ML20235F016

Summary of 870610 Meeting W/Util in Bethesda,Md Re Reliability of Plant Emergency Feedwater Sys.List of Meeting Attendees Encl

ML20235F016
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/01/1987
From:	Richard Lee Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8707130173
Download: ML20235F016 (12)

Text

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aj WASHINGTON, D. C. 20555 g July 1, 1987 Docket No. 50-368 LICENSEE: Arkansas Power and Light Company (AP&L)

FACILITY: Arkansas Nuclear One, Unit 2 (ANO-2)

SUMMARY

OF JUNE 10, 1987 MEETING WITH AP&L AND NRC STAFF REGARDING THE RELIABILITY OF THE ANO-2 EMERGENCY FEEDWATER SYSTEM (EFWS) -

INTRODUCTION At the request of the NRC staff, a meeting was hel:1 on June 10, 1987 at the NRC office in Bethesda, Maryland, on the above subject. The purpose of the meeting was to discuss a potential backfit action resulting from the assessment of the ANO-2 EFWS overall reliability by the NRC staff. The NRC staff reviewed the design, maintenance, surveillance and testing procedures, operating procedures, personnel training, system layout, instrumentation and control, environment, and accessibility of operation recovery actions following any potential malfunctions, associated with the ANO-2 EFWS to assess its over-all reliability. Based on the review, the NRC staff came up with a number of preliminary findings which were discussed with the licensee at the conclusion of the site visit by the NRC staff in December 1986. The potential backfit action which involves an additional source of feedwater to steam generators was not discussed with the licensee at that time. A list of meeting attendees is enclosed. A summary of the meeting follows.

SUMMARY

The NRC staff noted that the staff's preliminary evaluation indicates that an additional source of feedwater ta steam generators is needed to achieve a high reliability for the ANO-2 EFWS. The licensee commented that it believes the I current ANO-2 EFWS is sufficiently reliable as a result of various reliablity related modifications and meets the all applicable regulatory requirements. l The licensee also commented that it had undertaken various steps to reduce challenges to the EFWS by reducing the frequency of reactor scrams and improv-ing the reliability of the main feedwater system. In addition, the licensee  ;

noted that condensate pumps can be used to feed steam generators in place of  !

the EFWS and AN0-2 has a feed and bleed capability utilizing a 6 inch ECCS l l

vent.

The NRC staff indicated that the licensee's comments would be considered in the preparation of the assessment report related to the AN0-2 EFWS. The staff, however, noted that it is difficult to show a high reliability with a two pump EFWS.

l 8707130173 870701 PDR ADOCK 05000369 P PDR

V g.

FUTURE WORK The NRC t;taff will prepare the assessment report for issuance. The licensee and the NRC staff will discuss to exchange information on the feasibility and/or potential alternatives to the potential backfit action in the latter part of July 1987.

l l

15, Rober# S. Lee, Project Manager Project Directorate IV  !

Division of Reactor Projects III, IV, V and Special Projects Enclosure As stated cc w/ enclosure:

See-next page DIST1(IBUTION

@ cket File NRC PDR Local PDR P. Norian T. Enos PD4 Reading S. Diab S. Quinnoz J. Partlow D. Crutchfield H. Silver F. Schroeder J. C lvo R. Giardina I R. Lee P. Noonan G. Dick OGC-Beth E. Jordan D. James ACRS (10)

W. Minners ,

D. Howard i o a o 07/ / /87 07// /87 07/}/87 0

1 l

l I

[ .' .,

Mr. T. Gene Campbell Arkansas Nuclear One Arkansas Power & Light' Company Unit No. 2 cc:

Mr. J. Ted Enos, Manager Mr. Charlie B. Brinkman, Manager Nuclear Engineering and Licensing Washington Nuclear Operations Arkansas Power and Light Company C-E Power Systems P. O. Box 551 7910 Woodmont Avenue Little Rock, Arkansas 72203 Suite 1310 Bethesda, Maryland 20814 Mr. James M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Nicholas S. Reynolds, Esq.

Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, H.W.

