ML18047A611

ECCS Repts (F-47) TMI Action Plan Requirements,Palisades Plant, Technical Evaluation Rept

ML18047A611
Person / Time
Site:	Palisades
Issue date:	10/14/1982
From:	Vosbury F FRANKLIN INSTITUTE
To:	Chow E NRC
Shared Package
ML18047A612	List: ML18047A611
References
CON-NRC-03-81-130, CON-NRC-3-81-130, RTR-NUREG-0626, RTR-NUREG-0737, RTR-NUREG-626, RTR-NUREG-737, TASK-2.K.3.17, TASK-TM TER-C5506-287, NUDOCS 8210180071
Download: ML18047A611 (11)

Text

TER-C5506-287 CONTENTS Section Title Page r

l INTRODUCTION l 1.1 Purpose of Review * . l 1.2 Generic Background. l 1.3 Plant-Specific Background

• 2 2 REVIE'W CRITERIA. 3 3 TECHNICAL EVALUATION

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• • 3. l * *~eview *of- Compl1!teness

• 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 * .* 8 4 CONCLUSIONS. .. 9 5 REFERENCES

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~nklin Research Center A Division of The Franklin Institute

TER-C5506-287 FOREWORD 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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~nklin Research Center A Division of The Franklin Institute

TER-C5506-287

l. INTRODUCTION 1.1 PURPOSE OF REVIEW This technical evaluation report (TER) documents an independent review of the outages of the emergency core cooling (ECC) systems at Consumers Power company's (CPC) Palisades Plant. The purpose of this evaluation is to determine if the Licensee has submitted a report that is ~omplete and satisfies the requirements of TMI Action Item II.K.3.17, "Report on Outages of Emergency Core-Cooling Systems Licensee Report and Proposed Technical Specification Changes."

1.2 GENERIC BACKGROUND Following the Three Mile Island Unit 2 accident; the Bulletins and Orders

. *'**Task1*Force **reviewed--nuclecrr'-steam *supply-*"SYStem- (NSSS)

• ve*naors 1 smal'l break loss-of-coolant accident (LOCA) 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 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 substantial outages might occur within the limits of the present technical specification. 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 [l], " "Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in GE-Designed Operating Plants and Near-Term 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 (e.g., controller failure or spurious isolation). The outage data for ECC components should include all outages for the last five years of

~nklin Research Center A Division of The Frenldin institute

TER-C5506-287

3. TECHNICAL EVALUATION 3.1 REVIEW OF COMPLETENESS OF THE LICENSEE'S REPORT

.- ; The ECC systems at CPC' s Palisades Plant consist of the following four separate systems:

o safety injection (SI) tank o high pressure safety injection (HPSI) o low pressure safety injection (LPSI) o refueling water storage tank (RWST).

In Reference 4, CPC also included systems and components that support the

_ _,,ECC ::Systems .dn~car..ry.ing..:eu.t :.-.the;ir ;:-.desi9n:.£uncti0l1S.:~under. :various,_ accident conditions. The support systems are:

o design basis accident (OBA) sequencer o standby diesel generators o containment sump o engineered safeguards.

For each ECC system outage event, CPC provided the outage dates, the duration, and the cause, plus sufficient description to discern the corrective action taken. Maintenance and surveillance testing activities were included in the ECC system outage data. The results of CPC's review were provided for the period from January l, 1976 to December 31, 1980 for the Palisades plant.

Based on the preceding discussion, it has been established that CPC has submitted a report which fulfills the requirements of review criterion l without exception.

3.2 COMPARISON OF ECC SYSTEM OUTAGES WITH THOSE OF OTHER PLANTS The outages of ECC systems can be categorized as (l) unplanned outages due to equipment failure or (2) planned outages due to surveillance testing or preventive maintenance. Unplanned-outages are reportable as Licensee Event

~nklin Research Center A Division of The Franklin Institute

TER-C5506-287 unavailability is a function of planned and unplanned outages of essential support systems as well as planned and unplanned outages of primary ECC system components. In 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 under-estimate the unavailability 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 (SI tank, HPSI, LPSI, and RWST) and for the standby diesel generators were

- :;';.:identi£ie.d .:.:from ::the .:oci-tage *.:infozmaticn-.in ...-Be:fer.enc.e ,4. :and.. are .::shown .i-n. '.llUIDber of days and as percentage of plant operating time per year in Table l for the Palisades plant. Outages that occurred during nonoperational periods were eliminated as were those caused by failures or test and maintenance of support systems.

