study on SFP cochng).
2.0 STAFF'S EEVIEW OF SFP ISSUES RESULTING FROM THE SPENT FUEL STORAGE ACTION PLAN AND THE AEOD STUDY OF SFP COOLING The staff sent copies of the resolution of the spent fuel storage action plan to each of the plants identified in the July 26 report and offered these licensees an opportunity to address the issues related to their plants.
Most of the licensees took the opportunity to respond to the request.
Some licensees informed the staff that they have taken or plan to take voluntary actions that would eliminate the need to conduct the proposed regulatory i
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4 analysis. Other licensees provided additional information about the design and operation of their plant to address the issues. The staff considered all of the licensees' responses in its evaluation.
ReviewM_tih2D19.21 The staff conducted a review for each category in the July 26 report and for the refueling cavity seal issue identified in the staff's memorandum to the Commission dated February 28, 1997. For each review, the staff either:
evaluated the licensees' voluntary actions as thay applied to the design (1) feature of concern for those licensees committing to voluntary actions, (2) performed a plant-specific screening analysis (probabilistic analysis) as a first step in the regulatory analysis process to determine whether safety enhancements could be justified, or (3) gathered additional information and evaluated the need for further regulatory analysis.
In each of the 11 categories identified for this study, the staff selected one or two plants as the lead plants for that category's review. The lead plant a
selection was based on plant design.
For those plants undergoing regulatory analysis, the lead plant re) resented the most rigorous tests for the safety enhancement backfit.
For tiose categories requiring further evaluation plants with the " worst-case' example of the design feature of concern we,re selected for each category. Lead plants were also selected on the basis that their design features were representative of all plants in their category so that decisions based on the analysis of these lead plants could then be applied to all other plants in the category.
If for some reason, a lead plant was eliminated from a category due to voluntary actions by the licensee or through a review of additional 'aformation, the next lead plant was selected on the same basis from the remaining plants in that category.
If the results of the screening evaluation of a lead plant indicated the need for further regulatory action, additional plants in that category would also be screened.
plants Takina Voluntary Actions In res plan, ponse to the staff's July 26 report on the resolution of the SFP action sevenal licensees informed the staff that they intended to perform certain voluntary actions to address the issues identified for their plants (See Table 2). The staff reviewed-the pro >osed actions by the licensees and determined whether the actions addressed tie design features of concern.
In some cases, the propose'd actions by licensees eliminated the need for further regulator licensee'y-actions for certain categories. 'The staff will track the s voluntary actions using the Commitment Tracking System to ensure the underlying issue is resolved in a timely manner.
plant-Soecific Reaulatory Analysis The staff's July 26 report concluded that plant-specific regulatory analysis should be performed for seven categories of design issues to determine whether a safety enhancement backfit was warranted. For these categories, a probabilistic analysis was performed as a screening criteria to determine the likelihood of attaining certain predesignated endstates. The staff visited seven plants, the lead plants for 5 of the 7 regulatory analysis categories, I
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l to gather plant-specific design and operational information to be used in the probabilistic analyses. For the other two regulatory analysis categories, one issue was resolved solely through voluntary actions by the licensees and the other issue was resolved by performing a probabilistic analysis using information already available to the staff.
Regulatory analysts were performed by first conducting a screening analysis us'ng plant-specific design and operational information. Two anistates were chosen to test the design features under evaluation. For inventory control analyses, an endstate corresponding to a SFP level one foot above the top of the SFP rack was used. For issues related to SFP boiling, an endstate corresponding to sustained boiling in the SFP for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> was used. These endstates chosen for this evaluation represent conservative points in the event secuences where public health and safety was assured (i.e., several magnituces.above the point of exposing fuel or causing a safety systemdegradation). The endstates were also chosen to be consistent with previous models used by the staff to evaluate SFP events (see the staff's safety evaluation of SFP issues at the Susquehanna plant, dated June Ig, 1995).
The staff used arobabilistic analyses to determine the frequency of these endstates for tie lead plants in each category. An endstate frequency greater than 1 x 10'5/yr indicated the need to perform further analysis of the design feature, including sensitivity analyses, value-impact analyses, or a An deterministic evaluation of the plan,t's response to the event sequence.
endstate frequency less than 1 x 10 /yr indicated that the probability of the nt could not be justified.
event occurring was low and that a saf,ety enhancep/yr, engineering judgement For endstates in the range between 10' /yr and 10' based on the margin available was used to determine whether further analysis
-was necessary.
Plants Reauirina Further Evaluation As a result of the staff's July 26 report and the review of the AEOD study of SFP cooling, the staff identified four categories where further evaluation of certain design features was required to determine whether additional regulatory action was warranted. For the plants in these categories, the staff gathered plant-specific information from the licensees through site visits, information requests, telephone conferences, and by reviewing archived information at the NRC. On the basis of these reviews, the staff made case-by-case determinations regarding the raed for further regulatory action.
3.0 RESULTS 3.1 Inventory Control Issues 3.1.1 Absence of Passive Antisinhon Devices on Pinina Extendino Below the Too of the Stored Fuel SFPs at four plants (Turkey Point 3 and 4, Robinson, and Davis-Besse) lacked antisiphon devices for piping that could, through improper operation of the system, reduce coolant inventory to a level that provides insufficient
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shielding and eventually expose the stored fuel.
In all cases, the piping is a drain path from the lower portion of the 3FP that is no-longer used by the licensees.
Licensees provide protection against a siphoning event by providing locked-closed Yalves,1roviding a low-level alara, and establishing operator actions to stop the sipion ficw and add makeup water. The staff believed that a design modification to introduce passive antisiphon protection for the SFP could be easily implemented at the plants currently lacking this protection. The staff planned to perform a regulatory analysis to determine whether such design modifications could be justified.
The licensees in this category took the opportunity to address this issue ir, their responses to the NRC. Each licensee provided similar testimony as to why a loss-of-inventory event through this piping should be cons 1Jered a low likelihood event. The piping at each plant is seismically qualified up to the first isolation valve and exposed to a benign environment and the isolation valve in the piping is normally locked closed and not included in any plant operating procedures. In addition, at the plants reviewed for this category, the lower suction piping connects to the normal suction line for the SFP cooling system which terminates six to twenty feet above the top of the spent fuel racks providing siphon protection if a siphon event occurred.
