Text

Summary of ACRS 338th Meeting on 880602-04 in Washington,Dc. Agenda,880531 Fr Notice,List of Attendees,Future Agenda & List of Other Documents Received Encl
	ML20206B145
Person / Time
Issue date:	06/02/1988
From:	; Advisory Committee on Reactor Safeguards
To:	; Advisory Committee on Reactor Safeguards
References
	TASK-A-17, TASK-OR ACRS-2584, NUDOCS 8811150350
	Download: ML20206B145 (43)
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IABLE 0F CONTENTS 111HUTES OF Tile 338TH ACRS MEETING gg Il Y[

JUNE 2-4, 1988

1. Chairman'sReport(0 pen)........................................ 1 II. Standardi;:ation of Nuci ea r Plants (0 pen) . . . . . . . . . . . . . . . . . . . . . . . . 1 III. Emergency Preparedness Rule (0 pen).............................. 4 IV. Metal Components (0 pen)......................................... 5 A. Quality of Fasteners........................................ 5 B. In-Service Inspection of BWR Shell Welds.................... 5 C. Erosion-Corrosion of Pipe................................... 6 D. Boric Acid Corrosion....................................... 6 V. World Association of Nuclear Operations (0 pen) . . . . . . . . . . . . . . . . . . 7 VI. US!A-17,SystemsInteractions(0 pen)........................... 8 VII. Proposed Revisin of 10 CFR 20. "Standards for Protection AgainstRadiation,"(0 pen)....................................... 9 VIII. Executive Sessions (0 pen / Closed).................................. 10 A. Subcomi ttee Reports (0 pen) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10

1. Advanced Boiling Water Reactors (0 pen).................... 10

2. Regional Programs (0 pen)...................o............. 11 B, Reports, Letters and Necoranda (0 pen).........,............... 1? r

1. Proposed Priority Ranking of Generic Issues: Fifth Group., 12

2. NRC Research Related to Heat Transfer and Fluid Transport ir Nuclear Power P1 ants................................... 12

3. NRC Proposed Rule on Early Site Permits, Stardard Design Certification, and Combined Licenses for Nuclear Power Reactors.................................................. 12

4. The Babcock & Wilcox Owners Group Safety and Performance Improvement Program....................................... 1? ,

S. Proposed Revisions of 10 CFR 20 "Standards for Protection A ga i n s t ' ad i a t i o n " . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

6. Rulew k'nj on Emergency Planning and Prepareoness......... 13

7. Inservic., Inspection of Eciling Water Reactor Pressure Vessels................................................... 13

8. USI A-17. "Systems Interactions in Nuclear Power Plants".. 13

9. Issuana of NUREG-1150.................................... 13 l

8911150350 000604 PDR ACRS b

2584 PNU \

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C. Other Comittee Conclusions (0 pen / Closed)

1. Advanced Reactor Designs (0 pen)........................... 13 [

2. Important Safety Related Issues (0 pen).................... 14 t

3. Intern 6tional Conference on Quality Meeting (0 pen)........ 14 t

4. Fourth Regular Bilateral Meeting on Nuclear Regulatory Matters (C1osed).......................................... 15

, 5. Priori +'ntion of Generic Issues (0 pen) . . . . . . . . . . . . . . . . . . . 15 ;

D. Fu ture Ac tivi ti es (0 pen) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

1. Future Agenda............................................... 15

2. Future Subcomittee Activi ties . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Attache.ent A - Official Use Only (VIII.C.4) p t/e h l Fo/r? E 4 6.)f ,

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iii APPENDICES MINUTES OF THE +

, 338TH ACRS MEETING JUNE 2-4, 1986

!. Attendees II. Future Agenda 4

III. Future Subcomittee Activities

.IV. Other Documents Received J

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. Federal Register / Vd. S3, No.104 / Tuesday, May 31,1968 / N; tic:s Qh / 19tD1 J.) k

. . NUCLEAR Rt.'GULATORY With regard to potential For the Nedew Repletery Comminion.

COkMISSION nonradiological impacts, the proposed Daniel R. Muhe, change to the TSa involves systems A cting Director, Project Directore ne Ill-!

[ Docket Nos. 50-282 and 50-306) located within the restricted area as Division of Aeoctor Pro /cets 171. IV. Pt*

l defined in to CFR Part 20. It does not Specia/ Pro /cct.s.

