ML20059C756
| ML20059C756 | |
| Person / Time | |
|---|---|
| Issue date: | 04/29/1993 |
| From: | Shewmon P Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| REF-GTECI-120, REF-GTECI-NI, TASK-120, TASK-OR ACRS-2864, NUDOCS 9311020006 | |
| Download: ML20059C756 (35) | |
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Date Issued: 04/29/93 P. Shewmon - 04/17/03 TABLE OF CONTENTS MINUTES OF THE 393RD ACRS MEETING JANUARY 7-8, 1993 I.
Chairman's Report.................................
1 II.
Replacement of Analog Instrumentation with Digital Instrumentation...........................
1 III.
Key Policy Issues for Advanced Reactor Designs....
3 IV.
Annual Report to the U.S. Congress on the NRC Research program and Budget.......................
4 V.
Reactor Operating Experience - Dislodging of Thermal Insulation at the Barseback Nuclear Pl a n t i n Swed e n...................................
4 VI.
Generic Issue 120, Online Testability of Protection Systems..........
6 VII. NRC Procedures for Incident Investigation.........
7 VIII.
Performance Indicator Report.....................
7 IX.
ACRS Subcommittee Activities......................
8 X.
Future ACRS Activities............................
9 XI.
Upgrade of ACRS Conference Room..................
10 XII.
Reconciliation of ACRS Comments and Recommendations................................
11 XIII. Miscellaneous Regulatory Review Group e
Charter....................
12 Computers in Nuclear Power Plant 0p e r a t i o n s................................
12 XIV. Summary / List of Follow-up Matters................
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393rd ACRS Minutes TABLE OF CONTENTS MINUTES OF THE 393RD ACRS MEETING JANUARY 7 8, 1993 XV. Executive Session Reports.....................................
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Letter......................................
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APPENDICES MINUTES OF THE 393RD ACRS MEETING JANUARY 7-8, 1993 I.
Attendees I!.
Future Agenda III.
Future Subcomittee Activities IV.
List of Documents Provided to the Committee l
l i
4 I
. - - - - _ -. - - _ _ - - - -. -, ~
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,m 94; ^ ' e Federal Register / Vol. 57, No? 25iO!$
dayfDecimt r3001992 T Notices i
id efDuents generated will increase, the Office of the Secretary'U.S. Nuclear ~ Meeting Agenda k
the existin controllimits in place for Regulatory Commission, Washington, Thursday, January 7,1993
' liquid discharges will not change, andDC 20555, within 30 days of the, -
8:30 a.m.-a:45 a.m.: Opening 1
the impact to the environment due to publication of this notice in the Federal The ACRS Chairman will make open)ing]
Remarks byACHS Chairman (Open l
liquid discharges will not be significant. Register;1.1 served on the NRC staff -
sThe actual volume of uranium in the air (Executive Director for. Operations, One remarks regarding conduct of the =
effluents discharged to the atmosphere White Flint North,11555 Rockville
.amay decrease because of the additional Piks, Rockville, MD 20852kon the.
meeting and comment brieDy regarding -
items of current interest.The Committee -
filters placed on the new stacks. no licensee (Combustion Engineering, Inc.,
will discuss primities for preparation of
. calculated dose to the nearest resident is P.O. Box 107 Hematite,Missourl.
wellbelow established federal 63047), and must comply with the '.
reports during this session..
v 8:45 a.m.-10:25 a.m.: Replacement of ~
.^
regulations. If the proposed action is requirements for requesting a hearing Analog Instrumentation With Digital approved the licensee willbe able to set forth in the Commission's regulation, Jnstmmentation (Open)--%e.. J.
terminate the Windsor spedal nuclear to CFR part 2, subpart L," Informal.
Committee will hear a briefing and hold materiallicense and decommission liearing Pmcedures for Adfudications in docussions with representatives of the those buildings that had been used for Materials Limusing Proceedings."
NRC staff regarding the status of the fuel fabrication, resulting in a not nese requirements,which the staffa work on the replacement of positive impact to the environment.
requestor must add sss in detail, sre:-
analog instrumentation with digital yest of gp,,jjestuestyn the instrumentationln opeating pd.
g
.> Alternirthes to the Proposed Action resentatives of the nuclear, industry The alternative to the proposed action
- 2. How that interest rosy be affected Re(! artidpate,as appro riste.
wi P
. is to deny the license amendment, by the results of the proceedin6 10:30 un-21:30 m Poucy-Denial of the proposed action would including tho' reasons why the requestor nM ced M W gns,,
should be permitted a hearing, j
n}-The Committee will discuss mean the licensee would have to
(""Th'E'neM53
"[4'ti"ffCTIaM"ihe
. continue manufacturing the nuclear fuel iedtg.ddfG"'?, %aind" d
tS and NU 3 n
b estabil 8that reactor designa. Representatives of the business. nis alternative would only be 4 The considered if there were public health g'
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NRC staff and 6f the nuclearindustry and safety lasues that could not be 3~ ;ed. wi od of a
is Will articipate, as appropriate.
P resolved to the utisfaction of the NRC.
OCD-1 L30 a.m.-12 noon:Annvol Report to Agencies and Persons Consuhed la addressing how the requestor's the U.S. Congress on the NBC Sofety -
interest may be affected by the Research Progrum and Budget (Open/
In completing this assessment, the pr ceeding, the request should describe Closed)-The Committee will discuss its staff utilized the application dated
. the nature of the requestor's right under annual report to Congress on the NRC August 5,1992, and supplemental the AtomicEnergy Act of1954,as.
safety :ssearch program. The impact of environmentalinformation dated June amended,to be made a party to the budget an continuing and proposed 19,1992, and November 12,1992. Also, proceeding: the nature and extent of the research mntracts will be discussed as on September 3,1992, the r.taff visited requestor's property, financial, or other required. RepresWatives of the NRC the site and discussed the amendment (i.e., health, safety) interest in the staff will participate, as appropriate. '
application with CE personnel.
Pmceeding; and the possible effect of Portions of this session willbe closed Finding of No Significonf impact any order may be entered in the-as necessary to discuss information the no Commission has prepared an -
Proceeding upon the requestor's premature disclosure of which would be hkely to significantly frustrate proposed interest.
Environmental Assessment related to the amendmentof SpecialNuclear Dated at Rockville, Maryland, this 2 t st day agency action.
1 P.m 2 p.m.t Reactor Operating Material License No. SNM-33. On the of December 1992.
basis of the assessment, the Commission For the Nucinar Regulatory Comminion.
Experience (Open)-%e Committee willhear a briefing by and hold has concluded that environmental kha Inckey,
. discussi ns with repreentatives of the impacts that would be created by the clef, ruel cycle safety amnch, Division of NRC staff regarding an incident at the proposed licensing action would not be industrial and Medjcal Nuclear Safety, Barseback Nuclear Plant in Sweden signincant and do not warrant the uuss.
which involved the dislodging of -
preparation of an EnvironmentalImpact [FR Doc. 92-3t706 Filed 12-29-02; 8:45 sm) thernalinsulation inside containment Statement. According!,it has been a coo, m.
and resulted in partial clogging of two determined that a Fin ing of No of five ECCS strainers. Representatives Significant Impact is appropriate.
of the nuclear industry will partidpate, The Environmental Kssessment and Advisory Committee on Reactor the above documents related to this Safeguarda; Meeting a8 6Ppropriate.
2 p.m.-4 p.m.t Generielssue 120, -
proposed action are available for public In accordance with the purposes of Online Testobility of Protection Systems hspection and copying at the sections 29 and 182b. of the Atomic (Open)-The Committee will complete Commission's Public Document Room at the Celman Building. 2120 L Street Energy Act (42 U.S.C. 2039,2232b), the its review and comment on the NRC
- NW., Washington, DC.
Advisory Committee on Reactor.
staffs pmposed resolution of this Safeguards will hold a meeting on genericissue. Representatives of the Opportunity for a Hearing January 7-9,1993,in room P-110,7920 nuclear industry will participate, as Any person whose interest may be Norfolt Avenue,Bethesda, Maryland.
appropriate.'
affected by the issuance of this renewal Notice of this meetin8 was published in 4-4:45 p.m.tNRCProcedures for ' '
may file a request for a hearing. Any the Federal Register on November 25 Incident Im'estigation (Open}~ne Committee will discuss an NRC staff request for hearing must be filed with 1992.