The upper isolation valve on the normal suction line would also have to be mispositioned to threaten the stored fuel, further reducing the probability of a siphon event occurring.
Regardless, the licensees in this category informed the staff that they are making voluntary modifications to their plants to further reduce the likelihood of an inadvertent inventory loss. The modifications to the SFP cooling systems include removing the valve and blanking the pipe or permanently locking closed and removing the valve operator from the piping of concerns. Other controls, for example, tagging the locking devices to alert operators to their significance, are planned to prevent operators from misaligning the valves.
On the basis of these voluntary actions, further regulatory actions are not warranted. The. staff will continue to follow the progress of the voluntary actions for the licensees in this category until they are completed.
- 3.1.2 Jeansfer Tubef s) Within the SFP Rather Than a Senarate Transfer Canal Transfer tubes are normally open during refueling operations. When these openings are below the top of the stored fuel without a passive design feature to ensure adequate coverage of the stored fuel (e.g., a weir locatet between th ' transfer tube-and the stored fuel), any drain path from the refueling
' has the potential to reduce coolant inventory in the SFP to an extent tnat the stored fuel could be exposed to air. Licensees with SFPs that do not have these passive design features currently provide protection against loss-of-inventory events in the SFP from leakage in the refueling cavity through level alarms, closure of the fuel transfer tube blank flange during reactor operations, and operator actions to isolate the leakage and add makeup water.
During the staff's review, which was conducted as part of the SFP action plan, the staff concluded that the relative rarity of a fuel transfer system lacking passive design features to prevent the uncovery of the stored fuel warranted a
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more detailed review of the system design and the administrative controls at these plants. The staff performed a probabilistic analysis of this issue to detemine whether further regulatory analysis would be needed.
STP designs at five plants (Oconee 1, 2, 3, Crystal River 3, and Maine Yankee) have fuel transfer tubes that enter directly into the pool below the level of the stored fuel with no passive design feature to separate the fuel transfer tube from the stored fuel. Of the five plants, the staff chose to perform this assessment at Oconee because the single SFP that services Units 1 and 2 has four fuel transfer tubes, increasing the frequency of operations with the transfer tube open and maximizing the flow rate out of the pool through the tubes should a large leak or other coolant diversion event occur somewhere in the refueling cavity or the reactor vessel. The staff considered the design of this spent fuel storage system to be a " worst case" compared with the other plants in this category.
The staff conducted a site visit to Oconee to collect plant-specific information rq arding the design of the Units 1 and 2 SFP and refueling cavities.
This information was used to develop a plant-specific probabilistic analysis to determine the extent to which the Oconee plant design affected the potential for a loss-of-coolant inventory event. The staff considered normal and refueling system configurations in its assessment and estimates for the likelihood for relevant pipe breaks, seismic events, and operator errors.
The staff's assessment found that even with four fuel transfer tubes penetrating directly into the SFP below the level of the stored fuel, because of the minimal amount of piping available to fail and the availability of the transfer. tube isolation valve to isolate leaks, the frequency of events resultip/yr.1 x 10' g in the uncovery of the fuel was estimated to be less than The probabilistic analysis oyantified the frequenev of each sequence that led to the endstate resulting in SFP coolant one foot above the top of stored fuel. As a result of the low likelihood that the fuel could be uncovered, the staff considers this design feature to be of relatively low risk-significance. On the basis of this finding, no further regulatory action will be taken on this issue for any of the plants in this category.
3.1.3 Pinina Enterina the Pool Below the Too of the Stored Fuel In addition to having transfer tubes that enter directly into the SFP, the three units at Oconee have an interfacing system, a portion of the standby shutdown facility (SSF), that connects to the transfer tube. The normal alignment of the transfer tube during reactor operations is to have the transfer tube-isolation valve open to allow the interfacing system to draw water from the SFP under emergency conditions (a blank flange is installed on
-the transfer tube to maintain containment integrity and to prevent leakage from the SFP$. This fuel transfer tube arrangement is unique to Oconee. Pipe breaks or misalignment of the valves supporting the SSF has the potential to drain coolant from the SFP to such an extent that fuel could be exposed to air. The-licensee provides protection against events involving this piping through seismic qualification requirements, design features such as a normally closed valve on each SSF line, direct level indication in the SFP, and training operators to take appropriate actions (e.g., isolate the leakage and
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8 addmakeupwater). However, the staff concluded that a safety enhancement modification involving this piping or other spent fuel storage systems may be justified to ensure adequate protection of the stored fuel.
A probabilistic analysis of this issue was performed to determine whether further regulatory analysis would be needed.
In the assessment described in Section 3.1.2 of this report, the staff considered the reactor coolant makeup piping that is part of Oconee's SSF.
That atsessment led the staff to conclude that the piping penetrating the SFP below the stored fuel is of low risk significance. The staff found that loss-of-coolant-inventory events involving the fuel transfer tube and interfacing piping that result in a SFP level one foot above the top of the fuel storage racks had a frequency of less than 1 x 10',/yr.
Therefore, as a result of this estimate of the low likelihood of a significant coolant inventory loss in the SFP due to this design feature and consistent with the findings of Section 3.1.2 of this report, the staff considers that further regulatory actions are not warranted.
3.1.4 Limited Instrumentation for loss-of-Coolant Events Some facilities have limited instrumentation to reliably alert operators to a loss-of-SFP coolant inventory. Direct SFP level instrumentation is not available to operators at certain plants as an indication of a loss-of-coolant event. Operators use related alarms (e.g., a loss-of-SFP cooling alarm or an alarm for low levels in the SFP cooling surge tanks), operating procedures, and direct observation to provide protection against loss-of-coolant events.
The staff performed a probabilistic analysis of this issue to determine whether any safety enhancement backfits to improve the SFP level monitoring capability could be justified under the current guidance.-
Seven plants (Big Rock Point, Dresden 2 and 3, Peach Bottom 2 and 3, and Hatch 1 and 2) oo not have direct level indication in their SFPs. In response to the staff's task action plan, four of the seven plants are taking voluntary actions to address this-issue. At Peach Bottom 2-and 3, the licensee is installing level switches in the SFP that will provide low level-alarms locally and in the control room. At Dresden 2 and 3, the licensee is adding administrative controls to site procedures to locally monitor pool level during periods when forced cooling-is secured or when AC power is lost. With the S P cooling system operable at Dresden, level in the SFP can be monitored using the alams associated with the SFP cooling system.