Northern States Power Coa Environinental Assesament and effect n nradiological plant effluents [m Doc. SS-12073 filed be-M a 45 aml Finding of No Significant impact and _has no other environmental irnpact. sa.umo coot rse es l

Therefore, the Commission cx>ncludes The U.S. Nuclear Regulatory that there are nn significant .

Commission (the Commission)is nonradiological environmental impacts dvisory Committee on Reactor c:nsidering issuance of amendments to associated with the proposed Safeguards; Revised Meeting Agenda racihty Operating Ucenses Nos. DPR- amendment?

42, and DpR-60, issued to Northern The Notice of Consideration of In acc rdance with the purposes of St tes Power Corrpany (the licensee), Issuance of Amendment and sections 29 and 182b. of the Atomic for operation of the Praine Island Opportunity for Hearing in connection Energy Act (42 U.S.C. 2039,2232b), the Nuclear Generating Plant, Units Nos.1 with this action was published in the - Advisory Committee on kenetor and 2, located in Goodhue County, Federal Register on March 25,1988 (53 Safeguards will hold a meeting on June Minnesota. FR 9832). No request for hearin8 or W .198 in Room 1m 1717 H Strnt l go, g'* NW., Wa shington, DC. Notice of this Environmental Assessment t ntervene was filed meeting was published in the Federal

{'l! this o identification of Proposed Action Register on May 18,1988.

Alternative to the Pity >osed Acc.an Tha proposed amendments would Thunday, June 2,1988 revise the Technical Specifications (T3s) Since the Commission concluded that

&Jo o m -N5 o m.r Comments by t ch nge the protective instrumentation there are no significant environmental ACRS Choitrnen (Open)--ne AC'RS setting for the automatic reactor trip effects that would result from the prop sed action, any alternatives with Chairman will report briefly regardmg associated witri high flux, power range items of cunent interest.

nmentalimpacts (low setpoint) from equal to or less than 25% of rated power to equal to or less eqjl[ryat$ ,

a 45 a.m.445 o m.r ECCS Evoluotion than 4% of rated power.This The principal altarnative would be t Afodels (Open/ Closed)-Review deny the requested amendment. This analytical models proposed for instrumentation settmg applies only for Westinghouse PWR upper plenum reactor sts* tup protection. would not reduce environmental Th2 proposed action is in accordance impacts of plant operation and would injection systems for two-loop nuclear with the licensee's application for result in reduced operational flesibility. pg, am:ndment dated November 3,1987. Pod ns of this session willbe dosed Alternative Use o/ Resources as required to discuss Proprietary The Needfor the Pmposed Action This act.on does not involve the use of Information applicable to the models The proposed change'to the TSs is any resources not previously considered being proposed.

required to eliminate the potential of in the Final Endronmental Statements J0W o.m.-Jf;00 0.m.:Standarda.ouon scr:mming the reactor unnecessanly at related to the Praine Island Naclear of A cclect Picots (Open)-Driefmg acd '

low power levels (i e., approximately Generating Plant dated May 1973. discussion of proposed NRC rule 33g)- regarding standardnation of nudear Agencies and Persons Consul:ed power plants, EnvironmentalImpacts of the Proposed The Commission's staff reviewed the !! W o.tn.-!:t10 coon:Internatioval Action licensee's request and did not consult Afeetmss Regarding Nuclear Power

%) Commission has completed its other agencies or persons. Pro / roms (Open/ Closed)-Report of evaluation of the proposed revision to ^*' '*" Y

tha Technical Specifications. ne noding of No Significant Impact Planning Meeting for International proposed revision would change the The Commission has determin*d not Conference on Quality, held on May to, high flux. power range (low setpoint)in to prepare an enytronrcental trepact 1988 and report on Regular Bilateral Specification 2.3.A 1.b to read statement for the proposed li:ense Meeting on NucJear Regulatory Matters.

"' ' ' <40% of rated power' rather than amendment. Portions of this session will be closed

"' ' ' <25% of rated power." nis Based upon the foregoing to discuss information provided m change would apply for low power environmental assessment. we condude confidence by a foreign source.

eperations. Smce the evaluation that the proposed actica will cot have a J Wp.m.-Jc45 p.m. Emeryency d;monstrates that the plant does not sigmficant effect on the quahty of the P!cnnms (Open)-Driefmg regarding neced the acceptable thermal Linuts, human environment. proposed final NRC rule on emergency th] proposed change does not increase For further details with respect to this preparedness in the victnity of fuel cycle ,

th] probabibty or consequencre of action, see the application for facihties and other radioactive matenal accid:nts. no chaneen are bems made in amendment dated November 3, tott7, licenses and for low-power operations the types of any effluents that may be which is available for pubbe inspection of nuclear power plants.