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' 30, 1992 / Notices 82395 Vol S7, No. 251/ Wednesday, Decet 4
Federal Daalets
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Northeast Nuclear Energy Co.;
reports regardmg hems considered Issuance of Amendment to Facility proposal for changing the a& ting procedures for the NRC investigation of dudng this meeting.
Operating Ucenee g;30pg 2:30parMisocllaneous incidents at'.icensed !=' Mat (Open)-b rnmmittee willdiscuss pocht No. 50-423]
Representatives of the NRC staff will matters mn=Mered but not completed at he U.S. Nuclear Regulatory Participata as appmpdata.
previous meetings as time and Canission %missW s ismW 4
ACRSga-6 parPreparabon ofports (Open)-N Committee availability ofinformation permit.
Amendment No. 74 to Facility i
4:45 will discuss pro reports regarding Pmadures forthe maduct of and Operating Limase No. NPF-49 lesued to Northeast Nudoar Energy Company, items consid during this meeting.
participation in ACRS meetings were which revised the Technical Fridoy, Janumy 8,1993, published la the Federal Register on Spect'fications for operation of the October 16,1992 (57 FR 47494). In 8:30 am-0;30 amrPerformance accordance with these procedures, oral Millstone Nuclear Power Station, Unit
. IndicatorReport (Opsu)-b or written statements may be presented No. 3, located in New landon County, ennn*t. h a.mandmant is Commme wiU h at a bdefing and hold by rnambes af the public, recordings effective as of the date of issuance.
discussions with repmsentatives of the willbe permitted only during those h amendmentisvises theTodmical
- NRC staff togarding pmposed revisims open portions of the meeting when a Spedesuus toinmase de to the NRC perior i snm indicatn.-
transcript is balnglept, and gestins surveillance test interval for the 4 LV report. Representauves of the nuclear may be asked onlyby members of the bus undervoltage scheme so that industry.will participata, as appropriata. Committee, its consultants, and staff.
ass ciated logic and alann relays are 9;.so am-20am.r ActMtias ofACHS Persons desiring to maks oral statements actuated once par 18 months rather than Subcomrnisees and Mambers(Open}-
should notify the ACRS Executive m rmmittee willhear reports and Director, Mr. Raymond F. Fraley, as far
"".g.,YMuhbh hold discussions of ACRS subcommittee in advance as practicable so that complies with the standanis and.
actirity on assigned topia, including appropriate strangements can be made requirements of the Atomic Enaegy Act
. the mndet of Commutae adivities by to allow the necessary time during the of 1954, as amended (the Act), and the.
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the Planning and Procedures snecting for such statements. Use of still, Commission's rules and regulations. '
Subcommittee and the NRC Senior motion picture, and television cameras b Commisdm has maduppmpdate
. Management Meetingon the during this meeting maybelimited to findings es required by the Act and the Organwtanal Factors Research selected pottions of the meeting as Commission's rules and regulations in 10:15 c.rn.-11e45 ca: Atomic Safety determined by the Chairman.
10 CHL chapter I, which are set forth in Pmgram.
the license amendment.'
and Dcensing Board Psnel Activities Infon: sion regarding the time to be set aside fo -rUs purnose may be obtained Notice of Consideration of lasuance of representatives of the Atomic Safety and by a prepaid te% call tothe ACRS Amendm
. (Open)-N rnmmitte.e sad Licensigg Board Panel (ASLDP) will Executive Disctor prior to the meeting. Hearing in connection with this action discuss anatte-s of mutual interest In view of the possibuity that the was published in the Federal Regaster including the current and anticipated schedule for ACRS meetings may be on November 9.1992 (57 FR 533601. No request for e hearing or petition for activities of the ASLBP.
adjusted by the Chainnan as necessary has e to iraerver,e was hled following 12:45 p_m.-1:d5 p.m.: Actinties of to facilitate the conduct of the meeting.
db ld check this notice.
b Commission has prepesed an -
ACRS WorkingGroups (Open)-TheCommittee will discuss the adivities of persons plann Environmental Apesament related to I
the ACRS member / staff working gmuP _ such resseduling would result in major the action and has determined not to.
y r
on the planning for the ACRS inconvenience. _
Prepase an envimamentalimpact -
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confenam rooms inthe White,N 2 1 have dotermined in eccordaom with statsamt. Based upon b 2:45 c m subsedian to(d) Public Law S2-467 that envimamentalassessment,the
- I" I'
it is nomssary to close portions of this g
gg Reports (Openkm: Preparation of ACRS e Committee will meeung noted abwe m escuss issuants of this== =-Wt will not '
havea eg**Aelbct run time gaality discuss proposed reports regarding I"""*M[bQI I"I I
of the humanenvironmed (57 FR
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items considered during this meeting.
3:15 pa-4 pa:Recoeciliation of.
fmstrate pmpmed egency adionper 5 61103).
a
-wem 4
ACRS Comments and U.SC 552b(c)(9){B).
Fm W deWis e p to b
(
Recommendations (Open)-The.
Fmther Information regarding topics action ese:(1)W application Jor,
Committee willdiscuss reeponses to be discussed, whether the meeting m.mmndment date Odober 30,1991. (2) remived from the NRCon hasbeer> cancelled or rescheduled, the Amendment No. 74 to Licanes No.NPF-49,(3) the ammi= don'a relaamd Safety r
recommendatlans made in ACRS Chaltman's tuling on requests for the a
EvalmHn= and (4) the --i. ann,
c f
reports. Representauves of the NRC staff opportunity to present oral statements Envuonmental As=====e AU e4pase will participais, as appropriaia..
and the time allotted canbe obtained by items are available for pubMc inspartin
.4 pm-4:45 p.an.:hture ACHS a prepald telephone call to the ACRS N- _
at the Commission's Pi
,j Adevities(Open}-b romn.he will Executive Director.Mr.Raymond F.
Room, the Gelsman Mw 1120 6,
Aam the report of the PlannIn and Procedurtis Sv'hmmmittae reg
, ).. Fraley(telephone 301-492-8049),
Street NW., Washing 6ae,DD 3es55 4
b between'8 a.m. and 4:30 p.m. a.s.t.
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items pmposed for cxmsideration g,gg at the local public docensmest secas
- g located at the Leersteg Bassescoe hhnc.no7,mg -
c,,,,, m p.gn}. [.
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fullf%mmMm.
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Saturday,fanury e, toss. ~7 College. 574Me*w imdan kap 7
B:30am-L30p.m.:Prepafation of ' ' AdrkoryComm!rteeMannementOfaaer,S2-417D7 FDed 12 of' ACRS Reports (Open)-b rommittee.
items (2),(3) and(4) seey t e fFR Doc will Oscuss proposed Committee], '. sume2.coor rapww.
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'o UNITED STATES J'
NUCLEAR REGULATORY COMMISSION
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i ADVISORY CONNITTEE ON REACTOR SAFEGUARDS o
WASHINGTON, D C. 20555
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i Revised: January 6, 1993 i
SCHEDULE AND OUTLINE FOR DISCUSSION 393RD ACRS MEETING JANUARY 7-8, 1993 Thursday, January 7, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, Md.
1) 8:30 8:45 A.M.
Openino Remarks by ACRS Chairman (Open) 1.1)
Opening statement - (PGS/SD) 1.2)
Items of Current Interest (PGS/RPS) 1.3)
Priorities for preparation of ACRS.
reports (PGS/SD) 2)
8:45 10:15 A.M.
Reolacement of Analoc Instrumentation With Dicital Instrumentation (Open)
TAB 2 -----
2.1)
Comments by the ACRS Subcommittee Chairman regarding the status.of the NRC staff's efforts concerning the replacement of analog instrumentation with digital instrumentation in operating plants (HWL/DC) 2.2)
Meeting with representatives of the NRC staff and the nuclear industry, as appropriate 10:15 10:30 A.M.
BREAK i
3) 10:30 11:30 A.M.
Key Policy Issues for Advanced Reactor Desians (Open)
TAB 3 ------ 3.1)
Discussion of key policy issues raised by the NRC staff applicable to-the MHTGR, PIUS,' PRISM, and CANDU3 reactor designs (JEW /MME) 3.2)
Meeting with representatives of the NRC staff and'the nuclear industry, as appropriate I
i 2
4) 11:30
- 12:00 Noon ADDyal Report to'the U.S.