The staff selected four plants, Hatch 1-and 2 and Dresden 2 and 3, to evaluate whether limited level instrument affected the safe storage of spent fuel. The
-staff made site visits to these plants to gather plant-specific design infomation to be used in the probabilistic analysis. Hatch and Dresden were selected because they were representative of all plants in this category. Due to the design of the SFP and associated cooling systems of the plants in this category, conclusions based on the analyses performed for the Hatch and Dresden plants were considered to be applicable eu all plants in this '
y 4
9
' category. The staff performed a probabilistic analysis of event sequences dependent on SFP level indication to determine whether a safety enhancement backfit could be justified.
The staff found that for the four plants modeled for this analysis, the total endstate frequency for all sequences resulting in a SFP, level one foot above of the-top of the spent fuel racks was less than'l-x 10' /yr. The analysis took loss-of-cooling sequences without makeup water into consideration, as will as pipe breaks and flow diversions. <This low frequency indicates that
- additional analysis concerning direct SFP level 1ndication would not be cost beneficial. Therefore, the staff will not pursue further regulatory action on this issue for any plants in this category.
3.1.5 Absence of Leik Detection Canability or Absence of Isolation Valves in Leakaae Detection System Pioino Coolant inventory loss is not easily isolated following events that breach the SFP liner at facilities that do not provide a method of. isolating the liner leakoff system. The limited flow area through leak detection system telltale drains, the low leak rate through the seismically designed concrete structure, controls on movement of heavy loads over the fuel pool, and operator actions (to plug leak detection system drains and add makeup) provide protection at these plants. The staff noted in its raport on the resolution of the SFP task action plan that insufficient informatien was available at the time of the review to evaluate the makeup capability relative to credible leakage through the SFP liner.
Five plants were identified as having an SFP liner leakoff system that lacks a method for isolating a leak (Salem 1 and 2, DC Cook 1 and 2), or as having a liner that does not-include a leakoff system (Indian Point 2). -Two additional plants (Zion 1 and 2) that do not have liner leakoff isolation capability were identified after the the SFP action plan. publication of the July 26 report on the resolution of A review of the design information for each plant regarding credible leakage and makeup capability was performed by the staff to confirm that this issue had been addressed for these plants. The staff found that for all plants in this category, licensees have performed the necessary evaluations to ensure the available makeup rate to the-SFP exceeds the leakage rate for credible leakage scenarios.
On the basis of this as'sessment, the staff has detemined that no further regulatory action is warranted on this issue for any plaats in this category.
3.1.6 SFP Loss of Inventory Throuch Failure of the Refuelina cavity' Seal During refueling operations, refueling cavity seals-form a watertight boundary between the reactor vessel and the refueling cavity. -The seal is established and the refueling cavity is flooded so that the spent fuel can be transported safely from the reactor vessel to the SrP. Failure of this seal during refueling operations could dramatically lower the inventory level in the SFP.
.The staff focuted this review on boiling-water reactors (BWRs) with refueling cavity seals that contain pneumatic components. The staff selected BWRs
4:.
10 because the refueling cavity is isolated from the SFP thivugh the use of a gate that must be put in place with a building crane. Conversely, pressurized-water reactors transport spent fuel from the refueling cavity to the SFP through a tran.fer tube that contains a valve that can be closed in the event of a leak. Sudden gross leakage at a BWR, though unlikely, would be difficult to isolate before a significant level decrease would occur in the SFP. In addition, because pneumatic seals must have reliable air supplies to keep the seal from deflating and leaking, it is more likely that a significant leak would occur at plants that have pneumatic seals compared to plants with mechanical seals.
Of the five BWRs with pneumatic refueling cavity seals, three plants (Limerick I and 2 and Nine Mile Point 2) were selected for this evaluation. The staff-reviewed previous licensing information to determine whether these seals were susceptible to gross leakage or failure that could threaten stored fuel irdicating the need for further regulatory actions. Our review focussed on the design of the seal rather than its installation and testing because the seal must be installed and the cavity flooded to the level of the SFP before the refueling cavity is aligned with the SFP. This substantially reduces the risk of a seal failure that has been installed or tested incorrectly affecting the safety of the stored fuel. The cavity seals at the remaining two plants (Susquehanna 1 and 2) were extensively reviewed and accepted by the staff as documented in NUREG/CR-4525. " Closeout of IE Bulletin 84-03: Refueling Cavity Water Seal," dated June 1990, and are similar in design to the seals installed at Limerick I and 2.
In response to a refueling cavity seal event at Haddam Neck in 1984, the staff 4
issued Office of Inspection and Enforcement Bulletin (IEB) 84-03, " Refueling Cavity Water Seal." Licensees were required to evaluate the potential for a failure of a refueling cavity seal and provide a summary report to the NRC.
IE Informttion Notice 84-93, " Potential for Loss of Water From the Refueling Cavity," was issued late in 1984 to highlight events in which two failures-of pneumatic seals had the potential to drain the refueling cavity. A temporary instruction was also developed in late 1984 to prride guidance for performing reviews and inspections regarding utility responses to IEB 84-03.
The staff issued the findings from IEB 84-03 in NUREG/CR-4525 (June 1990).-
The study found that the Limerick 1 and 2 refueling cavity seal design uses two pneumatic seals, with keepers (to prevent seal. displacement even with a loss of air pressure),'one located above the other, in a narrow, fixed outer annulus. The outer annulus is covered with a plate fitted with compressible seals at each edge. The inner seal is a mechanical expandable bellows. Air supplies to the pneumatic seals are redundant. The seals include a leak detection system to alert operators to leakage past the pneumatic components.
Nine Mile Point 2 uses a Presray wedge-type refueling cavity seal design located in a narrow, fixed annular opening. The seal des _ign includes flanges that rest on the edges of the support plates. The annular opening is maintained at a fixed distance to provide interference if the seal becomes
i sl odged. The corners of the support plates are chamfered at the same angle as the seal so that a wedge effect occurs, becoming tighter as the water pressure above the seal increases. The annulus within which the seal fits 1
.=-
i e
g
+'
11 extends the full length of the seal thereby preventing the ballooning and hinging of the seal seen at Haddam Neck.
After reviewing the plant designs and sup>orting documentation submitted by the licensees in response to IEB 84-03, tie NRC concluded that the licensees for Limerick I and 2 and Nine Mile Point 2 complied with the actions required by the bulletin.