reinsed offsite, and there la no at the Commission's Public Document I f5 p.m -230p m.r Metallurgicn/

significant incre ese in the allowable Room,171711 Street NW Washtngton. Considerations (Open)-DrieIm' g and individual or cumdatave oaupational DC, and at the Technology and Scaence discussion regardmg the quahty of r:di: tion exposure. Accordmgly, the Department. Mmaeapolis Pubbe Ubrary. fasteners used in nuclear plants and Commission condudes that this 300 Nicollet Mall Mmneapobs, penodic inspection of BWR reactor /

proposed action would result in no Minnesota 55401. pressure vessels.

sigmficant radio logical environmental Dated at Rodvite. Maryta . ', this D-d day 0 45p m.-4:15p m.: Adranced impict. of May tea. Reactors (Open)-Discuss proposed

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.' 19632 Federal Register / V 1. 53, Nr.104 / Tuesd2y, M y 31,1968 / Notices meeting and the 337th ACRS mzting / Date: May 25,1986.

ACRS report / recommendations (May 5-7,1988). John C. itople, regarding regulatory requirements for k:y design iestures of advanced ges~ f:Mp.m.-tJ0p.m.: ACRS A dvisory committee Mancgement officer.

cooled and liquid.rnetal cooled nuclear Subcommittee Activities (Open}-- (FR Doc. so-12114 Filed F27-M 8.45 amj power plants. Reports and discussion of the status of auma coos riemu 4.15p.m.-600p.ma Bobcock c kl assigned subcommittee activities Wi/cox Nuclear Power Plant 4 spe n}-- including NRC regional activities, Discuss proposed ACRS reps on the intemational meeting on operational (Docket No. 50-440l safety reassessment of D&W nudear safety experience, and bilateral meeting power plants by the B&W Owners on significant operational events and Cleveland Electric illuminating Co. et Croup. consideration of severe accidents, al.; Consideration of lasuance of Amendment to Facility Operating Friday. juna 3,1983 Procedures for the conduct of and participation in ACRS meetings were License and Proposed No Significant Hazards Consideration Determination AJO o.m.-forf 5 a.m. Prioritization of published in the Federal Register on Ceneric /ssues (Open)--Discussion and and Opportunity for Hearing Oc.bober 2,1987 (51 FR 37241). In comment regarding the proposed ,ccordance with these procedures, oral The U.S. Nuclear Regulatory prioritization of several sew generic or wntten statements may be presented Commission (the Commission) is

' 8 8 " ' ** by membeis of the pub!!c, recordings considering issuance of an amendment 10 J0 0 m.-f f:30 0 m> Reactor will be permitted only during those Opes;fions (Open)-Driefing regarding to Facility Opera'ing Ucense No. NPF-portions of the meeting when a 58 issued to the Cleseland Electric proposed International Organization of transcript is being kept, and questions illuminating Company (CEI), the React r Opuntors. may be asked only b members of the 11.J0 0 m.-1200 noon: Future Committee, its consuftants, and Staff. Duquesne Light Company, the Ohio Activities (Open)-Discuss anticipated Ed' son Company, the Pennsylvania Persons desiring to make oral Power Company, and the Toledo Edison subcommittee activities and items statements should notify the ACRS proposed for consideration by the full Company (the licensees) for operation of Executive Director as far in advance as the Perry Nuclear Power Plant. Unit No.

Conw h practicable so that appropriate 1, located in Lak e County, Ohio. The f$0p m.- :30p.m. Systems' arrangements can be made to allow the Interactions (Open)--Briefing regarding licensees

application for amendment necessary time during the meeting for w as dated Apnl 4,1988.

the proposed resolution of USl A-17, such statements. Use of still, motion stems Interactions in Nuclear Power The amendrnent would modify the picture ud television cameras dunna Technical Specifications fTS) on page 1-this meeting may be limited to se!ected 2 J p m.-300 p.m.: ACRS e a ma at ng ri f n di c i n rega d n the the time to be set aside for this purpose making it consistent with the status of the PDA review for the may be obtained by a prepaid telephone requirements of Generic Lctter 83-43 Advanced Boiling Water Reactor dated December 19,19&1.

call to the ACRS Executive Director, hit. '

