ML20077K022

ECCS Repts (F-47) TMI Action Plan Reqirements,Pse&G,Salem Nuclear Generating Station Unit 1, Technical Evaluation Rept

ML20077K022
Person / Time
Site:	Salem
Issue date:	09/28/1982
From:	Luddington B, Ludington B, Overbeck G, Vosbury F FRANKLIN INSTITUTE
To:	Chow E NRC
Shared Package
ML18089A395	List: ML20077K022
References
CON-NRC-03-80-130, CON-NRC-3-80-130, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.17, TASK-TM TER-C5506-294, NUDOCS 8210010087
Download: ML20077K022 (14)

Text

.. . . .. ..

$ID33fW5MiNE[MSEWMj@5TMs@DFM6?F@ lM4%

k

'. m e MT frC. S '

"% TECHNICAL

+

b. hbh EVALUATION he REPORT hb ~ .g a b

4 V-

. ; un.; 1 ;w - ~ _

~. , .u w.

.g NECCSyREPORT w m ae F-47)s mx D 9N w Nw m _ ~a 1 i i M13 CTI'ON$w,naL. A..N : EQUIREMENTS' <

EL%s:mtd

' i f

~D'~ AS

, b J

~.fSi.j,I+C$$EE. .' ~ E C..O M P.-..

' , . , ~

f0N20NI

,"  ! 6A mNUCE m.,E,AR ' GENE ING

. _ . . . . .. n. ~ 1 m.m % . .

• .w w .  % 2 % ,m. _

!L 9^ b e -h 6 *

$9+'

NRCDOCKETNO, 5"0:272J; , FRC PROJECT CS606.h -- R "},

' u %,[J:f. & jf1 ' 3 6Ng i' h%': .. CQf:)y*tiMQq:yyQ.. ; , . .

+- 'q RCASSIGNMENTT ".-. sy 'g

• 1 Mdy d'fj NL

'N[NdMNc.. 9 .

SkT

?)f,1 )., 2 e.:4m. Il (d')[fg EM@

gg qp  %  ; '. ,' 1 ,A NR,C-03-81,130,

. NRC3NTRgNO. .

a }.j.,g w~ <QPg,gfRCTASK, J94 gggy,{

• W Sj

. ,, .h?.g@p';ty

.t

n 'v y

m - .

. h'f

/d W __ . _ _

g %v.g. g m  :

gy ,

....?:?.

%i

'^

for ~'~ _. ._

i!'a

, ,~ N mism'on44GE RC .gmeer:.- <

~-'

$l ,

"Ilir7.1I[ '365$6c l l

i _ _ _ _ w E .

e mt! l l

, L-n 4' . k -

-W

" -- -w E K-. +__~_ ,

W k..;f,Q$hW '

i g

yE.lji:7s"i4 . . . . .

. ..: NMT.W sponsofed by an agency! ...the . . . ited Un. States *

+-

. ,,. eport,was prepa . as:an account of w ..

enti.Neither.the U'ntted1 States Governmentfor any, agency thereof'ogariY,of thel (x i s2mskosiaE.jstrao f xpressed'6rfimplied,xor,asaurneWanyNegalillabMty.'dr'

' s usefo'r th'elGuits'of;such{use,3fa6yjnformatfon,'apps *

(b....,I,<

y.,

g~' gpwkwould

'e' @ponalbnityIfoEMf thlr' ' party @'ied(Ifthlai'rspd s

.t_Q pn7ducfod@d.' s'disi:lo e d

y Y.

nottnfring privately owned rights..- >(V# ';w'pr~ represents

{T.g g

(

.p.9fQ -

~

-Q.

g9% j __ -

.y j

-l l I r a

^

?

e t -" =wwy }

T M_ .E 4

@e . M Ab9 m,Lpj pl

~ p Mf gyyk ;ygh

^ %g w.gm.

S 2

g+%p?GhTMik&g,veEh%$,5 fb +} .m c%g Tme4 M <

3'ranifl'iniResearch;tenterkM disisiossfM.yransinTnstiliits.W i

.N . '

. . . m , s : . .-

.-4 .. . senprun rr.,esn p ,w.y, pse; p.' igi03 g21S) 4481000 " t-v .- -

c.. h -

~'

• n .... ...

L, G

Mip mhyEy;,%9,r+:wmsga' M srP w ,frir6,25 he w!..  %,inr w~ .

^.

TECNNICAL EVALUATION REPORT ECCS REPORTS (F-47)

TMI ACTION PLAN REQUIREMENTS PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION UNIT 1 1

NRC DOCKET NO. 50-272 FRO PROJECT C5506 FRC ASSIGP. MENT 7 n.