The report also came to the following conclusions:
(1)
The two major cavity seal leak events at Haddam Neck and Surry I were due to design and testing deficiencies unique to each plant..
(2)
Most applications of pneumatic seals incorporate the Precray design (e.g. those at Nine Mile Point 2, which uses a solid wedge the pr,imary seal and the inflated) portion as the backup seal. port' on as The inflated portion acts as the initial sealing mechanism until sufficient head butids up to seal the solid wedge. The success of this design has been adequately demonstrated.
(3)
In the few plants with pneumatic seals that do not use the solid wedge design (e.g., Limerick 1and2),someotherbackupmeansisprovided that is obviously adequate or has been tested.
For Limerick, this includes a stainless steel coverplate with compressible seals at each edge that covers the refueling cavity seal outer annulus. The coverplate acts to reduce leakage flow throu unlikely event of a pneumatic seal failure. gh the outer annulus in the In a separate study, the staff issued a generic evaluation of failures of refueling cavity and transfer gate pneumatic seals in NUREG-1353, " Regulatory Analysis for the Resolution of Generic Issue 82, 'Beyond Design Pasis Accidents in Spent Fuel Pools,'" dated April 1989.
The staff concluded that on the basis of the heightened awareness of refueling cavity seal design, installation, testing and maintenance; of the need for adequate procedures to r.ddress seal failures as identified in IEB 84-03; and considerin estimate frequency-is 3x10',e to diagnose a serious seal failure,g that ther is sufficient time svailabl the best fuel damage.
/ reactor-yr of a seal failure resulting in spent On the basis of the staff's conclusions in NUREG/CR-4525 concerning the acceptability of Nine Mile Point 2 and Limerick I and 2 refueling cavity seal designs, this review, and the low probability of a seal failure resulting in spent fuel damage as documented in NUREG-1353, the staff concludes that no further regulatory action is required for the plants in this category.
3.2 Decay Heat Removal Reliability Issues t
3.2.1 Shared Systems and Structures at Multi-Unit Sites At certain multi-unit sites, with one unit being refueled, the decay heat rate in the SFP may be sufficiently high that the pool could reach boiling in a short time following a loss-of-cooling event.
Communication between the fuel pool area and areas housing safety equi > ment supporting the operating unit through shared ventilation systems or slared structures may cause failure or i
y.._
12 I
degradation of those systems. Restrictive administrative controls on refueling operations, reliable SFP cooling systems, and operator actions to i
restore forced cooling and protect essential systems from the adverse environmental conditions that may develop during SFP boiling provide l
protection at these plants.
I The staff identified 13 plants at which SFP boiling may affect safety equipment in an adjoining unit through shared systems and structures. The staff reviewed the configuration of each plant in this category and performed a regulatory analysis of three plants (Hatch 1 and Dresden 2 and 3.
Hatch 2 i
is not included in this category because safety equipment required for the safe shutdown of Unit 2 is not affected by boiling of either Unit 1 or 2 SFPs). These plants were selected because they were representative of all 13 plants in this category. The staff conducted site visits to Hatch and Dresden i
j to gather plant-specific information about the design and operation of the i
spent fuel storage pool and cooling system. This information was used to perform the probabilistic analysis of the event sequences relevant to this l
design feature, i
To assess the effects of SFP boiling on safety equipment at these plants, an estimation of the frequency of sustained pool boiling event was calculated.
The staff calculated the frequency of the endstates (i.e., sustained SFP i
boilingforaminimumof8 hours,withorwithoutmakeuptotheSFP)that would have the capability of producing sufficient heat and water vapor to degrade the operating units' safety equipment. The endstates were chosen at j
raints in the event sequences where public health and safety were assured.
The staff calculated the frequency for these event sequences as a screening l
measure for this analysis, A sustained boiling frequency of approximately 10/yr was the basis to decide whether to perfom fu Sustained boiling frequencies of greater than 1 x 10'gther analyses,/yr indicate the i
i.
perform,/yr or less indicate that the frequency of these events is further analyses. However, sustained boiling frequencies of 1 x 10' i
i sufficiently low that even the lowest cost safety enhancements could not be justified. The staff used engineering judgement to determine whether further F
analysis was necessary for those sites wher the sustained boiling frequency
-was calculated to be between 10,/yr and 10'g/yr.
Initiating event sequences L
lL that were considered in this evaluation included the loss-of-SFP cooling system, seismic events, and loss of offsite power.
i i
l The results of the evaluttion indicated that there is a low likelihood of l
events that result in sustained boiling for Dresden 2 and 3.
The analyses concluded,/yr.that the frequency for events resulting in sustained boiling was
)
4.3 x 10' This low frecuency was primarily attributable to the reliability of the systems t1at provide cooling to the SFP. The Dresden SFP cooling system has pumps that receive power from an emergency onsite power source, and SFP cooling can be supplied from the Shutdown Cooling System which also receives backup power from an emergency onsite source.
s In its response to the staff's July 26 report on the resolution of the SFP action plan, the licensee for Dresden provided an analysis of the effects of sustained SFP boiling on safety equipment in shared spaces, indicating that high humidity and temperature could threaten the equipment required to
t..l s
13 mitigate a loss-of-coolant accident (LOCA) in an operating unit. However, the licensee noted that the SFP cooling systems, which include normal SFP cooling and shutdown cooling in the SFP cooling assist mode, are very reliable because of their redundant power supplies (i.e., two effsite sources, plus five onsita sources). The cooling systems' reliability, combined with the low probability of a concurrent LOCA plus a loss of offsite power event, makes the likelihood of a sustained SFP boiling event that affects safety equipment in the reactor building a low frequency event. The staff reviewed the licensee's evaluation, and based on our own independent probabilistic analysis, agreed with their conclusions.
- For Hatch 1 and 2, the sum o,f event sequences that result in sustained boiling had a frequency of 4.4 x 10' /yr. Event secuences resulting in evaporative cooling in the SFP was the dominated contrt>utor. Because this frequency exceeded the staff's screening criteria, additional analysis was required.