J 15 p.m.- 4:15 p m.: Radiooctive Raymond F. Fraley, prior to the meeting. Another proposed change is a deletion Effluents (Open)-Driefing and In view of the possibility that the of the organizational charts (Figures osed changes schedule for ACRS rr.eehngs may be 6 21-1 and 6 2 2-1), and the addition of discussion in 10 CFR Part regarding to,"Stanpro [ards adjusted by the Chairman as necessary statements in section 6 2.1 to Protection Against Radiation for to f acihtate the conduct of the meeting, co'npensate for the organization chart

.f.15 p.m.-J.15 p.m.: Preparation of deletions. These changes were persons pisnning to a9end should check ACRS Reports (Open) Discuss submitted in response to gs.idance with the ACRS Execative Director if contained in Genene Letter su;6 dated proposed ACRS reports on thermal. such restheduling would result in major hydraulic phenomena research htarch 22,1988. As such. these changes incons entence.

cctivities, to delete organization charts are 515 p.m.-J.45 p m.:New Afembers I have determined in accordance with considered administrative, subsection 10(d) Pub. L 92-M3 that it is (Closed}-Discuss status of appointment necessary to close portions of this An additional proposed change to the of pruposed mernbers and the TS is to delete the esception to TS meeting as noted abose to discuss quahfications of candidates being section 6.3.1 for the Senior Operations considered for nomination. information the release of which would represent a clearly unwarranted Coordinator as this exception is no This session will be closed to discuss invasion of personal pnvacy (5 U S C. longer required, information the release of which would 552b(c)(6)). Propnetary Ir. formation The proposed amendment would also represent a clearly unwarranted invasion of personal privacy, applicable to the facilny beias discussed modify TS 6 512. 6 5.1.3. and 6.51.5 to (5 U S C. 552b(c)(4)) and Prmleged and reduce the size and change the 5.45 p m.-dJ0 p.m.:ACRS Proctices membership requirements for the Plant classified information from a foreign

, and Procedures (Open)--Discuss Operations Resiew Committee (PORC) proposed cojoining of ACRS aource (5 U S.C. 552b(c)(4)).

Further information regarding topics The definition of QUORUht in TS 6 51.5 subcommittees and procedures would also be changed to reflect the to be disensed, whether the meetma regarding members' participation in above changes. The proposed meetings which are not sponsored by has been cancelled er rescheduled, the Chairman's ruhng on requests for the amendment would further modify TS the ACRS. 6 5.16.i and n and 6.5.3.1 f, deleting the opportunity to preser-t oral a,tatements 2 Saturday, Juri. A 19ee and the time allotted can be obtamed by requirement for the PORC to submit a prepaid telephone call to the ACRS recommended changes to the Nuc! car a fo a.m.-12J0 p m.: Preparutiott of ACRS Reports (Open)-Discuss Executive Director, hit. Raymond F. Safety Review Committee based upon Fraley (telephone 202/634-3265), PORC reviews of the Secanty Plan.

proposed ACRS reports to NRC regardmg items considered during this between 815 a m. and 5 00 p m. Secunty Contingency Instructmns.

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N:ticesf ,, "N W'18363

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Fed:rd Regist:r./ Vol. 53, No. 99 / M:nBayi May 23, 1988 /

condition ready for decommissioning not be' evaluated.%e principal Westinghouse PWR upper pisnum following an accident considering the alternative to the exemption would be to injection systems for two-loop nuclear current operaticaal limit. Granting the require the licensee to carry 1.06 billion power plants.

exemption request relieves the licensee dollars of on site primary property 10.M o.m.-72W noon Consideration from the unnecessary financial burden damage insurance. Such an action of Severe Accidente (Open)-Review -

cf carrying insurance coverage of 1,06 would not enhance the protection of the and comment regarding proposed NRC billion as required by to CFF 50.H(w)(1) environment. plan to impicment NRC policy statement until Seabrook Station receives an regarding savece accidents.

operating license which allows the Alternative Use of Resources J.Wp m.-f;45 p.m.: Emergency reactor to go critical or operate at any This action does not invoh e the use of Planning (Open)-Briefing regarding power level. any resources not considered in the proposed final NRC rule on emergency Final Environmental Statement for the preparedness in the vicinity of fuel cycle Environmental /mpacts of the Preposed Seabrook Station. facilities and other radioactive material Action licenses.