Conaress on the NRC Safety Research Procram and Budaet (Open/ Closed) 4.1)
Discussion of annual report to Congress on the NRC safety research program and budget (PGS/SD) 4.2)
Participation of NRC staff representatives, as appropriato (Note: Portions of this session will be closed as necessary to discuss information the premature disclosure of which would be likely to significantly frustrate proposed agency action.)
12:00 1:00 P.M.
LUNCH 5) 1:00 2:00 P.M.
Reactor Ooeratina Experience (Open)
Briefing re arding an incident at the TAB 5 ----
5.1) w Barseback Nuclear Plant-in Sweden which involved the dislodging of thermal insulation inside containment, resulting in partial-clogging of two of five ECCS.
strainers (JCC/DC/PAB) 5.2)
Discussions with representatives of the NRC staff and industry,Las appropriate 4:00 P.M.
Generic Issue 120; Online Testability of 6) 2:00 (3:00-3:15 P.M.- BREAK)
Protection Systems (Open)
TAB 6 ----
6.1)
Comments by ACRS Subcommittee Chairman.regarding the NRC staff's proposed resolution of this generic issue (CJW/DC) j 6.2)
Discussions with representatives of
)
the NRC staff, as appropriate 7) 4:00 4:45 P.M.
NRC Procedures for Incident Investication (Open) 7.1)
Discussion of NRC staff proposal for changing the existing procedures for the NRC investigation of incidents i
at licensed facilities (HWL/EI) 7.2)
Discussions with representatives of the NRC staff, as appropriate
]
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4 1
3 Y
6:00 P.M.
Discuss Proposed ACRS Reoorts (Open) 8)
4:45 8.1)
Proposed report regarding Generic Issue 120, Online Testability of Protection Systems' (CJW/DC) 8.2)
Annual report to Congress on the NRC safety research program and Budget-(PGS/SD)
Friday, January 8.
1993. Room P-110, 7920 Norfolk Avenue. Bethesda, Md.
9:30 A.M.
Performance Indicator Report (Open).
9) 8:30 TAB 9 ---- 9.1)
Briefing regarding proposed revisions to the NRC Performance Indicator Report (JCC/DC/EGI) 9.2)
Discussions with representatives of the NRC staff, as appropriate 10) 9:30
- 10:00 A.M.
ACRS Subcommittee Activities _(Open) 10.1)
Discuss recommendations of the Planning and Procedures Subcommittee regarding items proposed for considerat;on by the Committee (PGS/RPS) 10:00 10:15 A.M.
BREAK 11)
Cancelled 11:00 A.M.
Future ACRS Activities (Open) i
- 12) 10:15 12.1)
Discuss recommendations of the l
Planning and Procedures Subcommittee regarding items proposed for consideration by i
the Committee (PGS/RPS) 12:00 Noon Activities of ACRS Workinc Groups (Open) i
- 13) 11:00 13.1)
Continuation of discussion on options for upgrade of ACRS conference rooms (JCC/MM/MS) 12:00 1:00 P.M.
LUNCH 14) 1:00 1:45 P.M.
Reconciliation of ACRS Comments and Recommendations (Open) 14.1)
Discuss replies from the NRC
]
Executive Director for Operations
)
regarding proposed reconciliation of ACRS comments and recommenda-tions (PGS, et al./SD) i 1
4 m-J; k
4 e
6:00 P.M.
Preparation of ACRS Reports (Open) 15) 1:45 (3:00-3:15: Break) 15.1)
Discuss. scope and content of-proposed reports to the NRC.
regarding matters considered l
during this meeting r
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4 CE R M B MINUTES OF 393RD ACRS MEETING l
JANUARY 7-8, 1993 The 393rd meeting of the Advisory Committee on Reactor Safeguards was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Md., on January 7-8, 1993.
The purpose of this meeting was to discuss and take appropriate action on the items i
listed in the attached agenda. The entire meeting was open to public attendance, with the exception of a portion that dealt with the selection of new Committee members and other matters of a personal nature. There were no written statements nor requests for time to make oral statements from members of the public regarding the meeting.
A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room. (Copies of the transcript are available for purchase from Ann Riley & Associates, Ltd., 1612 K Street, N.W., Washington DC 20006.)
ATTENDEES ACRS Members: P. Shewmon (Chairman), J. E. Wilkins, (Vice Chairman), J. Carroll (Member at Large), I. Catton, P. Davis, H. Lewis, W. Lindblad, C. Michelson, T.
Kress, C. J. Wylie and prospective member Bob Seale.
I.
Chairman's Report (0 pen)
Note: Mr. S. Duraiswamy was the Designated Federal Official for this portion of the meeting.
Dr. Shewmon, ACRS Chairman, opened the meeting at 8:30 a.m. and mentioned the following matters:
The agenda for this meeting.
l Noted Ray Fraley's retirement and welcomed John Larkins as the new Acting
=
Executive Director of the ACRS.
Noted the closing of the Trojan Nuclear Plant.
Discussed priorities for the proposed ACRS reports and lctters to be discussed at the meeting.
Welcomed Bob Seale as a member of the Committee.
II.
Replacement of Analoa Instrumentation with Diaital Instrumentation (0 pen) t Note:
Mr. D. Coe was the Designated Federal Official for this portion of the meeting.
Dr. H. Lewis, Chairman of the Computers in Nuclear Power Plant Operations Subcommittee, introduced this topic to the Committee by noting that the 1
393rd ACRS Minutes 2
staff and industry are not in agreement regarding the degree to which staff review is required for licensee modifications involving replacement of analog instruments and controls with digital equipment. He stated that this informational briefing is an opportunity for the staff to discuss their thinking on this issue, and that NUMARC was present to answer any Committee questions.
NRC Staff Presentation, Mr. J. Mauck, Section Chief, I&C Branch, NRR Mr. B. Boger, Director of the Division of Reactor Controls and Human Factors, opened the staff's presentation by noting that the staff's final position on this issue would concede that not all analog-to-digital conversions, by definition, involve an unreviewed safety question. Mr. J.
Mauck then discussed the reasons plants are interested in conversions to digital a
equipment, how digital upgrades can improve safety, a list of plants that have performed such modifications, both under 10CFR50.59 and by NRC staff review, the staff's basis for its proposed position that most digital-based safety system:,
involve an unreviewed safety question under 10CFR50.59, the responses received during the public comment period for the a
proposed Generic Letter on analog-to-digital conversions, and future planned staff activities to meet with industry a
representatives to discuss the threshold for staff review.
Mr. Alex Marion spoke briefly for NUMARC by noting that the industry feels NRC expectations need to be transmitted to them so that regulatory uncertainty is reduced enough to allow forward progress. He stated that the joint meetings with the staff were intended to achieve more certainty in these expectations.
Mr. Michelson asked what portion of an instrument system was most subject to drift in voltages, currents, setpoints, and other process parameters over time.
Mr. Mauck explained that drift occurs throughout an analog system, from sensor through signal processing racks.
He noted tht sensors are not usually included in digital retro-fits and would continue to be subject to drift, although overall improvement is achieved.
Dr. Lewis expressed his view that the NRC proposed position might limit the incentive of industry to find genuinely new ways of employing digital systems beyond simply making improvements to old ways of providing control, protection, and information display functions. Mr. Mauck stated that the staff is trying to meet its legal mandate to ensure plants are safe without actively trying to hold back innovation.
393rd ACRS Minutes 3
Dr. Lewis asked if the staff was treating this issue as a safety or a legal issue.
Mr. Boger realied that the staff's concern is the safety issue, but recognizes that legal questions regarding the application of 10CFR50.59 also need to be addressed.
Dr. Lewis questioned what was meant by the staff's use of the word
" digi tal. " Mr. Mauck answered that the use of software was implied when the staff discusses its concerns over new failure modes of digital equipment.
He emphasized that the proposed Generic Letter was concerned only with software-based digital systems, and acknowledged that the definition of " software" may not be fully developed yet.
Dr. Lewis asked if the NRC Office of General Counsel has concurred with the staff's proposed Generic Letter.
Mr. Mauck responded that OGC has concurred and its comments were very favorable.
Conclus!o.nl This was a briefing for information only.