Suite 700 ,

Washington, D.C. 20036 Regiorici Administrator, Region IV U.S. Nuclear Regulatory Connission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Environmental Health Protection Arkansas Department of Health 4815 West Markam Street Little Rock, Arkansas 72201 L

Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220 3- 7910 Woodmont' Avenue Bethesda, Maryland 20814

4 Enclosure

>= ANO-2 EFWS MEETING ATTENDANCE LIST Name Affiliation R. Lee NRR/PD4 W. Minners RES/DRPS P. Norian RES/RPSIB J. Calvo NRR/PD4 S. Diab NRR/SRXB H. Silver NRR/PD22 R. Giardina NRR/0TSB G. Dick NRR/PD4 D. James AP&L D. Howard AP&L T. Enos AP&L S. Quinnoz AP&L

k [N'

/ 'o

1. ,,c UNITED STAT ES

!" NUCLEAR REGULATORY COMMISSION 1

W ASHNGTON, D. C. 2n555 f  ; ~;

July 1, 1987

• ...+

j Docket No. 50-368 LICENSEE: Arkansas Power and Light Company (AP&L)

FACILITY: Arkansas Nuclear One, Unit 2 (ANO-2)

SUMMARY

OF JUNE 10, 1987 MEETING WITH AP&L AND NRC STAFF REGARDING THE RELI ABILITY OF THE AND-2 EMERGENCY FEEDWATER SYSTEM (EFWS)

INTRODUCTION At the request of the NRC staff, a meeting was held on June 10, 1987 at the NRC office in Bethesda, Maryland, on the above subject. The purpose of the meeting was to discuss a potential backfit action resulting from the assessment of the ANO-2 EFWS overall reliability by the NRC staff. The NRC staff reviewed the design, maintenance, surveillance and testing procedures, operating procedures, personnel training, system layout, instrumentation and .

control, environment, and accessibility of operation recovery actions following' any potential malfunctions, associated with the AN0-2 EFWS to assess its over-all reliability. Based on the review, the NRC staff came up with a number of preliminary findings which were discussed with the licensee at the conclusion of the site visit by the NRC staff in December 1986. The potential backfit action which involves an additional source of feedwater to steam generators was not discussed with the licensee at that time. A list of meeting attendees is enclosed.. A summary of the meeting follows.

SUMMARY

The NRC staff noted that the staff's preliminary evaluation indicates that an additional source of feedwater to steam generators is needed to achieve a high reliability for the ANO-2 EFWS. The licensee cc.mmented that it believes the current ANO-2 EFWS is sufficiently reliable as a result of various reliablity related modifications and meets the all applicable regulatory requirements.

The licensee also commented that it had undertaken various steps to reduce challenges to the EFWS by reducing the frequency of reactor scrams and improv-ing the reliability of the main feedwater system. In addition, the licensee ,

noted that condensate pumps can be used to feed steam generators in place of l the EFWS and AND-2 has a feed and bleed capability utilizing a 6 inch ECCS vent.

The NRC staff indicated that the licensee's comments would be considered in the preparation of the assessment report related to the ANO-2 EFWS. The staff, however, noted that it is difficult to show a high reliability with a two pump EFWS.

1

. . . . . . I

1

FUTURE WORK The NRC staff will prepare the assessment report for issuance. The licensee and the NRC staff will discuss to exchange information on the feasibility .

and/or potential alternatives to the potential backfit action in the latter part of July 1987.

IS Robert S. Lee, Project Manager Project Directorate IV Division of Reactor Projects III, IV, V and Special Projects Enclosure As stated cc w/ enclosure:

See next page DISTRIBUTION DojcetFile WRC PDR Local PDR P. Norian T. Er.os PD4 Reading

5. Diab S. Quinnoz J. Partlow D. Crutchfield H. Silver F. Schroeder J. Calvo R. Giardina R. Lee P. Noonan G. Dick OGC-Beth E. Jordan D. James ACRS (10)

W. Minners D. Howarc PD-4 e -4 PNoo l JCalvo 07///87 07/I /87 07/c )/87

I 1 Mr. T. Gene Campbell Arkansas Nuclear One Arkansas Power & Light Company Unit No. 2 CC*

Mr. J. Ted Enos, Manager Mr. Charlie B. Brinkman, Manager Nuclear Engineering and Licensing Washington Nuclear Operations Arkansas Power and Light Company C-E Power Systems P. O. Box 551 7910 Woodmont Avenue Little Rock, Arkansas 72203 Suite 1310 Bethesda, Maryland 20814 Mr. James M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. C. Box 608 Russellville, Arkansas 72801 Nicholas S. Reynolds, Esq.

Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.