Agencies and Persons Consv/ted The proposed esemption affects only 1:45P,m.-2:Jop.m.: Afetallurgical the amount of on. site primary property The NRC staff reviewed the licensee's Consideratirns (Open)-Briefing and dimate insurance coverage and does request and did not consult other discussion regardira the quality of not affect the manner of normal facihty agencies or persons. fasteners used in nuclear plar.ts and operation or the risk of facility Finding of No Significant impact periodic inspection of DWR reactor cccidents. While the change in pressure vessels, insurance coverage may affect the The Commission has determined not to prepare an environmental impact 2:45 9.m.-4:15 p.m.: Advanced financial arrangements of the licensee Reactors (Open)-Discuss proposed and have some economic consequences, statement for the proposed esemption.

Based upon the environmental ACRS report / recommendations the possibihty that the environmental regarding regulatory requirements for impact of lict.nsed actisities would be assessment, the NRC staff concludes that the proposed action will not have a key design features of advanced gas.

altered by changes in insurance cooled and liquid metal cooled nuclear coserage is extremely remote The staff significant effect on the quality of the h:s determined in the exemption dated human environment, power plants.

May 11,1988 that a reduction in the For further details with respect to thF 4:15 p m -amp m.: Babcock and proposed action, see the licensee's Wi/cox Nuclear Power P/ orts (Open)- .

emount of required on. site damage insurance, from t.00 bilhon dollars to letters dated October 1.1987 and Discuss proposed ACRS report on the February 29.1988 These letters are safety reassessment of DAW nuclear 6:0 million dollars is commensurate with the clean up cost associated with a available for public inspection at the power plants by the B&W Owners postulated accident while the reacter is Commission's Public Document Room, Group.

maintained in a shutdown. subcritical 171711 Street NW., Washington. DC and Friday, June 3,1968 i.

configuration. Thus. the reduced at the Exeter Public 1.ibrary, founders cta etage authorized by the proposed Park, Exeter, New Hampshire 03333. 3 30 a m.-mf 5 a.m.:Prioritiration of esemption is sufficient to fund clean up Ceneric /ssues (Open)-Discussion and Dated at Rockvtlle Mar >tini this 7th dey ot radi%st impacts esser. lated with comment regarding the proposed of M23, ign.

any accidents posts. lated with the for the Nucleat Regulator > commissmn. prioritization of several new generic reactor maintained in a rub ntical m g g,,,,,,, issites.

cond: tion. In addition. the csemption in p ,,3 g- 1030 a m.-7 f.30 a m.: Reactor questinn would not autheyire g .

g g. , Operations (Open)--Driefing regarding construct.un er operat,en. w ould nnt g ,,c ,,, g g ,,, proposed international Organization of authorite a change in licensed activities Reactor Operators, nor effect changes in the permitted types (FR Doc. 8A-11464 Fded 5-sas. a 45 aml

"'8 C* 8 " JJ 30 o m.-13.m noon: future or amounts of radiological effluents. gegjyities (Open}-Discuss anticipated post. accident radiological releases will subcommittee actmties and items net differ from those determined Advisory Committee on nesctor pr@osed for consideration by the full previously. and the proposed esemption Safeguards; Meeting Agenda Committee, does not otheruise affect facihty ,_m p , _,;3g , ,_, gy,,,,,

radiological effluents or occupational in accordance with the pumoses of /ntercetions (Open)-Dnefing regarding esposures. With regard to potential non. sections 29 and 18 b. of the Atomic " gg ^

radiologicalimpacts the proposed Energy Act (42 U.S.C. :oM :23:b). the $'y 3 [' ,'g"'

3cn b Nu esr r esemption does not affeci plant non- Ad$isory Committee on Reactor Plants'"

i radiological effluents and has no other Safeguards will hold a meeting on lane .

30P m.-J m p.m.:ACRS environmentalimpact herefore, the 2419M. in Room 1N6.1't' l{ S*reet 8" # **# 'k'*N## NP"b I Commission concludes there are no NW., Washington, DC Lta.e of this Bnefing and discussion regarding the measurable radiolwical or non. meeting was pub!ished in the Fedral status of the PDA review for the j radiological ensironmental irrpact s Register on April 18,1988. Advanced Doding Water Reactor, assxlated with the proposed 3:15 p m.-4:!$ p m.: Radioactive esemption.

N*'*0*Y' 5 *** E' 1968 8 30 a.m -A 45 a m.: Comments by Ef!!uents (Open)-Briefing and Ahernatne to the Propased Actwn ACRS Chairman lopenkne ACRS discussion tegardtna proposed changes Since the Commission concluded that Chairman will report bnefly negarding in to CFR Part 20. "Standards for items of current mterest. Protection Against Radiation."

there is no measurable enuronmental impact assoctated with the proposed 8 45 a m -9 45 a m.: ECCS Evoluotion 415 p m.-515 p m.: Preparation of esemption, any altematis es with equal Afadels (Open/ClosedHReview ACRS Reports (Open)~ Discuss or greater environmentalimpacts need analytical models proposed for proposed ACRS reports on thermal.