The staff found that the sustained boiling frequency for Hatch was dominated by an event sequence in which both units are initially operating. During plant operation, the non-safety related Spent Fuel Pool Cooling (SFPC) syster provides cooling to the Units 1 and 2 SFPs. The Alternate Decay Heat Removal (ADHR) system, with its normal power supplied by a separate switchyard from the SFPC systems, is also available to provide SFP cooling. With neither unit in refueling, however,.ADHR is not required to have its portable backup diesel generator available. An extended loss of offsite power that disables both plant switchyards would render both the SFPC and ADHR systems inoperable. The Residual Heat Removal Assist mode to provide (RHR) system can be aligned in the Fuel Pool Cooling cooling to the stored fuel, but at Hatch, this mode can only be used if the reactor vessel is aligned with the SFP in a refueling configuration. Therefore, fuel pool cooling assist mode of RHR would not be available during an extended loss of offsite power with both units configured for operation.
Several factors affect the probability of a sustained boiling event that were not included in the staff's probabilistic analysis. During normal plant operation, there is a lower decay heat load in the SFP and a longer time-to-boil compared with refueling operations. In the staff's analysis, no credit was given for any contingency actions by the licensee, such as supplying temporary power to the SFP cooling pumps during an extended lower outage, or obtaining a portable diesel for the ADHR system, either of witch would restore cooling to the SFP. Either of these contingency actions would lower the frequency of a sustair.ed SFP boiling event. The staff calculated the frequency of sustained boiling during refueling at Hatch with a full core offlord in one SFP, and with the alternate decay heat removal system in operation including its d was approximately 9 x 10',edicated diesel generator aligned and ready for use,
/yr. This fre In addition, quency is more consistent with the results found at Dresden.
due to the extended time-to-boil at these lower decay heat loads, critical safety equipment required for safe shutdown of an operating unit should have completed its requitec' safety functions or can be otherwise protected from the effects of the boiling pools before degradation occurs.
4
- me engene em m
,-...w n
L .
4 t
14 l
Regardless, the staff reviewed the effects of pool boiling on safety equipment located in shared :tructures. The licensee for Hatch provided an evaluation of the safety-related equipment located on the refueling floor and in the Unit I reactor building that could be exposed to high temperature and humidity during a pool boiling event, as well as an evaluation of the effects of r
a flooding due to the spread of condensation throughout these spaces. The temperature and humidity qualification of the equipment was compared with the expected environment for a sustained boiling event in the SFP. Based on the existing environmental qualification of this equipment and the relatively mild environment created by the sustained boiling event, the licensee determined that it was unlikely that any safety equipment required for the safe shutdown of an operating unit would be adversely affected. The licensee also provided an analysis based on conservative assumptions of the effects of flooding due to the condensation of vapor from the boiling SFPs and concluded that adequate equipment was available for the safe shutdown of the plant. The staff reviewed the licensee's evaluations and agreed with their conclusions.
Initially, the staff selected Hatch and Dresden as lead plants for this issue because they ware representative of the other plants in this category. During this review, it became apparent that the evaluations for the shared systems and structures issue were complex and plant-specific and that the results of evaluations should not be applied to the other plants in this category without further review.
After reviewing the results of the Dresden and Hatch evaluations backup power, the staff determined that plants having SFP cooling systems with from onsite sources have a low likelihood of sustained boiling.
Plants without onsite backup power for the SFP cooling system should receive further evaluation to determine the frequency of sustained boiling events.
The staff reviewed design features for the remaining ten plants in this category and found that eight plants have SFP cooling systems with onsite backup power. The two remaining plants (LaSalle 1 and 2) have the capability to supply onsite backup power to the SFP cooling system pumps, however, critical valves within each units' SFP cooling system have control power
-circuits that are not powered from onsite sources and would fail shut during a loss-of-offsite-power event, rendering the SFP cooling system inoperable.
In their response to the staff's July 26 report, the licensee for LaSalle acknowledged this condition and informed the staff that they are taking voluntary actions to ensure the control circuits in the unit experiencing the loss of offsite power will be supplied power from-the other unit's nonsafety-related source. These actions would restore the valves' function in the event of a plant-centered loss of offsite power. However, should a grid-related less-of-offsite-power event occur, both units' control power circuits would become de-energized disabling both SFP cooling systems. The staff has determined that this configuration, unique to LaSalle, warrants further analysis to determine whether a safety enhancement is warranted.
Based on these findings, the staff has determined that no further regulatory action is warranted for eleven plants in this category. However, for LaSalle 1 and 2, the staff will continue its regulatory analysis to determine whether a plant-specific safety enhancement can be justified.
15 23.2.2 Absence of Onsite Power Sueolv for Systems Caoable of SFP Coolina A sustained loss of offsite power at plants without an onsite power supply for SFP cooling may lead to departur from subcooled decay heat removal in the fuel pool, increased thermal str.s in pool structures, loss of coolant inventory increased levels of airborne radioactivity, and adverse environmen,tal effects in areas connunicating with the SFP area. Operator actions to align a temporary power supply from an onsite source or establish alternate cool' ng such as feed and bleed using a diesel-powered pump, high
-temperature alarms, filtered ventilation, and separition and isolation of areas containing equipment important to safety frt. the SFP area provide protection at tiese plants. To address this category, the licensee's
-capability to supply onsite power to the SFP cooling system relative to the time available for recovery actions was evaluated relative to the risks of a loss of all cooling.
Seven plants (Surry 1 and 2 Prairie Island I and 2 ANO 2, and 71on 1 and 2) were identified in the staff's re> ort on the resolution to the SFP action plan as not having onsite power avallaale to a system available to cool the SFP.
Licensees for four of the plants (SMy 1 and 2 and Prairie Island I and 2),
notified the staff of their intentions to install backup power to their SFP cooling system pumps from an onsite source. Of the three plants remaining, the staff selected Zion 1 and 2 for review because it was representative of the remaining plant in this group.
During initial licensing, the staff reviewed the design of plants without backup power to the SFP cooling system pumps and found that the use of evaporative cooling as a backup method for SFP cooling was acceptable, provided sufficient makeup was available to maintain SFP coolant inventory.
Although evaporative cooling is an available method of backup SFP cooling at these plants, it has never been used. Operating the SFP at elevated temperatures for evaporative cooling results in some adverse consequences that do not otherwise affect the safety of the stored fuel. These consequences include the inability to operate the SFP cleanu) system, effects on plant operations resulting from high temperature and tumidity in the spent fuel building, and long-term effects of elevated SFP temperature on the pool's concrete structure.