No ACRS action was taken at this meeting.
III.
Key Policy Issues for Advanced Reactor Desiani (0 pen)
Note: Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.
Dr. Wilkins, Chairman of the Advanced Reactor Designs Subcommittee, discussed the Key policy issues that were identified by the NRC staff for the MHTGR, PIUS, PRISM, and CANDU 3 designs.
There are 10 key policy issues that have been identified for ACRS consideration and on which the staff is requesting approval of their position or alternate guidance.
These issues were discussed at a January 6, 1993 meeting of the Advanced Reactor Designs Subcommittee.
Staff Comments Dr. Murley, NRR, suggested that the ACRS request a meeting with representatives of the Department of Energy to discuss the status of the latest designs.
He noted that the PRISM reactor might be viewed as an actinide burner for waste management.
j Conclusions Discussion of the ten key policy i.ssues will be discussed with the pre-applicants and the NRC staff at the February 11-13, 1993 ACRS meeting. No Committee action was taken at this meeting.
Note:
Representatives of the Department of Energy will attend the February 1993 ACRS meeting and discuss their status of the PRISM and the HTGR.
4 393rd ACRS Minutes 4
IV.
Annual Reoort to the U.S. Conaress on the NRC Safety Research Proaram and Budaet (0 pen)
Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.
The Committee reviewed draft letters on this subject.
Section 29 of the Atomic Energy Act of 1954, as amended by Section 5 of Public Law 95-209, requires the ACRS report to the Congress each year on the Safety Research Program of the NRC.
Conclusions The Committee provided letters on this subject to The Honorable Albert Gore, Jr., President of the United States Senate and The Honorable Thomas S. Foley, Speaker of the United States House of Representatives, as noted in Section XV.
V.
Reactor Operatina Exoerience - Dislodaina of Thermal Insulation at the Barseback Nuclear Plant in Sweden (0 pen)
Note: Mr. Paul Boehnert was the Designated Federal Official for this portion of the meeting.
Mr. J. Carroll, Chairman of the Plant Operations Subcommittee, introduced this discussion topic to the Committee. He indicated that the Committee had expressed interest in a transient that occurred last year in the Swedish Barseback BWR power plant.
During a minor LOCA event, the containment sumps became clogged with pieces of insulation that were blown off RCS piping.
Clogging of the sumps necessitated operator actions, i.e., backflushing, in order to prevent possible cavitation of the ECCS pumps being used to cool the core.
NRC-NRR Presentations Mr. G. Holahan noted that Mr. R. Dennig will summarize the details of the above event, and that Mr. R. Barrett would provide an overview of the staff's actions (on-going and planned) in response.
Details of the Barseback, Unit 2 July 28, 1992 containment spray sump blockage event were noted by Mr. Dennig. He noted the following summary points:
Unit 2, a 615 Mwe BWR, was designed by ABB and was placed in commercial operation in July, 1975.
On July 28, while at 1-2% power, a safety valve spuriously opened resulting in steam discharge to containment (pursuant to design).
Core and containment spray actuated as designed; the force of the steam discharge dislodged jacketed mineral wool insulation.
393rd ACRS Minutes 5
The insulation was washed into the wetwell; approximately one hour later the operators saw evidence of cavitation for the containment spray pumps due to clogging of the sump strainers by the insulation.
Operators were able to cope with the event given a low decay heat level and the capability to backflush the containment spray strainers, thus restoring spray function.
If a design-basis LOCA had occurred, core overheating could occur due to loss of the ECCS pumps prior to completion of the backflushing operation.
Mr. Davis asked if any U.S. plants discharge their safety relief valves to the drywell, as at Barseback. NRR indicated that some do. In response to Dr. Catton, Mr. Dennig said that the surprises for this event included the speed at which the sump strainers clogged up (one hour versus ten hours assumed in the Swedish safety study) and the amount of insulation that was swept into the sumps. Mr. Michelson, referring to the deliberations that surrounded resolution of USI A-43 (Containment Emergency Sump Performance) urged NRR to revisit the issue of the ECCS pump bearings becoming clogged with fiberglass particles from dislodged insulation.
The staff's Action Plan for addressing resolution of concerns raised by the Barseback event was described by Mr. R. Barrett.
The Action Plan consists of the following elements:
Develop understanding of event Determine if U.S. BWR plants are susceptible to a similar event Determine if there is need for immediate action for U.S. plants Revisit technical findings of USI A-43 vis sump / strainer clogging Determine appropriate regulatory action (s)
Concerning the need for immediate regulatory action, Mr. Barrett indicated that NRR has decided no immediate action is needed because: (1)thisissue is not new, having been addressed via USI A-43, and (2) core-melt risk is relatively low during the interim that the staff will evaluate this matter.
Mr. Davis asked how NRR became aware of this event. Mr. Barrett said that it was reported via the IAEA/NRC normal communication arrangements.
In response to questions from Dr. Catton, Mr.
A.
Serkiz (USI A-43 Task Manager) indicated that the model developed by NRC to estimate the amount of insulation destroyed / disturbed given a
LOCA was successfully
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benchmarked against the HDR containment blowdown experiment.
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Mr. Michelson, citing the ACRS letter issued in 1985 following Committee review of the staff's resolution approach for USI A-43, said the Committee expressed two concerns: the impact of (insulation) debris on pump seals and bearings, and, the trend of licensees to switch from use of metallic to fibrous insulation for the RCS.
NRR has initiated a survey of all U.S. BWRs to determine their susceptibly to a Barseback-type event.
The goal of the survey is to determine if
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393rd ACRS Minutes 6
these plants conform to the major elements specified in Regulatory Guide 1.82, Revision 1 which was issued in 1985 pursuant to resolution of USI A-t 43.
This study should be completed by mid-1993.
Plants found with potential problems here will be dealt with on a case-by-case basis.
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the long term, PWR plants will also be evaluated vis-a-vis this issue.
Mr. Holahan committed the staff to investigating the issues raised above by Mr. Michelson as part of the BWP plant survey.
They will also ensure that this matter is evaluated for the ABWR design certification review.
Prior to recess, Mr. Carroll requested that the cognizant staff engineer for this issue monitor NRR's progress.
He also said that the Committee i
should be informed of the staff's ultimate resolution approach for this matter.
Conclusions The Committee wishes to be kept informed of the staff's progress in determining if U.S. BWRs are susceptible to a similar series of events as occurred at Baresback, as well as be informed of NRR's ultimate resolution of this matter.
t VI.
Generic Issue 120. Online Testability of Protection Systems (0 pen)
Note:
Mr. D. Coe was the Designated Federal Official for this portion of the meeting.
Mr.
C.
Wylie Chairman of the Control and Electrical Power Systems Subcommittee, introduced this topic.to the Committee by noting that the NRC staff was prepared to answer the Committee's unanswered questions remaining on Generic Issue 120 from the 392nd ACRS meeting in December 1992.
NRC Staff Presentation, Dr. T. Chang, RES Mr. B. Baer, RES, opened the staff's presentation with a brief discussion of how GSI 120 originated and the NRC Office of Research approach to its resolution.
Dr. Chang continued the staff's presentation by further describing the origins of GSI-120, the focusing of the approach to resolution toward ESF " slave a
relays,"
the function of ESF " slave relays" within the larger ESF system and a
the concept of overlapping testing methods, the use of staggered testing as a basis for allowing certain ESF
" slave relays" to be tested only during shutdown conditions pursuant to the new Standard Technical Specifications, and
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the staff's review of advanced plant designs with respect to the resolution of GSI-120.
P Mr.3rroll asked if Regulatory Guide 1.22 legitimizes a way in which a licensee can avoid compliance with GDC-21.
Mr. Baer stated that GDC-21 was originally intended to apply to reactor protection systems (not including ESF systems), and that as ESF systems evolved, the staff had to make provisions for those portions of ESF systems which could disrupt plant operations if tested while the plant was operating.
He further noted that RES is not tasked with determination of compliance issues.
Conclusions The Committee provided a report on this matter to Mr. James M. Taylor, Executive Director for Operations, as noted in Section XV. The Committee agreed with the NRC staff's conclusions and recommendations.
VII.
NRC Procedures for Incident Investication (0 pen) 4 Note: Mr. M. D. Houston was the Designated Federal Official for this portion of the meeting.