I 18364*

Federal Resister / Vd. 53. N2. 99 / M:nday, May 23, 1988 / N:tices hydraulle phenomena research represent a clearly unwarranted of the allowable value In Table 3.7.5 of I invaalon of personal privacy (5 U.S.C. 13 section 3.7.12. and the measured acuvities, value exceeded 75% of the allow able 3:25 p.m.-J:45 p.m. New Afembers $52b(c)(6)] and Proprietary Informadon (Closed)-Discuss status of appointment applicable to the facility being discussed exceeding 75% value in Junedif'eren'lal of allowable 1987 and in 10an cf proposed members and the (5 U.S.C. 552b(c)(4)). settlement between these two points Fur'.her information regarding topics qualifications of candidates being was submitted to the NRC in 1981 and in to be discussed, whether the meeting conaldered for nomination. has been cancelled or rescheduled, the August 1967 in accordance with the NA-5 45 p.mmop.m.t ACllS Pxetices 1&2 TS. The August 1787 report is and Pmcedures (Open)-Discuss Chairman's ruling on requests for the opportunity to present oral statements provided as part of the licensee's March propoted procedures regarding and the time allotted can be obtained by 10.1988 submittal, members' participation in meetinas The primary concern of the which are not sponsored by the ACRS. a prepaid telephone call to the ACRS I Executive Director, Mr. Raymond F. differential settlement between the SB Saturday, W L 1988 Fraley (telephone 202/624-3265). and the N A-2 htSVit is the effect on the 3 30 a.m.-22:30 p,m.: Preparotion of between 8:15 a.m. and 5.00 p m. four buried service water linea running ACRS & ports (Open)--Discuss Date: May tr, tpaa between the two structures. ne code John C. We, abwaW mn In N uh waW te a g ema e n i e during this lines for differential settlement Advisory Committee Afan,esement Oficer. condition is 45.000 pounds per square meeting and the 337th ACRS meeting (11t Doc. 88-11497 Filed 5-:o-se; e 45 em]

(May 5-7,1988) inch (psi). As atated in the NA-la2 TS. ;

1:Jop.m.-2 Jap.m. ACRS emma com riews.a critical differential settlem:nt is the i

Subcommittee Activities Open)-- downward movement of the SD with a rnpect to b MM. he rds d an ss ned sub utte act v t s '8 8 including NRC regional activities, Virginta Electnc and Power Co4 d sregar ng zu eI ccur cies. there international meeting on operational Cono6deration of Isauance of has been negligible additional safety experience, and bilateral meetin8 Amendments to Facility Operating settlement of the SS since 1981, on signiticant operational events and ucenaea and Opportunity for Hearing he differential set'lement limit of consideration of severe accidents, 0.03 feet in the TS was based upon an he U.S. Nuclear Regulatory Procedures for the conduct of and estimate of future differential settlement participation in ACRS meetings were Commission (the Commission)is between points 117 and 113. The service considering issuance of amendments to water pipe stress analysis shows that published in the Federal Register on October 2,1987 (51 FR 37241). In Facility Operating Ucense Nos. NPF-4 considerabls margin exists before code-accordance with these procedures, oral and NPF-7 Issued to the Virginia Electric and Power Company (the allowable stresses would be exceeded or written statements may be presented and, therefore, the differential by members of the public. recording will licensee), for the operation of the North settlement of the SD with respect to the be ermitted ont during those portions Anna Power Station. Units No.1 and NA-2 htSVit has had no significant of e meeting w en a trans.cri t is being No. 2 (NA-la2) located in touisa impact on the service water pipes or on kept, and questions may be as ed caly County, Virginia plant operabihty.

ne proposed kmendments would he proposed changes would revise by members of the Committee,its consultants, and Staff. Persons desiring modify the NA-la: TS, section 3.7.12, Table 3.7.5 to delete components which the allowable value of differential to make oral statements should notify settlement between the SD and the NA-were replaced dunns the Service Water the ACRS Executive Director as far in Reservoir Improvement Project and to : MSVH from o.03 feet to 0.047 feet. This advance as practicable so that S alue. 0 G47 feet, corresponds to a stress appropriate arrangements can be made change the allowable differential of 44.176 psiin the service water imes.

