ML20076B634
| ML20076B634 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 09/24/1982 |
| From: | Ludington B, Overbeck G, Vosbury F Franklin Research Ctr, Franklin Institute |
| To: | Chow E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20076B636 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 TER-C5506-280, NUDOCS 8209290030 | |
| Download: ML20076B634 (14) | |
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i TECHNICAL EVALUATION REPORT l
ECCS REPORTS (F-47)
TMI ACTION PLAN REQUIREMENTS WISCONSIN PUBLIC SERVICE CORPORATION l
KEWAUNEE NUCLEAR POWER PLANT NRC DOCKET NO.
50-305 FRC PROJECT C5506 FRC ASSIGNMENT 7 NRC CONTRACT NO. NRC43-81-130 FRC TASK 280
- 8##8#UF F. W. Vosbury Franklin Research Center Author:
G. J. Overbeck 20th and Race Streets B. W. Ludington Philadelphia, PA 19103 FRC Group Leader: G. J. Overbeck Prepared for Nuclear Regulatory Comrnission Lead NRC Engineer:
E. Chow Washington. D,C. 20555 September 24, 1982 1
l This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their empicyees, makes any warranty, expressed or Impfled, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, appa-ratus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.
Prepared by:
Reviewed by:
Approved by:
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Date-Cate-Date:
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. Franklin Research Center A Division of The Franklin institute The Sengtrun Frannst, Partmey, PMs. Pa. 19103(2151 448 1000
TER-C550 6-28 0 l
QNTENTS Section Title Page 1
INTBODUCTION 1
1.1 Purpose of Review.
1 1.2 Generic Background.
1
- 1. 3 Plant-Specific Background.
2 2
AEVIEW CRITERIA.
3 3
TECHNICAL EVAIDATION 4
3.1 Review of Completeness of the Licensee's Report 4
3.2' Comparison of ECC System Outages with those of Other Plants.
4 3.3 Review of Proposed Changes to Improve the Availability of ECC Equipment.
6 4
CONCIRSIONS.
8 5
REFERENCES.
9 nklin Rese
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TER-C550 6-28 0 FORENDRD This Technical Evaluation Report was prepared by Franklin Research Center under a contract with the U.S. Nuclear Regulatory Commission (Office of Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance in support of NRC operating reactor licensing actions. The technical evaluation was conducted in accordance with criteria established by the NRC.
Mr. G. J. Overbeck, Mr. F. W. Vosbury, and Mr. B. W. Ludington contributed to the technical preparation of this report through a subcontract with WESTEC Services, Inc.
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TER-C5506-2SO 1.
INTRODUCTION 1.1 PURPOSEOF'REhEN This technical evaluation report (TER) documents an independent review of the outages of the emergency core cooling (ECC) systems at Wisconsin Public Service Corporation's (WPSC) Kewaunee Nuclear Power Plant. The purpose of this evaluation is to determine if the Licensee has submitted a report that is complete and satisfies the requirements of 1MI Action Item II.E.3.17, " Report on Outages of Baergency Core-Cooling Systems Licensee Report and P-oposed hchnical Specification Changes."
1.2 GENERIC BACKGROUND Pb11owing the Three Mile Island Unit 2 accident, the Bulletins and Orders Task Nece reviewed nuclear steam supply system (NSSS) vendors' small break loss-of-coolant accident (IDCA) analyses to ensure that an adequate basis existed for developing guidelines for small break LOCA emergency procedures.
During these reviews, a concern developed about the assumption of the worst single failure. Typically, the small break LOCA analysis for boiling water reactors (BWRs) assumed a loss of the high pressure coolant injection (HPCI) system as the worst single failure. However, the technical specifications l
permitted plant operation for substantial periods with the HPCI system out of service with no limit on the accumulated outage time. There is concern not only about the HPCI system, but also about all ECC systems for which substan-tial outages might occur within the limits of the present technical specifica-tion. Therefore, to ensure that the small break LOCA analyses are consistent with the actual plant response, the Bulletin and Orders Task Force recommended in NUREG-0626 [1], " Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in GE-Designed Operating Plants and Near-TWrm Operating License Applications," that licensees of General Electric (GE)-designed NSSSs do the following:
" Submit a report detailing outage dates and lengths of the outages for all ECC systems. The report should also include the cause of the outage _
l (e.g., controller failure or spurious isolation). The outage data for l
ECC components should include all outages for the last five years of d!J Franidin Research Center 4 on a.a n. r, men m
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TER-C5506-280 operation. The end result should be the quantification of historical unreliability due to test and maintenance outages. This will establish if a need exists for cumulative outage requirements In technical specifications."