NRC CONTRACT NO. NRC-03-81 130 FRC TASK 294

# D 7. L Vosbury Franklin Research Center Author: G. J. Overbeck B. W. Ludington 20th and Race Streets Philadelphia, PA 19103 FRC Group Leader: G. J. Overbeck Prepared for Nuclear Regulatory Commission Lead NRC Engineer: E. Chok Washington, D.C. 20555 ,

September 28, 1982 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 employees, makes any warranty, expressed or impi;ed, or assumes any legal liability or responsibility for any third party's use, or the results of such naa. of any information, appa-ratus, prod' Jct or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.

Pre Reviewed by: Approved by:

red b7:

4% w Principal Aut'hof A~,40R Group L'eader AALD Depa'rfment Dire or []

Date- bNI Date- E' #U Date: O%*M l

al

. 00. Franklin Research Center A Division of The Franklin Institute l The Benjamin Frankan Parkway, Phala Pa. 19103(215)448 1000 l

f 3 TER-C5506-294 CONTENTS Section Title Page 1 INTRODUCTION . . . . . . .- . . . . . . 1 1.1 Purpose of Review . . . . . . . . . . . 1 1.2 Generic Background. . . . . . . . . . . 1 1.3 Plant-Specific Background . . . . . . . . . 2 2 REVI1!N CRITERIA. ,

. . . . . . . . . . . . 3 3 TECHNICAL EVALUATION . . . . . . . . . . . 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 COICLUSIONS. . . . . . . . . . . . . . 8 ,

5 REFERENCES . . . . . . . . . .. . . . . 9 i

e l

nklin Research Center A Dheeson d The Fransen ansamme

TER-C5506-294 FOREWORD

! This Technical Evaluation Report was prepared by Franklin Rasearch Center under a contra $t with the U.S. Iniclear Regulatory'Comunission (Office of Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance in support of NBC operating reactor licensing actions. The technical evaluation was conducted in accordance with criteria established by the NRC.

Mr. G. J. Overbeck, Nr. F. W. Vosbury, and Mr. B. W. Ludington contributed to the technical preparation of this report through a subcontract with WESTEC Services, Inc.

C

• l l

e V

nklin Research Center A Dhesson of The FransenInsumme

i

{ ..

TEP-C5506-294 1

1. INTRODUCTION 1.1 PURPOSE OF REVIEN 1 This technical evaluation report (TER) documents an independent review of the outages of the emergency core cooling (BCC) systems at PubilJ Service Electric and Gas Company's (PSE&G) Salen Nuclear l'enerating Station Unit 1.

The purpose of this evaluation is to determine if the Licensee has submitted a report that is complete 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 BACKGROUE Pollowing the Three Mile Island Unit 2 accident, the Bulletins and Orders Task Force 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 IOCA emergency procedures.

During these reviews,' a concern developed about the assumption of the worst a

single failure. Typically, the small break ICCA analysis for boiling water reactors (BNRs) 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 [1], " Generic Evaluation of Feedwater Transients and Small Break Ioss-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:

_nklin Resea_rch._

_ . Center

~ _ .

TER-C5506-294

" 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 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 recommendation was incorporated into NUREG-0660 (2], "NBC Action Plan Developed as a Result of the TMI-2 Accident," for GE-designed NSSSs 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 light water reactor pla'nts and added a requirement that licensees propose changes that will improve and control availability of ECC systems and t:ceponents. ; 2n addition. the.wa=+= Jaf -the Isports to be subnitted by the licensees were further clarified as follows:

"The report should contain (1) outage dates and duration of outages; (2) cause of the outager (3) ECC systems'or components involved in the outage; and (4) corrective action taken."

1.3 PLANT-SPECIFIC BACKGROUND On December 31, 1980 (4), PSE&G submitted a report in response to NUREG-0737, Item II.K.3.17, " Report on Outages of Emergency Core-Cooling Systems Licensee Report and Proposed Technical Specification Changes." The report submitted by PSEEG covered the period from December 1, 1976 to December 31, 1980 for the Sales plant. PSE&G did not propose any changes to improve and control the availability of ECC systems.

4 4

dbranidin Research Center A DMean of The Frenten insumme

. _ _ _ .._ _. _ , . _ _ _ _ _ __..____.._.,_....____.,.__,,..._,_,,,__.m., _ . , _ _ . . . . _ . . - - . _ . . , _ .

s TER-C5506-29 4

, 2. REVIEW CRITERIA The Licensee's response to NUREG-0737, Item II.K.3.17, was evaluated against criteria provided by the NRC in a letter dated July 21, 1981 [5]

outlining Tentative Work Assigwnt F. Provided as review criteria in Reference 5, the NBC stated that the Licensee's response should contain the following information:

l. 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 systems or components involved and ccerective actions, taken. Test and maintenance outages were to be included. .