to allow the necessary time during the settlement between Unit 2 Main Steam which is still below the code. allow able meeting for ench statements. Un of still, Valve House and the Service Duilding stress of 45.000 psi.ne reportable motion picture and television camerns (SD). threshold of 75% would still be dunng this meeting may be limited to The proposed changes to the NA-la maintained in the NA-la2 TS.

selected portions of the meeting as TS section 3.7.12. Table 3.7.5 woeld Pnor to issuance of the proposed i determined by the Chairman, delete the settlement monitoring license amendmen's, the Commission Information regarding the time to be set requirentais for service water lmes will have made fi.idmgs required by the aside for this purpose may be obtained which were removed from service and Atomic Energy .sct of 1954. a s amended by a prepaid telephone call to the ACRS replaced with new lines cormecting the Service Water System to the new (the Act) and the Commission's F.necutive Director, hit. Rapnesi P. regulations.

Fraley, prior to the meeting. In view of Service Water Valve House and spray headera during the Service Water Dy June ia,1968. the licensee may file the possibthty that the schedule for a request for a hearing with respect to ACRS meetings may be adjusted by the Reservoir Improvement Project in 1987.

his replacernent was appros ed by the issuance of the amendment to the Chairman as neccesary to facilitate the subject facibly operating license and conduct of the meettryt persona NRC in license Amendrnents 91 and 76, any person whose interest may be planning to attend should check with the respectively, on March 27,1987. affected by this proceedmg and who he proposed changes would also

. ACRS hecutive Directoe if such wishes to partWpate as a party in the rescheduling would result in major revise the limit for diUerential- proceeding must file a written request settlement between points 117 and 113 inconvenienza. for a heanns and a petition for leave to I beve determined in accoedance with of Table 3.7.5.no differential intervene. Requests for a heanns and subsection 10(d) Pub. L 92-463 that it is settlement between settlement petitions for leave to mtervene shall be necessary to close portions of this monitortna points 117. the SB. and 113.

filed in acc<,rdance with the meetmg as noted abose to discuss the NA-2 Main Steam Valve Houn information the release of which would (MSVH). has frequently approached 75% Commission's "Rules of Practice for

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. REVISED - REFC.",TED SFRVICES NFEOF0 WHERE BRACKETED e .

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'o UNITED 6TATES

!" . 'fga NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS

' "'[.)n[I o, W ASHINGTON. D. C. 20665 Revised: June 1, 1988 SCHEDULE AND OUTLINE FOR DISCllSSION 338TH ACRS MEETING JUNE 2-4, 1988 WASHINGTON, D.C.

Thursday, June 2, 1988, Room 1046, 1717 H Street, N.W., Washington, D.C.

40

1) 8:30 - 8:AF A.M. Chairman'sComments(0 pen) 1.1) Opening remarks (WK) -

1.2) Itemsofcurrentinterest(WK/RFF) do 8:45-

19) 8:45 - 9t00 A.M. Safety Related issues (0 pen) 19.1) Discuss proposed hierarchical structure regarding important safety-related issues identified by ACRS memoers (CPS /SD)

( 6:45' os- ~

3) 3400 - 11:00 A.M. Standardi:ation of Nuclear Plants (0 pen)

(9730-St45 - BREAK) 3.1) Report of 'CRS Sub: wnittee Chairman

/r:ro 10# regarding proposed NRC rule on standardized nuclear power plants '

(CJW/HA) j 3.2) Meeting with representatives of NRC Staff os to U

4) 11:00 - 12:00 Noon Reports of International Meetings Regarding Nuclear Power Programs (0 pen / Closed) 4.1) Planning meeting for International Conference on Quality (May 10,1988)

(CPS /EGI)(0 pen) 4.2) Fourth Regular Bilateral Meeting on Nuclear Regulatory Matters on Mry 12-18, 1988(Closed)(DAW /PGS/EGI)

(Note: Portions of this session will be closed to discuss information provided in confidence by a foreign source.)

to 45- '

12:Q(T- 1:00 P.M. LUNCH I

4

._.--.-_--.---__..______.,7 _- - , - - - . _ . , . , _ -, . _ , , , . - , _ --

, . . - - - - - . . - + - ,

~

338th ACRS Meeting Agenda !