Later, the recosumendation was incorporated into NUREG-0660 [2], "NBC Action Plan Developed as a Result of the THI-2 Accident," for GE-designed NSS8s as TMI Action Item II.K.3.17.
In NUREG-0737 [3], " Clarification of TMI Action Plan Requirements," the NRC staff expanded the Action Item to include all lightwater reactor plants and added a requirement that licensees propose changes that will improve and control availability of ECC systems and components. In addition,'the contents of the reports to be submitted by the licensees were further clarified as follows:
"The report should contain (1) outage dates and duration of outages; (2) cause of the outages (3) ECC systems or components involved in th., outage; and (4) corrective action taken."
1.3 PLANT-SPECIFIC BACKGROUND On January 5, 1981 [4], WPSC submitted a report in response to NUREG-0737, Item II.K.3.17, " Report on Qatages of Emergency Core-Cooling Systems Licensee Report and Proposed Technical Specification Changes." The report submitted by WPSC cove-ed the period from January 1,1976 to December 31, 1980 for the Kewaunee Nuclear Power Plant. WPSC did not propose any changes to improve or control availability of ECC systems.
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TER-C5506-280 2.
REVIBf CRITERIA The Licensee's response to NUREG-0737, Item II.K.3.17, was evaluated against criteria provided by the NRC in a [[letter::05000305/LER-1981-023-03, /03L-0:on 810621,boric Acid Found Leaking from Instrument Isolation Valve CVC-11188.Caused by Leaking Diaphragm & Corroded Bonnet.Transfer Pump 1A Isolated & Bonnet Assembly Replaced|letter dated July 21, 1981]] (5]
outlining Tentative Work Assignment F.
Provided as review criteria in Reference 5, the NRC stated that the Licensee's response should contain the following information:
1.
A report detailing outage dates, causes of outages, and lengths of outages for all ECC systems for the last 5 years of operation. This report was to include the ECC systews or components involved and corrective actions taken. Test and maintenance outages were to be included.
2.
A quantification of the historical unavailability of the ECC systems and components due to test and maintenance outages.
3.
Proposed changes to improve the avaLlability of ECC systems, if necessary.
The type of information required to satisfy the review criteria was clarified by the NBC on August 12, 1981 (6]. Auxiliary systems such as component cooling water and plant service water systems were not to be considered in determining the unavailability of ECC systems. Only the outages of the diesel generators were to be included along with the primary ECC system outages. Finally, the "last five years of operation" was to be loosely interpreted as a continuous 5-year period of recent operation.
i on July 26, 1982 (7], the NRC further clarified that the purpose of the review was to identify those licensees that have experienced higher ECC system l
outages than other licensees with similar NSSSs. The need for improved reliability of diesel generators is under review by the NBC. A Diesel l
Generator Interim Reliability Program has been proposed to effect impecv'd performance at operating plants. As a consequence, a comparison of diesel generator outage information within this review is not required.
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l TER-C5506-280 l
I 3.
TECHNICAL EVALUATION 3.1 REVInt OF COMPLETEMESS OF THE LICENSER'S REPORT The ECC systems at WPSC's Kewaunee Nuclear Power Plant consist of the following four separate systems:
o accumulators o safety injection system (SIS) o residual heat removal (RER) 4 o refueling water storage tank (RNST).
In establishing the type of events that constitute an ECC system outage, WPSC considered an outage to be any event that rendered an ECC system unable
-to respond -daritig plant conditions for which technical specifications required BCC system operability.
j For each ECC system outage event, WPSC provided the outage dates, the duration, and the cause, plus sufficient description to discern the corrective
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action taken. Maintenance and surveillance testing activities were included in the ECC system outage data. S e results of WPSC's review were provided for the period from January 1,1976 to December 31, 1980 for the Kewaunee Nuclear Power Plant.