Dr. Lewis, Chairman of the Regulatory Policies and Practices Subcommittee, introduced this topic by summarizing the NRC staff's proposed options as described in SECY-92-413 for the Incident Investigation Program.
The Committee had been given copies of SECY-92-413, " Incident Investigation Options Reporting to the Commission," and was prepared to offer comments on it.
In general, the Committee endorsed the NRC staff's proposal but did have some comments regarding the makeup of the Incident Investigation Group (IIG) membership and the IIG reporting instructions.
Conclusions i
The Committee provided a report on this matter to Chairman Selin, as noted as noted in Section XV.
It was decided that the Committee would not acknowledge the personal letter that Dr. Lewis had sent to the Commission in December 1992 commenting on this matter.
VIII. Performance Indicator Report (0 pen)
Note: Mr. E. Igne was the Designated Federal Official for this portion of the meeting.
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NRC Staff Presentations SECY-425, " Performance Indicator Program - Peer Group and Operating Cycle Phase Enhancements," was submitted to the Commission on December 23, 1992.
The NRC staff discussed the improvement to the performance indicator program delineated in SECY-425.
The improvements include the operating phase effects and the comparison of an individual plant to its peer group instead of the industry average. The peer group plants are from a
393rd ACRS Minutes 8
particular NSSS vendor, with similar product line, generating capacity, age, etc.
Reportable events vary significantly with plant activities.
The NRC staff described some of the statistical calculational methods used to determine the trends for each individual plant and how the individual plant is compared to the peer group. Members of the Committee questioned the validity of using the median value instead of the mean to indicate trend deviations as well as the statistical significance of the results based on a small number of plants in the peer group.
Some graphical results of causes code for various peer groups were shown.
Also shown were trends and deviation histograms.
Conclusions This was a briefing for information only.
No ACRS action was taken at this time.
I IX.
ACRS Subcommittee Activities (0 pen)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting.
ReDort of ACRS Plannina and Procedures Subcommittee Meetina on Januarv 6,
1191 The minutes of the January 6,1992 Planning and Procedures Subcommittee meeting were discussed.
There was general agreement with the minutes of that meeting with the following comments:
Status of Actions Related to R. Fraley's Retirement It was noted that Mr. Fraley will be retiring from the NRC on February 26, 1993.
The Committee agreed to have a retirement dinner in honor of Mr.
Fraley on the evening of February 11, 1993.
ACRS/ACNW Budaet (Multilateral Meetina)
It was noted that the ACRS office had received correspondence from the German RSK indicating that the French GPR has indicated its intent to sponsor a multi-national meeting of reactor safety advisory committees in France in October 1993. The members suggested that the preferred date was the week of October 21-25, 1993 and the second choice for that month was October 11-15, 1993.
It was noted that since the FY 1994 budget may not be approved until October 1993 that funding for the trip may be a problem.
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The ACRS office staff was asked to look into this matter and discuss the outcome with Dr. Wilkins.
Dr. Wilkins should then agree on the actual date to be suggested.
Note: The ACRS office staff was told by the French DSIN that the meeting would have to be held during the week of October 11-15, 1993 or at some much later undetermined date.
Dr. Wilkins agreed that October 11-15, 1993 would be appropriate.
The German RSK staff was notified of the
393rd ACRS Minutes 9
acceptability of October 11-15, 1993 and a memorandum was sent to Chairman Selin's office notifying the Commissioners of the Committee's intant to accept the invitation.
X.
Future ACRS Activities (0 pen)
Note: Dr. R. Savio was the Designated Federal Official for this portion of the meeting.
The following activities were scheduled for the 394th ACRS Meeting, February 11-13, 1993, Bethesda, MD:
Key Policy Issues for Preapolication Desians - The Committee will review and comment on key policy issues identified by the NRC staff L
for resolution with respect to advanced reactor designs such as the l
MHTGR, PIUS, PRISM, and CANDU-3. Representatives of the NRC staff, of the Department of Energy and of the industry will participate, as appropriate.
Fitzpatrick Nuclear Power Plant - The NRC staff will brief the Committee on the restart of the Fitzpatrick nuclear plant following an extended shutdown for plant and organizational changes.
Representatives of the licensee and will participate, as appropriate, Research on Oroanizational Factors - The NRC staff will brief tha a
Committee on matters regarding NRC sponsored research oh organizational factors.
Representatives of the industry will participate, as appropriate.
Atomic Safety and Licensina Board Panel (ASLBP) - The NRC staff will brief the Committee regarding the current and anticipated activities of the Atomic Safety Licensing Board Panel (ASLBP).
Multiple System Responses Proaram - The NRC staff will brief the Committee regarding the status of the staff's work for dealing with the potential generic safety issues identified in the Multiple System Responses Program.
ACRS Subcommittee Activities - The Committee will hear and discuss the status of ACRS subcommittee assignments, including use of digital instrumentation and control systems in nuclear power plants, the ABB-CE System 80+ design, and pro'cedures for conduct of ACRS business.
Representatives of the NRC staff will participate, as appropriate.
Future ACRS Activities - The Committee will discuss topics proposed for consideration by the full Committee.
Resolution of ACRS Recommendations - The Committee will discuss the j
NRC Executive Director for Operations replies to recent ACRS comments and recommendations.
NRC Reaulatory Review Group - The Committee will discuss the proposed charter for and activities of the NRC Regulatory Review Group. The purpose of this group will be to conduct a comprehensive and disciplined review of power reactor regulations and related NRC process, programs, and implementation practices. Representatives of the NRC staff and of the industry will participate, as appropriate.
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393rd ACRS Minutes 10 Briefino on Recent Chanaes to the Reaulations on the Conduct of Government Emoloyees - Representatives of the NRC Office of the-General Counsel will brief the Committee on the impact on ACRS members of the implementation of the recent Office of Government Ethics government-wide changes to the regulation on the conduct of government employees.
Schedules of NRC Review of Proposfd Advanced Reactor Desians - The NRC staff will brief the Committee on the current schedules for the NRC staff's review of proposed advanced reactor designs.
Miscellaneous - The Committee will discuss information of a personal nature where disclosure would constitute an unwarranted invasion of personal privacy and matters discussed but not completed during previous meetings as time and availability of information permit.
Multilateral Meetina of Advisory Committees The Committee discussed some proposed dates that were suggested by the
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French GPR and the German RSK for the next International Meeting of Advisory Committees.
Dr. Wilkins and the ACRS staff should determine whether funding of travel for such a meeting might be a problem if the meeting is conducted in October 1993.
It was noted that the French GPR, along with the German RSK has agreed to sponsor the meeting in France in October 1993.
Note: It has been decided that October 11-15, 1993 is the only date acceptable to all parties, i.e., the French GPR, the German RSK, the Japanese NSC, and the ACRS, for the conduct of this meeting during calendar year 1993.
It appears that it will be advantageous to purchase airline tickets and pay the workshop admission charges (which include room and board) in FY 93.
XI.
Uoarade of ACRS Conference Room (0 pen)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting.
Mr. Stella, ACRS Fellow, discussed preliminary comments from ACRS members on a questionnaire that members had completed and returned to the ACRS office on matters concerning the future conference room computer equipment to be considered for the new White Flint building.
Conclusions This matter will be continued at future ACRS meetings.
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XII.
Reconciliation of ACRS Comments and Recommendations (0 pen)
Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.
The Executive Director for Operations' (E00's) responses to previous ACRS reports were discussed as follows:
ED0 letter, dated December 2, 1992, responding to the ACRS report dated October 16, 1992, concerning SECY-92-287, " Form and Content for a Design Certification Rule."
The EDO letter did address the Committee's comments.
ED0 letter, dated December 8, 1992, responding to the ACRS report dated October 15,
- 1992, concerning
" Proposed Guidance for Implementation of the Maintenance Rule, 10 CFR 50.65."
The ED0 letter did address the Committee's comments; however, it was noted that the Commission has given the ACRS an SRM to look at maintenance with regard to plant life extension and has asked the Committee for advice on this matter.
ED0 letter, dated December 10, 1992, responding to the ACRS report dated November 12, 1992, concerning the staff's research program related to the environmental qualification of digital instrumentation and control (I&C) systems.