2. A quantification of the historical unavailability of the ECC systed.s and-components due to-test and 1 maintenance outages.

3. Proposed changes to improve the availability of ECC systems, if necessary.

De type of information required-to satisfy the review criteria was clarified by the NRC on August 12, 1981 [6]. Auxiliary systems such as component cooling water and plant service water systems were not to be e j 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.

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 outages than other licensees with similar NSSSs. He need for improved reliability of diesel generators is under review by the NBC. A Diesel Generator Interim Reliability Program has been proposed to effect improved performance at opera' ting plants. As a consequence, a comparison of diesel generator outage information within this review is not required.

1 00hu Franklin Research Center A Common of The Fransen insmede l

TER-C5506-294 s

3. TECHNICAL EVALUATION 3.1 REVIEW OF COMPLETENESS OF THE LICENSER'S REPORT The ECC systems at Salen Unit 1 consist of the following five separate systems:

o accumulators -

o safety injection system (SIS) o chemical and volume control system (CVCS) o residual heat removal (RBR) o refueling water st'orage tank (RNST).

For each ECC system outage event, PSEEG provided the outage dates, the duration, and the cause, plus sufficient description to discern the corrective action taken. Naintenance and surveillance testing activities were included in the ECC system outage data. The gesults of PSE&G's review were provided for the period from December 1, 1976 bo December 31, 1980 for Salen Nuclear Generating Station Unit 1.

On the basis of the preceding discussion, PSE&G's report fulfills the requirements of review criterion 1 without exception.

3.2 COMPARISON OF ECC SYSTEM OUTAGES WITH THOSE OF OTHER PLANTS 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. The technical specifications ident'ify the type and quantity of ECC equipment required as well as the maximum allowable outage times. 'If an outage exceeds the maximum 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 000 Frenidin Research Center A Ohemen of The Frenten truseme

l l

l l

TER-C5506-294 prevent extended plant operation without sufficient ECC system protection.

The maximus 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 outages from accumulating

' extensive ECC system downtime.

Unavailability, as defined in general terms in WASH-1400 (8], is the probability of.a system being in a failed state when required. However, for this review [ a detailed unavailability analysis was not required. Instead, a preliminary estimate $f the unavailability of an ECC system was made by

~

calculating the ratio of the ECC system downtime to the number of days that the plant was in operation, during the last 5 years. 'Ib simplify the tabula-tion of operating time, only the period when the plant was in operational Mode 1 was considered. This simplifying assumption is reasonable 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 syistem component was unavailable due to any cause.

It should be noted that the ratio calculated in this manner is not a true e 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. Fbr 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 satiafy core cooling requirements, then an outage of a single pump would not prevent the system from performing 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 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 i

' nklin Research Center A Chamon of The Frereen Insensee

__. _ . . _ . , _ . . _ _ . . _ . _ _ . _ _ _ . _ _ _ _ . _ _ . . _ _ _ _ . _ ~ . _ _ . - .

U i * -

3. TER-C5506-294 s

inclusion of all outage events assumed to be true ECC system outages tends to overestimate tha' uhava11 ability, while{the exclusion of support system outages tends to uncerestimate .the unairailability of ECC systems and cozaponents. 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 pla5 reed and unplannel (forced) outage times for the five ECC systems (accumulators, SIS, CVCS, RER, and 15fST) were identified from the outage information in Refeatence 4 and are shown in number of days and as percentage of plant operating time per year in Table 1 for Salem Unit 1. Outages that occurred during nonoporatisnal periods were eliminated, as were as those caused by failures 'or test and maintenance of support systems. Data on plant operating conditions were obtaihed from the annual reports, *1taclear Power Plant Operating Experience" (9-12], and from monthly reports, " Licensed Operating Reactors Status Summary Report" (13]. We remaining outages were segregated into planned and unplanned outages based on PSE&G's description of the causes. The outage-periods for each category were calculated by summing .

the individual outage durations, e Observed outage times of various ECCs system at Salen Nuclear Generating Station Uhit l' were compared with those of other PWRs. Based on this comparison, it was concluded that the historical unavailiability of the accumulators, SIS, letST, CVCS, and RHR systems has been consistent with the performance of those systems throughout the industry. The observed unavailability was less than the industrial mean for the accumulators, SIS, RWST, and RER systems and less than about one standard deviation above the industrial mean for CVCS, assuming that the underlying unavailability is distributed lognormally. The outage times were also consistent with existing technical specificat' ions.