Suite 700 Washington, D.C. 20036 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan, Plaza Drive, Suite 1000

. Arlington, Texas 76011 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Environmental Health Protection Arkansas Department of Health 4815 West Markam Street Little Rock, Arkansas 72201 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220 7910 Woodmont Avenue _

Bethesda, Maryland 20814

e s

Enclosure

\

ANO-2 EFWS MEETING ATTENDANCE LIST Name Affiliation R. Lee NRR/PD4 W. Minners RES/DRPS P. Norian RES/RPSIB J. Calvo NRR/PD4 S. Diab NRR/SRXB H. Silver NRR/PD22 R. Giardina NRR/0TSB ,

i i

G. Dick NRR/PD4 D. James AP&L D. Howard AP&L T. Enos AP&L

5. Quinnoz AP&L

J a

+ pcp Mcg'S UNITED STATES

'i, ! r,

~h NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 r,,

~l July 1, 1987 g

=..o Docket No. 50-368 LICENSEE: Arkansas Power and Light Company (AP&L)

FACILITY: Arkansas Nuclear One, Unit 2 (ANO-2)

SUMMARY

OF JUNE 10, 1987 MEETING WITH AP&L AND NRC STAFF REGARDING THE RELIABILITY OF THE AND-2 EMERGENCY FEEDWATER SYSTEM (EFWS)

INTRODUCTION At the request of the NRC staff, a meeting was held on June 10, 1987 at the NRC office in Bethesda, Maryland, on the above subject. The purpose of the meeting was to discuss a potential backfit action resulting from the assessment of the ANO-2 EFWS overall reliability by the NRC staff. The NRC staff reviewed the design, maintenance, surveillance and testing procedures, operating procedures, personnel training, system layout, instrumentation and control, environment, and accessibility of operation recovery actions following any potential malfunctions, associated with the ANO-2 EFWS t'o assess its over-all reliability. Based on the review, the NRC staff came up with a number of preliminary finding:5 which were discussed with the licensee at the conclusion of the site visit by the NRC staff in December 1986. The potential backfit action which involves an additional source of feedwater to steam generators was not discussed with the licensee at that time. A list of meeting attendees is enclosed. A summary of the meeting f9llows.

SUMMARY

The NRC staff noted that the staff's preliminary evaluation indicat.es that an additional source of feedwater to steam generators is needed to achieve a high reliability for the ANO-2 EFWS. The licensee connented that it believes the current ANO-2 EFWS is suf fic$ently reliaMe as a result of various reliablity related modificat. ions and meets the all applicable regulatory requirements.

The licensee also commented that it had undertaken various steps to reduce challenges to the EFWS by reducing the frequency of reactor scrams and improv-ing the reliability of the main feedwater system. In addition, the licensee noted that condensatt pumps can be used to feed steam generators in piece of the EFWS and ANO-2 has a feed and bleed capability utilizing a 6 inch ECC5 vent.

The NRC staff indicated that the licensee's conarents would be considered in the preparation of the assessment report related to the ANO-2 EFWS. The staff, however, ncted that it is difficult to show a high reliability with a two pump

'EFWS.

{

q.. 2 FUTURE WORK The NRC staff will prepare the assessment report for issuance. The licensee and the NRC staff will discuss to exchange information on the feasibili',y and/or potential alternatives to the potential backfit action in the latter part of July 1987.

15 Robert 5. Lee, Project Manager Project Directorate IV Division of Reactor Projects III, IV, V and Special Projects Enclosure As stated cc w/ enclosure:

See next page DISTRIBUTION Ifocket File NRC PDR

@ (al PDR P. Norian T. Enos PD4 Reading

5. Diad S. Quinnoz J. Partlow D. Crutchfield H. Silver F. Schroeder J. Calvo R. Giardina R. Lee P. Noonan G. Dick OGC-Beth E. Jordan D. James ACRS (10)

W. Minners D. Howard '

nw ;M 07/ / /87 07// /87 ho 07/g}/87

( Mr. T. Gene Campbell Arkansas Nuclear One Arkansas Power & Light Company Unit No. 2 cc:

Mr. J. Ted Enos, Manager Mr. Charlie B. Brinkman, Manager Nuclear Engineering and Licensing Washington Nuclear Operations Arkansas Power and Light Company C-E Power Systems P. O. Box 551 7910 Woodmont Avenue Little Ror.k, Arkansas 72203 Suite 1310  !

Bethesda, Maryland 20814  !

Mr. James M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Nicholas 5. Reynolds, Esq.

Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.

Suite 700 Washington, D.C. 20036 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Environmental Health Protection Arkansas Department of Health 4815 West Markam Street Little Rock, Arkansas 72201 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220 7910 Woodmont Avenue Bethesda, Maryland 20814

'Y Enclosure ANO-2 EFWS MEETING ATTENDANCE LIST Name Affiliation R. Lee NRR/PD4 W. Minners RES/DRPS P. Norian RES/RPSIB J. Calvo NRR/PD4 S. Diab NRR/SRXB H. Silver NRR/PD22 R. Giardina NRR/0TSB G. Dick NRR/PD4 D. James AP&L D. Howard AP&L T. Enos AP&L AP&L S. Quinnoz