The ED0 letter did address the Committee's comments; however, it was suggested that the Committee take a " wait and watch" approach to see what is actually accomplished. The ACRS staff should look into the ED0's proposed actions and invite the staff to an ACRS meeting in about six months to see if the proposed actions have actually been accomplished.
ED0 letter, dated December 16, 1992, responding to the ACRS report dated November 16, 1992, concerning the staff's draf t Commission paper on risk-based regulation.
The EDO letter did address the Committee's comments..Even though members of the Committee were not satisfied with the response, they did agree to take a " wait and watch" approach to see what is actually accomplished. Dr. Lewis noted that even though the EDO did say that the NRC staff's activities are
" coordinated. and consistent," that the Committee has said otherwise in various letters.
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393rd ACRS Minutes 12 XIII. Miscellaneous (0 pen)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting.
Reaulatory Review Group Charter Dr. Lewis noted that he has a concern with the discussion in Comis-92-025 Regulatory Review Paper, that ht: the NRC reviewing itself.
Mr. Lindblad was asked to look at the Comis-92-025 Paper and the Charter of the Regulatory Review Group and suggest whether the ACRS staff should invite Messrs. Gillespie or Sniezak to the February 1993 ACRS meeting to discuss the Paper.
Note:
Mr. Gillespie has asked to brief the Committee on the proposed charter of the Regulatory Review Group at the February,1993 ACRS meeting.
This briefing has been scheduled.
Computers in Nuclear Power Plant Operations Dr. Lewis discussed the need he perceives for a short workshop on the relationship between digital systems reliability and nuclear safety by the National Academies of Sciences and Engineering. The Committee reviewed a draft proposed letter to the Commission but did not endorse it.
Drs. Lewis, Kress and Wilkins did send a personal letter, not approved by the Committee, on this matter to Chairman Selin, dated December 11, 1992.
XIV.
Summary / list of Follow-up Matters The Committee should specify at the time it approves its reports, that the report will be included in the annual report to Congress on the Safety Research Program of the NRC. (All ACRS staff engineers have follow-up on this matter.
Mr. Boehnert has the lead on this matter and should maintain a list of reports to be included.)
Mr. Michelson asked to receive a copy of an environmental qualification information report on the harsh environment at the Haddam Neck Nuclear Plant that was referred to by Mr. Mauch, NRR, during his presentation on replacement of analog instrumentation with digital instruments. (Mr. Coe has the follow-up on this matter.)
Mr. Mauch, NRR, agreed to provide the ACRS with documents and minutes of NRC staff /NUMARC meetings on replacement of analog instrumentation. (Mr. Coe has the follow-up on this matter.)
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393rd ACRS Minutes 13 Representatives of the Department of Energy (D0E) sho~uld be invited to a future ACRS meeting to discuss their advanced reactor designs and status and the DOE positions being taken with regard to these designs.
(Dr. El-Zeftawy has the follow-up on this matter.)
Mr. Holahan, NRR, agreed to keep the Committee informed of the NRC staff's progress in determining if U.S. BWRs are susceptible to ECCS sump clogging with insulation, such as occurred at the Barseback Nuclear Plant in Sweden.
In addition, the Committee would like to know the NRC staff's ultimate resolution of this matter, including the resolution of the Committee's September 16, 1985 Report to the Commission that raised the concern of the effect of sump debris on pump seals and bearing assemblies.
(Mr. Coe has the follow-up on this matter.)
XV.
Executive Session (0 pen)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting.
During its 393rd meeting, January-7-8, 1993, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and letters as noted.
Reports SECY-92-413. " Incident Investiaation Options Reportino To The Commission" (Report to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated January 13,1993)
Proposed Resolution of Generic Safety Issue 120. "On-Line Testability of Protection Systems."
(Report to Mr. James M. Taylor, Executive Director for Operations, from Paul Shewmon, ACRS Chairman, dated January 13,1993) letters Letter to the Honorable Albert Gore, Jr., President of the United States Senate, from Paul Shewmon, ACRS Chairman, reporting on the Safety Research Program of the Nuclear Regulatory Commission, dated January 28, 1993.
Letter to the Honorable Thomas S. Foley, Speaker of the United States House of Representatives, from Paul Shewmon, ACRS Chairman, reporting on the Safety Research Program of the Nuclear Regulatory Commission, dated January 28, 1993.
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Meeting was adjourned at 11:45 am on January 8, 1993
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t APPENDICES MINUTES OF THE 393RD ACRS MEETING JANUARY 7-8, 1993 I.
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List of Documents Provided to the Committee
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APPENDIX I MINUTES OF THE 393TH ACRS MEETING JANUARY 7-9, 1993
~i January 7. 1993 4
Public Attendees NRC Attendees Y. S. Kim, NUS G. C. Wright, Region III/EDO John Herczeg, DOE M. R. Fleishman, OCM/KR Kevin Graney, SERCH Licensing, Bechtel F. Coffman, RES A. Marion, NUMARC C. C. Harbuck, NRR Tony Pietrangelo, NUMARC B. Bouer, NRR a
Karen Unnerstall, Newman & Holtzinger H. Pastis, NRR Roger Huston, TVA C. Antonesa, RES Dick Becker, GE W. Gleaves, RES L. W. Rib, AECLT M. Slosson, NRR'
> Connor, STS E. D. Throm, NRR Rex Brown, George. Mason University D. Sealretti, NRR R. J. Ba T. Cox, NRR John M. Fubringer, EG & G, Idaho Inc.
J. Kennedy, NRR M. Taylor, OEDO J. J. Burns, RES H. Newsome, OGC J. E. Donoghue, NRR G. Sege, RES J. Kudrick, NRR T. Dangelo, NRR R. Woodruff, NRR T. Cintula, AE0D l
R. J. Barrett, NRR A. L. Sericiz, RES T. Y. Change, RES R. J. Summers, OCM/GD A. E. Chaffee, NRR i
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APPENDIX 11 MINUTES OF THE 393RD ACRS MEETING JANUARY 7-8, 1993 FUTURE AGENDA The following activities were scheduled for the 394th ACRS Meeting, February 11-13, 1993, Bethesda, MD:
e Key Policy Issues for Preapolication Desians - The Committee will review and comment on key policy issues identified by the NRC staff for resolution with respect to advanced reactor designs such as the MHTGR, PIUS, PRISM, and CANDU-3. Representatives of the NRC staff, of the Department of Energy and of the industry will participate, as appropriate.
Fitzpatrick Nuclear Power Plant - The NRC staff will brief the-Committee on the restart of the Fitzpatrick nuclear plant following an extended shutdown for plant and organizational changes.
Representatives of the licensee and will participate, as appropriate.
Research on Orcanizational Factors - The NRC staff will brief= the Committee on matters regarding NRC sponsored research on organizational factors.
Representatives of the industry will participate, as appropriate.
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Atomic Safety and Licensino Board Panel (ASLBP) - The NRC staff will brief the Committee regarding the current and anticipated activities of the Atomic Safety Licensing Board Panel (ASLBP).
Multiple System Responses Proaram - The NRC staff will brief the Committee regarding the status-of the staff's work for dealing with the potential generic safety issues identified in the Multiple System Responses Program.
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ACRS Subcommittee Activities - The Committee will hear and discuss the status of ACRS subcommittee assignments, including use of digital instrumentation and control systems in nuclear power plants, the ABB-CE System 80+ design, and procedures for conduct of ACRS business.
Representatives of the NRC staff will participate, as appropriate.
Future ACRS Activities - The Committee will discuss topics proposed for consideration by the full Committee.
l Resolution of ACRS Recommendations - The Committee will discuss the NRC Executive Director for Operations replies to recent ACRS i
comments and recommendations.
NRC Reaulatory Review Group - The Committee will discuss the proposed charter for and activities of the NRC Regulatory Review Group. The purpose of this group will be to conduct a comprehensive and disciplined review of power reactor regulations and related NRC process, programs, and implementation practices. Representatives of the NRC staff and of the industry will participate, as appropriate.
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1 Briefina on Recent Chanaes to the Reaulations on the Conduct of' Government Employees - Representatives of the NRC Office of the General Counse'. will brief the Committee on the-impact on ACRS members of the implementation of the recent Office of Government Ethics government-wide changes to the regulation on the conduct of government employees.
Schedules of NRC Review of Proposed Advanced Reactor Desians - The NRC staff will brief the Committee on the current schedules for the NRC staff's review of proposed advanced reactor designs.