Based on the preceding discussion, it has been established that WPSC has submitted a report which fulfills the requirements of review criterion 1 without exception.
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3.2 COMPARISON OF ECC SYSTDI OUTAGES WITH THOSE OF OTHER PLANTS l
(
The outages of ECC systems can be categorized as (1) unplanned outages due to equipment failure or (2) planned outages due to surveillance testing or preventive maintenance. Unplanned outages are reportable as Licensee Event Reports (LERs) under the technical specifications. Planned outages for periodic maintenance and testing are not reportable as LERs. He technical specifications identify the type and quantity of ECC equipment required as well as the maximum allowable outage times. If an outage exceeds the maximum
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TER-C5506-280 allowable time, then the plant operating mode is altered to a lower status consistent with the available ECC system components still operational. The purpose of the technical specification maximum allowable outage times is to prevent extended plant operation without sufficient ECC system protection.
The maximum allowable outage time, specified per event, tends to limit the unavailability of an ECC system. However, there is no cumulative outage time limitation to prevent repeated planned and unplanned outager from accumulating extensive ECC system downtime.
Unavailability, as defined in general terms in NASE-1400 [8), is the probability of a system being in a failed state when required. However, for 4
this review, a detailed unavailability analysis was not required. Instead, a t
preliminary estimate of the unavailability of an ECC system was made by calculating the ratio of the ECC system down::ime to the number of days that the plant was in operatic n during the last 5 years. To simplify the tabula-tion of operating time, only the period when the plant was in operational Mode 1 was considered. T!Pis simplifying assumption is r,easonable given that the period of time that a plant is starting up, shutting down, and cooling down is small compared to the time it is operating at power. In addition, an ECC system was considered down whenever an ECC system component was unavailable due to any cause.
It should be noted that the ratio calculated in this manner is not a true measure of the ECC system unavailability, since outage events are included that appear to compromise system performance when, in fact, partial or full function of the system would be expected. Full function of an ECC system would be expected if the design capability of the system exceeded the capacity required for the system to fulfill its safety function. Per example, if an ECC system consisting of two loops with multiple pumps 'in each loop is designed so that only one pump in each loop is required to satisfy core cooling requirements, then an outage of a single pump would not prevent the system from performing i
I its safety function. In addition, the actual ECC system unavailability is a function of planned and unplanned outages of essential support systems as well as of planned and unplanned outages of primary ECC system components. In nklin Research Center A Dhimon of The Femruen Inumane
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TER-C5506-280 accordance with the clarification discussed in Section 2, only the effects of outages associated with primary ECC system components and emergency diesel generators are considered in this review. The inclusion of all outage events assumed to be true ECC system outages tends to overestimate the unavailability, while the exclusion of support system outages tends to I
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underestimate the unavailabilityk of..ECC systems and components. Only a detailed analysis of each ECC system for each plant could improve the confidence in the calculated result. Such an analysis is beyond the intended scope of this report.
The planned and unplanned (forced) outage times for the four ECC systems (accumulators, SIS, RER, and IOfST) were identified from the outage information in Reference 4 and are shown in number of days and as percentage of plant operating time per year in Table 1 for the Kewaunee Ikiclear Power Plant.
Outages that occurred during nonoperational periods were eliminated as were those caused by failures or test and maintenance of support systans. Data on plant operating conditions were obtained from the annual reports, " Nuclear Power Plant Operating Experience" (9-12], and from monthly reports, " Licensed Operating Reactors Status Susmary Reports" [13]. The remaining outages were segregated into planned and unplanned outages based on WPSC's description of the causes. The outage periods for each category were calculated by summing the individual outage durations.
Observed outage times of various ECC systems at Kewaunee Nuclear Power Plant were compared with those of other PWRs. Based on this comparison, it was concluded that the historical unavailability of the accumulators, SI, RRR, and RNST systems has been consistent with the performance of those systems throughout the industry. The observed unavailability was less than the industrial mean for all ECC systems, assuming that the underlying unavail-ability is distributed lognormally. The outage times were also consistent with existing technical specifications.