In response to the resolution of the SFP action plan, the licensee for Zion 1 and 2 provided an analy' sis that concludes that an extended loss of offsite nower event combined with a failure to establish makeup to the SFP is a low probability event. The sequence to be 2.1 x 10';1icensee calculated-the frequency of this event with any extraordinary ac/yr. Their evaluation did not credit their operators tions, such as connecting emergency power to the SFP cooling pumps, even though sufficient time may be available to perform such actions. If the probability of a failure to connect emergency power to the pumps were considered, the licensee estimsted the frequency of this event sequence to be less than 1 x 10/yr.
The staff reviewed the licensee's evaluations and perforrhed independent calculations which confirmed the licensee's conclusions for Zion. The staff found that the low frequency of an extended loss of offsite power combined 7...._......
- -- -...._... m
._._.m_____
16 with a failure to establish makeup to the SFP was primarily based on the reliability of the SFP makeup systems and the low non-recovery probability for loss of offsite power. The staff reviewed the design of the remaining plant in this category, ANO 2, and concluded that, due to the similarity in the design of the systems that support the storage of spent fuel, the results of the probabilistic analysis performed for Iion are representative of ANO 2.
On the basis of the low likelihood of a sustained loss of offsite power, the redundant makeup systems available to compensate for a boiling event, and the design of the spent fuel storage systems that have been. analyzed for boiling, the staff has determined that no further regulatory action for any plants in this category is warranted.
3.2.3 Limited SFP Decay Heat Removal Canability Assuming a full core discharge at an equivalent time after reactor shutdown during a period-of peak ultimate heat: sink temperature, some plants have higher SFP equilibrium design temperatures and shorter design recovery times than other similar plants. Licensees use administrative controls on refueling operations to ensure that spent fuel temperatures are controlled within the appropriate limits. The staff has previously reviewed.and approved the designs of these systems, however, the relatively high equilibrium design temperatures and short recovery times compared with other similar plants indicated the need for further review. The staff examined the administrative controls with respect to SFP temperature and available recovery time to determine the need for further actions.
The. staff identified four plants (Indian Point 2 and 3, Salem l' and 2) that have SFP cooling systems with limited decay heat removal capabilities. The staff reviewed design calculations; normal, abnormal and emergency operating procedures; and annunciator response procedures and held discussions with the licensee's SFP cooling system engineers to determine how these systems are actually operated compared with the assumptions and calculations used for their design.
Most spent fuel storage systems include a ecoling system with a relatively.
large heat capacity designed to maintain the SFP temperature below 150 'F
-under all offload conditions, including the failure of a single active component. The four plants included in-this category have relatively low cooling capacities. Under design conditions, which include the maximum decay heat load possible, ultimate heat sink temperature at its maximum design temperature, and the failure of a single active component, the SFP equilibrium temperature was calculated as high as 205 'F.
Higher equilibrium temperatures in the SFP limit the capability of the licensee to operate the SFP cleanup system and reduce the available time operators have to make provisions to add makeup water to the pool in the event of a sustained loss of cooling. High SFP temperatures also create operational problems for operators during refueling because of the high temperature and humidity in the fuel building.
The staff reviewed operating practices and procedures from three of the four plants (Salem I and 2, Indian Point 2) in this category to determine whether additional administrative controls were warranted. The staff also conducted
17 telephone interviews with site personnel to determine the actual operating conditions under which refuelings are conducted.
Based on the conversations with the licensees contacted for this issue, administrative controls are used to limit the temperature in the SFP. The licensees indicated that pool temperature at these sites have been consistently maintained below SFP cooling system alarm set less than 130 *F, even under full core offload conditions. points, normally Each licenses has procedures that direct their operators to take actions early in loss-of-coolin events to ensure temperature limits in the SFP are not exceeded. SFP hi h temperature alarms are typically set well below design and licensing lim ts to allow operators sufficient time to address any degraded conditions.
Procedures require operators to.take action to isolate the SFP cooling purification system and resolve the cooling inadequacy as SFP temperatures approach alarm setpoints.
In sore cases, operators are required to align makeup water to the pool if cooling is lost for an extended period, well in advan:e of pool boiling. The staff found that requiring operators to take mitigative actions to restore cooling at temperatures well below design temperatures, and make > reparations to add makeup water early in a loss-of-cooling event ensures t1at operators will have sufficient time to establish makeup and reduces the likelihood that boiling could occur without makeup water available.
Both licensees interviewed for this issue took additional measures that ensure significant margin to SFP temperature design limits. Though not m l ired, these licensees typically perform their refuelings in colder months to-take advantage of the additional cooling from low ultimate heat sink temperatures.
Although system design calculations at one plant in this category indicated that the SFP temperature could exceed 180 *F under design conditions with a
. full core offload, the practice of offloading when ultimate heat sink temperatures are low enables the licensee to maintain the SFP temperature below 125 *F.
In addition, preventive maintenance and repairs to the cooling
)
system are typically performed just before the refueling outage when the SFP decay heat load is low so that system malfunctions are minimized during refueling.
These practices and others are not exclusive to the licensees in this category but are commonly used throughout the industry to minimize risk during shutdown operations.
In addition, the staff is currently developing a proposed rule for shutdown -
operations that would provide clarification and improvements in the way licensees provide administrative control over the management of decay heat.
On the basis of our review of these plant-specific practices and procedures regarding the management of decay heat during shutdown operations, and due to the staff's current actions regarding the oevelopment of proposed shutdown regulations, the staff has determined that there is no need to pursue further regulatory analysis for any of the plants in this category.
3.2.4 Infreauentiv Used Backuo SFp Coolina Systems Infrequently operated backup cooling systems are relied on at plants in this
4 18 category more than other similar plants because of the absence of an onsite power supply for the primary SFP cooling system or the low relative capacity of the primary cooling system. Administrative controls on refueling optrations and availability of backup SFP cooling capability ensure that adequate cooling is available for the spent fuel. The staff examined the administrative controls on the availability of the backup cooling systems during refueling and technical analyses demonstrating the capability of these backup systems to determine the need for further regulatory analyses.
The staff performed a plant-specific review of this issue for four plants (Dresden 2 and 3, and Hatch I and 2 weredeterminedtoberepresentative). These plants were selected because they of the six other plants in this category.
These plants use a permanently installed backup system to augment SFP cooling during periods of high decay heat in the pool or during periods of maintenance when SFP cooling or other support systems are unavailable. Because these backup systems normally perform other functions or are staged in dry layup, the staff reviewed the licensees' administrative procedures for the control and use of these systems.