Miscellaneous - The Committee will discuss information of a personal nature where disclosure would constitute an unwarranted invasion of personal privacy and matters discussed but not completed during previous meetings as time and availability of information permit.
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APPENDIX III MINUTES OF THE 393RD ACRS MEETING JANUARY 7-8, 1993 FUTURE SUBCOMMITTEE ACTIVITIES Computers in Nuclear Power Plant Operations, February 9,
- 1993, 7920 Norfolk Avenue, Bethesda, MD (Coe), 8:30 a.m., Room P-110.
The Subcommittee will discuss current and proposed methods used L
to evaluate software for safety-critical applications, including the use of risk-based criteria.
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of February 8:
Lewis RESIDENCE INN Wilkins HOLIDAY INN Carroll HOLIDAY INN Wylie HYATT I
Catton HYATT Advanced Pressurized Water Reactors, February 10, 1993, 7920 Norfolk Avenue, Bethesda, MD (Igne), 8:30 a.m., Room P-110.
The Subcommittee will begin its review of the NRC staff's Draft Safety Evaluation Report (NUREG-1462) for certification of the ABB CE System 80+ Design.
Attendance by the following is antici-pated, and reservations have been made at the hotels as indicated for the night of February 9:
Carroll HOLIDAY INN Michelson HYATT Catton HYATT Seal NONE Davis NONE Shewmon NONE Kress HYATT Wilkins HOLIDAY INN Lindblad HYATT Wylie HYATT Plannino and Procedures, February 10, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 3:00 p.m. - 5:30 p.m., Room P-422.
The Subcommittee will discuss proposed ACRS activities and related matters.
Qualifications of candidates nominated for appointment to the ACRS will also be discussed.
Portions of this meeting will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy.
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of February 9:
Shewmon NONE Wilkins HOLIDAY INN Carroll HOLIDAY INN
t 394th ACRS Meetina, February 11-13, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110.
Items are tentatively scheduled.
A.
Kev Policy Issues for Preapplication 'Desians Review and i
comment on key policy issues identified by the NRC staff for resolution with respect to advanced reactor designs such as' the MHTGR, PIUS, PRISM, and'CANDU-3.
Representatives of the i
NRC staff, of the Department of Energy and of the industry' will participate, as appropriate.
B.
Fitzpatrick Nuclear Power Plant,- Briefing and discussion regarding restart of the Fitzpatrick nuclear plant following an extended shutdown for plant and organizational changes.
Representatives of the licensee and of the NRC staff will participate, as appropriate.
Besearch on Oraanizational Factnrq - Lriefing and discussion C.
regarding NRC sponsored research on organizational factors.
Representatives of the NRC staff and of the industry will participate, as appropriate.
D.
Atomic Safety and Licensing _ Board Panel (ASLBP) - Briefing by and discussion with representatives of the ASLBP regard-ing the current and anticipated activities of the ASLBP.
E.
Multiple System Responses Procram - Briefing by and discus-sion with representatives of the NRC staff regarding the status of the staff's work for dealing with the potential generic safety issues identified in the Multiple System Responses Program.
F.
ACRS Subcommittee Activities - Reports on and discussion of the status of ACRS subcommittee assignments, including use of digital instrumentation and control systems in nuclear power plants, the ABB-CE System 80+ design, and procedures for conduct of ACRS business.
Representatives of the NRC staff will participate, as appropriate.
G.
Future ACRS Activities - Discuss topics proposed for con-sideration by the full Committee.
H.
Resolution of ACRS Recommendations - Discuss replies from
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the NRC Executive Director for Operations regarding the NRC staff reaction to recent ACRS comments and recommendations.
I.
NRC Reculatory Review Group - Discuss the proposed charter for and activities of the NRC Regulatory Review Group.
The purisse of this group will be to conduct a comprehensive and disciplined review of power reactor regulations and related NRC process, programs, and implementation practices.
Repre-sentatives of the NRC staff and of the industry will partic-ipate, as appropriate.
J.
Briefina on Recent Chances to the Reaulations on the conduct of Government Employeen - Briefing by and discussion with representatives of the NRC Office of the General Counsel on the impact on ACRS members of the implementation of the recent Office of Government Ethics government-wide changes to the regulation on the conduct of government employees.
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3chedules of NRC Review of Proposed Advanced Reactor Desians
- Briefing by and discussicn with representatives of the NRC staff on the current schedules for the NRC staff's review of proposed advanced reactor designs.
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Miscellaneous - Discuss information of a personal nature where disclosure would constitute an unwarrantod invasion of personal privacy and matters discussed but not completed during previous meetings as time and availability of infor-mat'an permit.
Thermal Hydraulic Phenomena,' March 4 and 5, 1993, (exact-location to be determined) Idaho Falls, ID (Boehnert), 8:30 a.m.
The Subcommittee will review the status of the PWR version of the RELAP5/ MOD-3 code with emphasis on analytical programs in support of the AP600 design certification effort.
Attendance by the following is anticipated:
Catton Schrock Davis Ward Kress Wulff Wilkins Zuber Dhir i
Joint Materials-and Meta,llurcv/ Structural Encineerina, March 10, 1993, 7920 Norfolk Avenue, Bethesda, MD (Igne), 8:30 a.m.,
Room P-110.
The Subcommittees will discuss:
(1) the status of the NRC staff's concerns regarding steam generator tube degradation, and (2) the industry proposal on piping design improvements to reflect current technical knowledge for ALWR plants.
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of March 9:
Shewmon NONE Davis NONE Kress HYATT Catton HYATT Carroll HOLIDAY INN Siess (tent.)
NONE Lewis RESIDENCE INN Thompson (tent. ) NONE Lindblad HYATT Michelson HYATT J
395th ACRS Meetina, March 11-13, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110.
Agenda to be announced.
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Reaional Procra m_g, March 23, 1993, Region II Offices, Atlanta, GA (Bochnert), 8:30 a.m.
The Subcommittee will review the activi-ties of the NRC Region II Office.
Lodging will be announced later.
Attendance by the following is anticipated:
Shewmon Michelson Carroll Wylie Probabilistic Risk Assessment (tentative) Date to be determined 1
(February / March), Bethesda, MD (Houston).
The Subcommittee will discuss a proposed regulatory guide on the use of PRA in design certification and other applications of PRA in the regulatory process.
Attendance by the following is anticipated:
Lewis Wilkins Davis Consultants - TBD Kress Michelson t
Safety Philosophy, Technolocry and Criteria (tentative), Date to be determined (February / March), Bethesda, MD (Houston).
The Subcommittee will discuss a proposed plan for comparing safety 1
goals with regulations.
Attendance by the following is antici-f pated:
Kress Wylie Davis Kerr Lewis Ward Michelson Joint Severe Accidents /Probabilisti(Llink Assessment (PRA),
(tentative) Date to be determined (Feb m ary/ March), Bethesda, MD (Houston).
The Subcommittees will s tsco.s Chapter 19 of the ABWR FSAR and its evaluation in regard 7 ae'are accident and PRA issues.
Attendance by the followl 3r anticipated:
Kress Shewmon i
Lewis Wilkins Catton Kerr Davis Lee Lindblad Other Consultants - TBD Michelson i
m
,s 5
Reliability and Ouality, Date to be determined (March / April),
Bethesda, MD (Igne).
The Subcommittee will discuss the quality management standard used by the European Community (ISO 9000) and its impact on the domestic nuclear power plant industry.
Atten-dance by the following is anticipated.
Kress Michelson Carroll Shewmon Davis Wylie Lindblad Recav Heat Removal Systems, Date to be determined (March / April),
Bethesda, MD (Boehnert).
The Subcommittee will continue its review of.the NRC staff's proposed final resolution of Generic Safety Issue 23, " Reactor Coolant Pump Seal Failures."
Atten-dance by the following is anticipated:
Catton Michelson Davis Wylie Lindblad Ward Thermal Hydraulic Phenomena, Date to be. determined (April /May, 2-day meeting), San Jose, CA (Boehnert).
The Subcommittee will continue its review of both the GE analytical program (TRACG code) and the experimental programs suppo:: ting the certification effort for the Simplified Boiling Water Reactor design.