3.3 REVIEW OF PROPOSED CHANGES TO IMPROVE THE AVAILABILITY OF ECC EQUIPMENT In Reference 4, WPSC did not propose any changes to improve the availability of ECC systems and components.
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Table 1.
Planned and Unplanned (Forced) Outage Times for the Eewaunee Plant *
'i a
$IS MMR 50fST I
28 Days of Plant Outage in Days Outage in Dave Gutage in Days Outage in Days Year Operation Forced Planned Forced Planned Forced Planned Forced Planned la 4
[n 1976 288.6 0.0
.0.0 0.0 0.80 0.0 0.80 0.0 0.0 j
[$
(0.2st)
(0.2st) 4 1977 291.3 0.0 0.0 0.0 0.00 0.0 0.0 0.0 0.0 (0.27t)
(0.274) i 1978 326.5 0.0 0.0 0.38 0.83 0.0 0.83 0.0 0.0 i
4 (0.126) (0.256)
(0.2:54) i 1979 280.5 0.0 0.0 0.0 0.80 0.0 0.80 0.0 0.0 (0.2Cl)
(0.284)
)
]
1980 305.0 0.0 0.0 0.63 0.83 0.0 0.83 0.0 0.0 3
(0.214) (0.274)
(0.276) 1 4
Total 1499.9 0.0 0.0 1.01 4.06 0.0 4.06 0.0 0.0 j
(0.078) (0.274)
(0.276)
Y Q
1
- Numbers in parentheses indicate system outage time as a percentage of total plant operating time.
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TER-C5506-280 4.
CONCI,USIONS Wisconsin Public Service Corporation (WPSC) has submitted a report for the Iowaunee maclear Power Plant that contains (1) outage dates and duration of outages, (2) causes of the outages, (3) ECC systems or componwnts involved in the outages, and (4) corrective actions taken. It is concluded that WPSC has fulfilled the requirements of NUREG-0737, Item II.K.3.17.
In addition, the historical unavailability of the accumulators, SI, RER, and RNST systems has been consistent with the performance of those systems throughout the industry. 1he observed unavailability was less than the industrial mean for all BCC systems. The outage times were also consistent with existing technical specifications.
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REFERENCES 1.
" Generic Evaluation of Feedwater Transients and Small Break rass-of-Coolant Accidents in GE-Designed Operating Pl. ants and Near-Thra Operating License Applications" NRC, January 1980 2.
NUREG-0660 "NRC Action Plan Developed as a Result of the TMI-2 Accident" NRC, March 1980 3.
" Clarification of 'DtI Action Plan Requirements" NRC, October 1980 4.
E. R. Mathews (WPSC)
Letter to D. G. Eisenhet (Director, Diarision of Licensing, NRC)
Subject:
Submittal of Information Required by NUREG-0737 WPSC, January 5, 1981 5.
J. N. Donohew, Jr. (NRC)'
Letter to Dr. S. P.-Carf agno (FRC).
Subject:
Contract %.
NRC-03-81-13 0, Tentative Assignment F NRC, July 21, 1981 6.
NRC Meeting between NRC and FRC.
Subject:
C5506 Tentative Work Assignment F, Operating Reactor PORV and ECCS Outage Reports August 12, 1981 7.
NRC Meeting between NRC and FRC.
Subject:
Resolution of Review Criteria and Scope of Work July 26, 1982 8
WASE-1400
" Reactor Safety Study" NRC, October 1975 9.
" Nuclear Power Plant Operating Experience 1976" NRC, December 1977 10.
" Nuclear Power Plant Operating Experience 1977" NRC, February 1979 nidin Research Center A Dhamon of The Frwuen huanae
TER-C5506-280 11.
- mselear Power Plant Operating Experience 1978" NRC, December 1979 12.
NUREG/CR-1496 "Muclear Power Plant Operating Experience 1979" NBC, May 1981 13.
" Licensed Operating Reactors Status Susumary Report" Volume 4, Nos. 1 through 12, and volume 5, No. 1 NBC, December 1980 through January 1981 l
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