Data on plant operating conditions were obtained from the annual reports, nNuclear Power Plant OperatingExperiencen (9-12], and from monthly reports, nLicensed Operating Reactors Status Summary Reportsn (13]. The remaining outages were segregated into planned and unplanned outages based on CPC'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 the Palisades plant were compared with those of other PWRs. Based on this comparison, it was concluded that the historical unavailability of the SI tank, RWST, LPSI, and HPSI systems has been consistent with the performance of those systems throughout the industry. The unavailability was less than the industrial mean for the SI tank, RWST, and LPSI system and less than about one standard deviation above the industrial mean for the HPSI system, assuming that the underlying unavailability is distributed lognormally. The outage times were also consistent with existing technical specifications. The outages of the standby diesel generators were not included in this comparison.

~nklin Research Center A Division of The Franklin Institute

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Table 1. Planned and unplanned (ibrced) Outage Times for Palisades Plant*

SI Tank HPSI LPSI: RWST Diesel Generator Days of Plant Ou ta9e in Da:l(:B Outa9e in Da:l(:S 0uta2e in Da:l(:s Outa9e in Da:l(:S 0Uta9e in Dal:'.s

~ Operation Forced Plannec;l Forced Planned Forced Planned Forced Planned ibrced Planned 1976 202.04 o.o . o.o o.o 0.67 1.12 ,0.61 o.o o.o 2.38 5.36 (0 .33') (0.55\) (0.30\) (l.18\) (2.65\)

.....I 1977 333.67 0.06 o.o 7.15 2.22 o.o 0.08 o.o o.o 5.61 7.49 I (0.02\) (2.14\) (0 .67) 0.02' (l.68\) (2.24')

1978 181.18 .o.o o.o o.o 1.11 o.o 0.23 o.o o.o 3.13 4.84 (0.61') io.13\) (l.73%) 2.67' 1979 218.54 0.20 0.09 o.o 1.55 o.o 0.16 o.o o.o 3.46 13.11 (0~09\) (0.04\) (0. 71%) fo.07%) (1.58%) (6.00\)

1980 201.13 o.o . o.o o.o 0.08 o.o 0.28 o.o o.o 10.21 4.54 (0.04') (0.14%) (5.08%) (2.26%)

T<>tal 1136.56 0.26 0.09 7.15 5.63 1.12 ;1.36 o.o o.o 24.79 35.34 (0.02\) (0 .ou) (0.63%) (0.50%) (0.10\) fo.11%) 2.18% (3.11%)

• NUmbers in parentheses indicate system outage time as a percentage of total plant operating time.

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TER-C5506-287 3.3 REVIEW OF PROPOSED CHANGES TO IMPROVE THE AVAILABILITY OF ECC EQUIPMENT In Reference 4, CPC did not propose any changes to improve the availa-bility of ECC systems and components.

~nklin Research Center A Division of The Franklln Institute

TER-C5506-287

4. CONCLUSIONS Consumers Power Company (CPC) has submitted a report for the Palisades plant that contains (1) outage dates and durations, (2) causes of the outages, (3) emergency core cooling (ECC) systems or components involved in the outages, and (4) corrective actions taken. It is concluded that CPC has fulfilled the requirements of NUREG-0737, Item II.K.3.17. In addition, the historical unavailability of the SI tank, RWST, LPSI, and HPSI systems has been consistent with the performance of those systems throughout the industry. The observed unavailability was less than the industrial mean for the SI tank, RWST, and LPSI system and less than about one standard deviation above the industrial mean for the HPSI system. The outage times were also consistent with existing technical specifications.

~nklin Research Center A Division of The Franklin Institute

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TER-C5506-287

5. REFERENCES

l. NUREG-0626 "Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in GE-Designed Operating Plants and Near-Term 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. NUREG-0737 "Clarification of TMI Action Plan Requirements" NRC, October 1980

....:~.;,.

,.4. .:D. "P. 'Hoffman (CPC)

Letter to D. M. Crutchfield (Operating Reactors Branch ts, NRC)

Subject:

Submittal of Information Required by NUREG-0737 December 19, 1980 S. J. N. Donohew, Jr. (NRC)

Letter to Dr. s. P. Carfagno (FRC).

Subject:

Contract No.

NRC-03-81-130, Tentative Assignment F 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 WASH-1400 "Reactor Safety Study" NRC, October 1975

9. NUREG-0366

• . :1 "Nuclear Power Plant Operating Experience 1976" NRC, December 1977

10. NUREG-0483 "Nuclear Power Plant Operating Experience 1977" NRC, February 1979

~nklin Research Center A Division of The Franklin Institute

• TER-C5506-287

11. NUREG-0 618 "Nuclear Power Plant Operating Experience 1978" NRC, December 1979

12. NUREG/CR-1496 "Nuclear Power Plant Operating Experience 1979" NRC I May 19 81

13. NUREG-002 0 "Licensed Operating Reactors Status Sununary Report" Volume 4, Nos. 1 through 12, and Volume S, No. 1 NRC, December 1980 through January 1981

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~nklin Research Center A Division of The Franklin Institute