In addition, the staff verified the capability of one backup system to perform its function as described in the licensee's final safety analysis report (FSAR).
The staff found that the licensees reviewed for this study manage decay heat using an outage safety assessment in a manner consistent with NUMARC 91-06,
' Guidelines for Industry Actions To Assess Shutdown Management." Outage safety assessments provide methods for documenting the availability of systems and components that provide adequate core and fuel pool cooling, provide emergency power supplies, and provide containment. Systems available to provide primary and backup SFP cooling are identified to the operational staff through this assessment and are updated as conditions change throughout the outage period.
The staff also found that systems relied upon to provide augmented cooling to the SFP under the high heat load conditions associated with refueling at the plants in this category were aligned, inspected, and tested before the licensee began the transfer of fuel assemblies. Often these systems require spool-pieces or special system alignments to provide this cooling function.
Requirements to prepare these backup systems for use were contained in the appropriate refueling procedures.
However, at one site, the licensee found that the backup cooling system could not provide the required flow rate to the SFP as described in the FSAR. The licensee performed an operability determination to verify that the actual flow of the backup cooling system would provide sufficient cooling to keep the stored fuel below its temperature limits under design conditions. The licensee found that the original design calculations wcN conservative and that the actual system flow rate provides sufficient culing to the. stored fuel under design conditions. The licen a ? Dlans to update its FSAR with the latest design parameters and the results of the updated calculations, as appropriate.
On the basis of the staff's findings that the backup cooling systems are used regularly during refueling outages, the systems are aligned and tested by
f 19 I administrative procedures before the commencement of fuel offload, and administrative controls are in place to manage decay heat during refuel periods, the staff has determined that no further regulatory action is required on this issue.
3.2.5 Limited Instrumentation for loss of Coolino Events The capability of instrumentation to alert operators to a sustained loss of SFP cooling is limited at certain plants. Fuel storage pools at most sites have direct tem >erature indication. However some sites rely on temperature indication in tie SFP cooling and cleanup sys, tem (SFPCCS) to provide an indication of the temperature of the coolant in the acol. A loss of firw in the SPFCCS would prevent operators from monitoring tse temperature of the pool and could lead to delays in identifying a loss-of-cooling event. Related alarms, along with operating procedures, and operator identification would provide protection for the stored fuel if a loss-of-cooling event occurred.
The staff evaluated this issue to determine whether additional instrumentation or operational controls were warranted on a safety enhancement basis at these plants..
The staff identified 10 plants (ANO 1. Big Rock Point, Brunswick 1 and 2, Cooper, Hatch I and 2, lasalle 1 and 2, and Millstone 1) that had limited temperature instrumentatinn for loss-of-cooling events and selected the Hatch facility for this assess' ment because the Hatch plant configuration was representative of the other plants in this category and it also had other design features being evaluated as part of this study. The staff visited the site to document the instrumentation and procedures available to the operators to control and monitor cooling of the stored fuel in the SFP so that they could be used to construct a plant-specific probabilistic analysis. This information was used to assess the effects of having limited temperature indication during loss-of-cooling events.
The probabilistic analysis performed at Hatch indicated a low likelihood of sustained loss-of-cooling events and loss-of-inventory events. The staff found no indication that the lack of direct temperature indication significantly increased the likelihood associated with identifying or mitigating loss-of-cooling events in the SFP. Alternate instrumentation available to operators provides indication and alarm (e.g., SFP cooling and cleanup temperature indication). Administrative controls that are put in
~
place when SFP cooling is secured or becomes otherwise disabled (e.g., installing temporary temperature indication in the pool if cooling is lost for a significant period) provide adequate information to operators concerning the status of pool cooling.
On the basis of the available alternate in'strumentation, administrative controls, and the low frequency of loss-of-cooling events and loss-of-inventory events associated with the lack of direct-tem)erature instrumentation for the SFP the staff has determined t1at further regulatory actions on this issue are no,t warranted.
'" c j +,,
20 4.0
SUMMARY
The staff has completed its actions to perfom plant-specific evaluations and regulatory analyses of issues that were identified in the resolution of the SFP action plan and the AE00 study on SFP cooling and provides the following sumary of issues and resolutions.
In their response to the staff's report dated July 26, 1996, 12 licensees volunteered to perform actions ranging from procedural changes to plant modifications.
A list of these licensees and their proposed actions is presented in Table 2.
The staff reviewed the licensees' voluntary actions and agreed that they address the issues identified in the staff's July 26 report for their raspective plants. The staff will track the licensees' actions using the Comitment Tracking System to ensure the underlying issue is resolved in a timely manner.
For the four plants in the category " Absence of Passive Antisiphon Devices on Piping Extending Below the Top of the Stored Fuel," the proposed actions by these licensees, which include modifications to the plants (e.g., valve removal or installation of a permanent locking device) ant administrative controls that further reduce the arobability that these valves could be inadvertently operated, resolve t1e staff's concerns on this issue.
Therefore, no further regulatory action is warranted.
For the categories " Transfer Tube (s) Within the SFP Rather Than a separate Transfer Canal," and " Piping Entering the Pool Below the Top of the Stored Fuel," Oconee was evaluated because it has the most transfer tubes penetrating the SFPs, and is the only site that has an interfacing system. The results of the staff's probabilistic analysis indicated a low likelihood (less than 1 x 10/yr) that stored fuel could become uncovered, indicating that this design feature is of relatively low risk-significance.
On this basis, no further regulatory action will be taken for the plants in this category.
The staff's evaluation of the " Limited Instrumentation for loss-of-Coolant Events," and " Limited Instrumentation for Loss of Cooling Events," determined that no event sequence resulted in a SFP level one foot p/yr and there w bove the top of the fuel storage racks with a frequency greater than 1 x 10' indication that the lack of direct temperature indication significantly increased the likelihood associated with identifying or mitigating loss-of-cooling events in the SFP.. Also, alternate instrumentation and administrative controls are available to operators to provide information concerning the status of pool cooling. Therefore, no further regulatory actions will be
-taken for the plants in these categories.
For the five plants in the category of " Absence of Leak Detection capability or Absence of Isolation Valves in Leakage Detection System Piping," the staff found that the licensees performed the necessary evaluations to ensure that the available makeup rate to the SFP exceeded the leakage rate for credible leakage scenarios. Therefore, no further regulatory action is warranted.