3.3 REVIEW OF PROPOSED CHANGES TO IMPROVE THE AVAILABILITY OF ECC EQUIPMENT In Reference 4, PSE&G did not propose any changes to improve the availability of ECC systems and components.

nMn Research Center

' A Dhemen of La Feenseninssewee

--,g.p,,

p d-----g ---fg.7 , r w ,- 3 gen mn,im---mWg%-wgyem ---*=*w-w-- "-'-e*'*"-*"'"'--

o_

i b Table 1. Planned and Unplanned (Forced) Outage Times for Salem Unit 1*

• vi j

h g'h Accumulators SIS CVCS RHR InfST ym Days of Plant Outage in Days Outage in Days Outage in Days Outage in Daya Outage in Days

'k Year Operation Forced Planned Forced Planned Forced Planned Forced Planned Forced Planned

' 1977 Commercial 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.0 0.0 0.0

6/30/77 E 99.2 i

s 1978 203.0 0.0 0.0 0' .1 0.2 0.0 0.1 0.0- 0.0 0.0 0.0 1 (0.1%) (0.1%) (0.1%) -e -

1979

^*4 93.0 0.0 0.0 0.6 (0.6%)

0.3 0.0 0.7 (0.7%)

0.0 0.6 - 0.0 3 0.0 (0.3%)

1980 264.2 0.0 0.0 0.8 0.3 5.1 1.2 2.9 0.0 0.0 0.0

} (0.3%) (0.1%) (1.9%) (0.5%) (1.1%) ,

J 1

, Total 659.4 0.0 0.0 1.5 0.8 5.1 2.0 2.9 0.0 0.0 0.0 (0.2%) (0.1%) (0.8%) (0.3%) (0.4%)

• Numbers in parentheses indicate system outage t.ime as a percentage of total plant operating time.

4

=

2 A

3 TER-C5506-294

4. CONCLUSIONS Public Service Electric and Gas Company (PSr%G) has submitted a report for Salen Nuclear Generating Station Unit 1 that contains (1) outage dates and duration of outages, (2) causes of the outages, (3) ECC systems or components involved in the outages, and (4) corrective actions taken. It is concluded that PSE&G has fulfilled the requirements of NUREG-0737, Item II.K.3.17. In addition, the historical unavailability of the accumulators, SIS, RNST, CVCS, and RHR systems has been consistent with the performance of those systems throughout the industry. W e observed unavailability was less than the industrial mean for the accumulators, SIS RNST, and ret systems and less than about one standard deviation above the industrial mean for the CVCS. Se

" outage times were also 1:ensistent with existing technical specifications.

O e

l l

i l

00h Franklin Research Center a c>= a .e Th. rr.n.en m

' TER-C5506-294

. 5. REFERENCES

l. NUREG-0626

" Genesic Evaluation of Feedwater Transients and Small Break

- Ioss-of-Coolant Accidents in GE-Designed Operating Plants and

. Near-1%rm Operating License Applications" NBC, 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. R. L. Mittel (PSE&G)

%tter to 3.'s 'varga 1 Director of Nuclear Beactor Regulation, NBC)

Subject:

Submittal of Information Required by NUREG-0737 December 31, 1980

5. J. N. Donohew, Jr. (NBC) -

Letter to Dr. S. P. Carf agno (FRC) . Subject Contract No.

NRC-03-81-13 0, Tentative Assignment F NBC, July 21, 1981 e

6. NRC Neeting between NRC and FRC.

Subject:

C5506 Tentative Work Assignment F, Operating Reac*.or PORV and BCCS Outage Reports August 12, 1981

7. NRC Neeting between NBC and FIC.

Subject:

Resolution of Review Criteria and Scope of Work July 26, 1982 8 WASE-1400

" Reactor Safety Study" NRC, October 1975

9. NUREG-036'6 "Maclear Power Plant Operating Experience 1976"

, NRC, December 1977

10. NUREG-0483

• "Maclear Power Plant Operating Experience 1977" NBC, February 1979 Ubb rankDn Research Center A % em w rrenma m

• TER-C5506-294

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

12. NUREG/CR-1496 "mclear Power Plant Operating Experience 1979" NRC, May 1981 13.

NUREG-0020

" Licensed Operating Deactors Status Summary Report" Volume 4, Ms.1 through 12, and Volume 5, No.1 NBC, December 1980 through January 1981 S

9 t

c nklin Research Center A Dhamen of The Fransen insmewee

- - - - - , - -, , , - . , . . . ,__. ---. . _ , , . _, _ , , _ , , _ . _ , , , _ _ _ _ _