Atten-dance by the following is anticipated:
Catton Kerr Davis Ward Kress Wulff Wilkins Zuber Dhir Joint Severe Accidents / Thermal Hydraulic Phenomena, Date to be determined (April /May), Bethesda, MD (Houston).
The Subcom-mittees will begin the discussion of the technical positions on severe accident issues for future plant designs.
The topics of fuel-coolant interactions and hydrogen will be discussed.
Attendance by the following is anticipated:
Kress Shewmon Catton Ward Davis Kerr Lindblad Lee Michelson Dhir
e-e.
k 6
Thermal Hydraulic Phenomena, Date to be determined (2-day meet-ing), (May), Orecon State University, Corvallis, OR (Bochnert).
The Subcommittee will continue its review of the. Westinghouse and NRC integral systems and separate effects test programs support-ing the AP600 design certification effort.
Attendance by the following is anticipated:
Catton Kerr Davis Schrock Kress Ward Wilkins Wulff Dhir Zuber Thermal Hydraulic Phenomena, Date to be determined, Bethesda, MD (Boehnert).
The Subcommittee will continue its review of the NRC staff program to address the issue of interfacing systems LOCAs.
Attendance by the following is anticipated:
Catton Dhir Davis Kerr Kress Schrock Wilkins Ward Wulff Zuber Joint Thermal Hydraulic Phenomena / Core Performance, Date_to be determined, Bethesda, MD (Boehnert).
The Subcormittees will continue their review of the issues pertaining to BWR core power stability.
Attendance by the following is anticipated:
Catton Dhir-Wilkins Kerr Davis Lee Kress Lipinski Shewmon Zuber Joint Severe Accidents / Thermal Hydraulic Phenomena, Date to be determined (Fall), pethesda, MD (Houston).
The Subcommittees will continue the discussion of the technical positions on severe accident issues for future plant designs.
The topics of basemat penetration and direct containment heating will be discussed at this meeting.
Attendance by the following is anticipated:
Kress Shewmon Catton Ward Davis Kerr Lindblad Lee Michelson Dhir m,-
+
APPENDIX IV MINUTES OF THE 393RD ACRS MEETING JANUARY 7-9, 1993 LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE
-[ NOTE: Some of the materials listed may have been provided for ACRS Internal Use Only or may contain proprietary Information) tLEETING NOTEBOOK Replacement of Analoa Instrumentation With Diaital Instrumentation Agenda Project Status Report Proposed Generic Letter:
Analog-to-Digital Replacement: Under the 10CFR50.59 Rule, FRN Vol. 57, No.158, August 14, 1992 Letter from William Rasin NUMARC for David Meyer, dated September 14, 1992, re: Industry Comments on NRC Draft Generic Letter, " Analog to Digital Replacement Under the 10 CFR 50.59 Rule,"
Letter from P. M. Beard Florida Power Corp., for Chairman Selin, dated
?
October 23, 1992, re: Analog to Digital Replacements, [with attached letter)
Letter from James Taylor for P.M. Beard, dated December 9, 1992, re:
Comments related to 10CFR 50.59 as applied to Analog to Digital Replacements Memorandum for Harold Lewis from Stewart Long, dated December 14, 1992, re: Status of NRC's Generic Letter on Analog to Digital I&C Conversions Key Policy Issues for Advanced Reactor Desians Tentative Schedule Status Report Attachments I and II:
Draft SECY-Paper: Issue Pertaining to the Advanced Reactor (PRISM, MHTGR, and PIUS) and CANDU 3 Designs and their Relationship to Current Regulatory Requirements [ Prepared for Internal Committee.
Use]
SECY-92-393, " Updated Plans and Schedules for the Preapplication Reviews of the Advanced Reactor (MHTGR, PRISM, and PIUS) and CANDU 3 Designs," dated November 23, 1992 Reactor Operatina Experience Agenda Project Status Report NRC Information Notice 92-71 " Partial Plugging of Suppression Pool Strainers at a Foreign BWR," dated September 30, 1992 Memorandum for Thomas Murley from Ashok Thadani, dated October 19, 1992, re: Program Approach to Resolution for Sump Clogging Faxed copy for Mats Sjoberg Stockholm, Sweden from Bob Dennig, dated September 15, 1992, re: IRS Report 1294.00 Faxed copy for Mats Sjoberg, SKI, Stockholm from Bob Dennig, dated September 17, 1992, re: Questions on Barsebeck 2 Event Note to Ashok Thadani from' J. Kudrick, dated September 18, 1992, re:
Insights on the Sump Screen Clogging Event NRC Information Notice 92-71, dated September 30, 1992 BWR Owners Group Primary Representatives, dated September 30, 1992, re:
Survey to Respond to NRC Questions Regarding Piping Insulation I
..-4,
=.
w 2
Letter for Ashok Thadani from C. Tully, dated October 14, 1992, re: BWROG Survey Results SECY-85-349 Resolution of Unresolved Safety Issue A-43, " Containment Emergency Sump Performance," dated October 31, 1985 Regulatory. Guide 1.82, revision 1,
Water Sources for. Long-Term Recirculation Cooling Following a loss-of-Coolant Accident, November 1985 ACRS letter from D. Ward, to W. Dircks, dated September 16, 1985, re: ACRS Review of Proposed Resolution for USI A-43 and Regulatory Guide 1.82, Revision 1 Generic Issue 120. Online Testability of Protection Systems Agenda Project Status Report Memorandum for T. Speis from R. Bernero, dated August 5,1985, re: Regitest-for Prioritization of Potential Generic Issue per Office Letter #40 [with 1
enclosures]
Performance Indicator Report Tentative Schedule Status Report Proposed SECY: " Performance Indicator Program - Peer Group and Operating-Cycle Phase Enhancements, " Received from AE0D on December 22, 1992 a
[Provided For Internal ACRS Use Only]
Atomic Safety and Licensina Board Panel Activities Tentative Agenda Status Report ASLBP Section from the 1991 NRC Annual Report ASLBP Organization Chart of January 31, 1992 Membership Listing of the ASLBP t
ACRS MEETING HANDOUTS AGENDA DOCUMENTS ITEM NO.
6 Generic Issue 120. Online Testability of Protection Systems I
1.
Technical findings Related to Resolution of Generic Safety Issue 120' Online Testability of Protection Systems, NUREG/CR-5916, pp.1-70 2.
Excerpt from NUREG-1366, Improvements to Tech Spec Surveillance -
Requirements, pg.71 i
7.0 3.
NRC Procedures for Incident Investiaation Memorandum for ACRS Members from D. Coe,-dated December 24, 1992, re: Individual letter from an ACRS member to the NRC Commissioners, with SECY-92-413 attached, [ Prepared for Internal Committee Use) i 12.1 4.
Future Activities - Multilateral Meetina -
5.
Telefax to Fraley/Quittschreiber from Candeli/RSK-GS, dated 1/7/93, re: Multilateral Meeting RSK/GPR/ACRS/NSC 6.
Letter for Cogne from P. Shewmon, dated November 17, 1992, re:
9/17/92 letter to David Ward 7.
Memorandum to Addressees from R. Fraley, dated October 29,1992, re:
ACRS Meeting Dates for Calendar Year 1993 8.
Memorandum for ACRS Members from R. Savio, dated January 7,1993, re: Future ACRS Activities - 394th ACRS Meeting February 10-13, 1993
)
la
.3 M
14 Reconciliation of ACRS Comments and Recommendations 9.
Letter for David Ward from James Taylor, dated December 2,1992, re:
SECY-92-287, " Form & Content for a Design Cert. Rule" [with attachment]
10.
Letter for Paul Shewmon from James Taylor,. dated December 8,1992, re: Maintenance Rule [with enclosures]
11.
Memorandum for Edward Jordan from Eric Beckjord, dated November 10, 1992, re: Resolution of issues identified by ACRS,. CRGR, and OGC, Draft Regulatory Guidance to implement the Maintenance. Rule, 10
. CFR50.65 [with enclosures]
12.
Letter for Paul Shewmon from James Taylor, dated December 10, 1992, re: Environmental Qualification for Digital Instrumentation and Control Systems [with enclosure]
13.
Letter for Paul Shewmon from James Taylor,- dated December 16, 1992, i
re: Comments on the Staff's Draft Commission Paper on Risk-Based-Regulation [with enclosures].
.}
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