The category entitled "SFP Loss of Inventory Through Failure of the Refueling Cavity Seal" was added to this study as a restilt of AEOD's review of SFP
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21 cooling. The staff evaluated the design and licensing of three BWR refueling cavity seals, and found that no further regulatory action is warranted regarding this design feature.
conclusions in NUREG The staff based this finding on the staff's cavity seal designs /CR-4525 concerning the acceptability of the refueling at Nine Mile Point 2 and Limerick I and 2, the results of this review, and the low probability of a seal failure resulting in spent fuel damage as documented in NUREG-1353.
The staff performed regulatory analyses for three of thirteen plants in the category " Shared Systems and Structures at Multi-Unit Sites," and reviewed the designs of the other ten plants to ensure that the results of the regulatory analysis were applicable to these >1 ants. The staff found that at plants where the systems cooling the SFP 1 ave backup lower from onsite sources, there is a low likelihood of events that result in tie sustained boiling of the SFP.
Because Hatch does not supply backup power from an onsite source to their available SFP cooling syste.ns during normal plant operation, the staff evaluated the effects of sustained boiling on equipment required for the safe shutdown of the reactor. The staff found that the qualification of this equipment exceeded the expected environment created by boiling in the SFP and that potential flooding caused by condensation would not threaten any vital equipment.
During the review of the remaining plants in this category, the staff determined that LaSalle 1 and 2 may experience sustained boiling during certain loss-of-offsite-power events, and that further evaluation is necessary to determine whether a pit.nt-specific safety enhancement is warranted.
For the other eleven plants in this category, the staff has determined that further evaluation is not warranted.
The staff found that no further regulatory action was necessary for the category " Absence of Onsite Power Supply for Systems Capable of SFP Cooling" on the basis of the low likelihood of a sustained loss of offsite power, the redundant and reliable makeup systems available to compensate for a boiling event, and the design of the spent fuel storage systems that have been analyzed for boiling.
For the four plants that have SFP cooling systems under the category " Limited SFP Decay Heat Removal Capability," the staff found that there is no need to perform any further regulatory analysis based on existing licensee practices and procedures for managing decay heat in the SFP. Even though the plants in this category are susceptible to relatively high SFP temperatures due to the design of their spent fuel storage systems, the staff found these licensees employ practices to limit the SFP temperatures to below the SFP cooling system alarm setpoints which are set significantly below design limits and have administrative controls in place to add makeup water early in a loss-of-cooling event.
The staff is also in the process of formulating regulations to clarify and itaprove the way licensees manage decay heat during shutdown operations.
Four plents were evaluated under the category " Infrequently Used Backup SFP Cooling Systems."
The staff found that these backup cooling systems are used regularly during refueling outages, that the systems are aligned and tested by administrative procedures before the commencement of fuel offload, and that
)
administrative controls used manage decay heat during refuel periods. At one
s.
.e e e s
22 dual unit site provide the coo, ling flow rate described in the FSAR.however, the staff found tha The licensee aus performed the necessary calculations to ensure the system is capable of providing adequate cooling to the SFP and will update their FSAR. Based on these findings, the staff found no need to pursue further regulatory action.
The staff has completed its actions to perform the evaluations and regulatory analyses identified in our July 26 report to the Commission on resolution to the SFP action plan.
Other planned actions identified in resolution to the SFP action plan report, which include rulemaking and revising the staff guidance for SFP evaluations, are still under development. The staff has issued SECY-97-168, " Issuance for Public Comment of Pro Package for Shutdown and Fuel Storage Pool Operation," posed Rulemaking requesting Commission approval to release for public comment the proposed rule on shutdown operations.
Revision of the staff's SFP evaluation guidance documents will be completed by October 1998, as described in our response to the Staff Requirements Memorandum dated October 2, 1996.
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23 i
TABLE 1 SFP DESIGN FEATURES IDENTIFIED IN THE JULY 26 REPORT Category Review Pinot sosece Absene dressh. - '
Deviene se riplag sneeneme asemer the Tap dihe Sessed Feel Regueseary Iteblasse. D h FestR Ammeysis Turkey reise Tremesse Tube (s) Walhis the SFP Retur Den e Seperses Treaster Canal Reguaseary Ocesse*.Caymet Alver.
FestR A ser M i.e vedes Firing Esameing abe Pm4 Below the Top of the Sassed Fusf Reguissory Ocesse*
PsitR Aa=8y==
IJsuhed baserummmenden Amr Immed<asend Besses Reselseary Dresdes". ]lggh*, Big Reedt Pelm Ptssh tuneen MitR Aassy
="
jagste reist 2.Esima. D.C.C==k reta Atenacedtask DeesselenCapsheryer Abesasedsesenessa ves In a Dee eisensysesse i=ter== mea Firing mes.heory presdue*. Heath f*. Cahen CEGh D.C. Cost.
NUtR shes.d sysemme and Sm aw m uses-Unk Snee Amasy us.ms.
Poise Bemeh. Quad Chlos PetR Ahemmee dOmske Peeer Snyply ser Syseene Capshes of SFP CosEag Reguimesy Zigt. Afs0 2. Pembis M Suny Aasey==
peutR Addissanaf jeden.Psist 2.5sfem IJaulted SFP Doesy Nest stensevat Csyshiery Interinsessa e
I Addiesenet presdem*. Ilesc4*. Suomas Feery. Duetesse.
MPJt i,
-~
" Used Bestup SFP CosEsg Sysesaw sarer==eme Fernsi. Meerserick.WNP.2 9
MutR I
Res.heory pseer6*. Apot, sig meek rehs. me ms.esh.C per.
8 m huanumssessen ser tas fe Eng m. esse A,_
LaSalls. Millseeme AEOD Addissonal LineetkII. IWee M l'
Reeseling Cavity Seels widi Passuunnels Cessyoneses hter sms a
- t i
- the suost rigeeous llee===a,Ismed plane (s).as selected as the lead seview plant (s) for each category. Design fessores at these plunds
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Notes:
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.e s,.,,he m.m I, sis _ sm ees
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e n.
1.
-l Resolution of the Spent Feel Settage Pool Action Plssi Issues. July 26.1996.
2.
NRR:
AEOD: Assessment of Spent Feel Cooieng. October 3.1956.
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