(

I 3~ M ~

5) 1:96 - 1:45' P.M. # mergency E Planning (0 pen) 5.1) Report of the NRC Staff regarding proposed NRC rule on emergency preparedness in the vicinity of fuel cycle facilities'and other radioactive material licenses, and for low-power operation of nuclear power plants (DWM/EG1)

S.2) Meeting with representatives of NRC Staff, as appropriate sr .$5'

6) 1:45'- 2:30' P.M. 'MetalComponents(0 pen) 6.1) Report by ACRS Subcomittee chairman regarding the quality of fasteners in !

- nuclear power plants and periodic inspection of BWR reacter pressure t vessels (PGS/EGI) 6.? Briefing by representatives of NRC Staff, as appropriate

-n 50 .'

{)

! 2 *.3 0' - 2:45'P.M. BREAK .

( 7) f6 10 2:,45'- 4:)5 P.M. Advanced Reactors (0 pen) 7.1) Discuss proposed ACRS report /recomenda-tions regarding regulatory requirements for key design features in advanced J e - 9 .* ; C i e " '- gas-cooled and liquid tretal-cooled i nuclearpowerplants(DAW /MME) ;

20 l o,

8) 4:)5 - 6:20 P.M. Babcock & Wilcox Nuclear Power Plants (0 pen) ,

6.1) Coments by ACR5 Subcomittee Chaiman regarding safety reassessment of B&W l nuclear plants by the B&W Owners Group !

(CJW/RKM) :

' 8.2) Meeting with representatives of NRC Staff I and B&W Owners Group, as appropriate Friday. June 3, 1988, Room 1046, 1717 H Street, N.W., Washington, D.C. !

r s

9) 8:30 - 10:35 A.M. Prioritization of Generic Issues (0 pen) !

9.1) Coments by ACRS Subecmittee chainnen l and designated members regarding proposed !

NRC Staff priorities for several new I genericissues(CPS,etal./SD,etal.)

9.2) Meeting with representatives of NRC l Staff, as appropriate ;

r .: <-

I 10:}E - 10:30 A.M. BREAK r

7

. 338th ACRS Meeting Agenda (

$5 f*ReactorOperations(0 pen) 10)10:30- 11:30 A.M. < , . ,

t10.1) Briefing by Stanley J. Anderson, INPO, ,'

regarding proposed World Association of Nuclear Operators (FJR/RFF) e- -

11)11:30- 12:00' Noon Future Activities (0 pen) 11.1) Discuss anticipated ACRS Subcomittee activities (MWL/RFF) 11.2) Items proposed for consideration by the full Comittee (WK/RFF) 6 12:00 - 1:00 P,M. LUNCH 2 e

12) 1:00 - 2:30~P.M. SystemsInteractions(0 pen) 12.1) Comrents by ACRS Subcomittee chaiman regarding proposed NRC plan for resolution of USI A-17 Systems Interactions in Nuclear Power Plants (DAW /MOH) 12.2) Briefing by representatives of NRC Staff

13) 2 t30' - 3:15 P.M. ACRS Subcomittee Activities (0 pen)

M 3.1) Report and discussion of the status of

[ the review of the GE Advanced Boiling WaterReactor(CM/RKM) 13.2) Report on Regional Programs Subete. Mtg.

on May 24, 1988 at Region 11 (FJR/PAB) 3:15 - 3:30 P.M. BREAK

14) 3:30 - 4:30 P.M. fProtectionAgainstRadiation(0 pen) 14.1) Report of ACR5 Subcomittee chairtnan regarding proposed changes in 10 CFR Part 20, Standards for Protection 9: 3c -.4: 4*H.hd Against Radiation (DWM/EGI) 14.2) Meeting with representatives of NRC Staff 4c Therinal-Hydraulic Phenomena (0 pen)

15) 4:)6- 5:45 P.M.

15.1) Discuss proposed ACRS report /recomenda-tions regarding NRC research related to themal-hydraulic phenomena (DAW /PAB) g:50

16) 5:45 - 6:15 P.M. New ACRS Members (Closed) 16.1) Discuss status of appointment of proposed members and qualifications of candidates being proposed for consideration (FJR/NSL)

(Note: This portion of the meeting will be closed to discuss infortration the release of which would represent a clearly unwarranted invasion of personal privacy.)

S.

...i,

) .

338th ACRS Meeting Agenda 5:50 rr ,

17) Sr!5 - 6: P.M.

ACRSPracticesandProcedures(0 pen)fACRS 17.1) Discuss proposed conjoining o .

subcomittees (CM/SD) 17.2) ACRS procedures regarding participation by members in meetings which are not theACRS(HWL/RFF) 17.3) sponsoredby(WK/RFF)

Revised NOU Saturday, June 4, 1988, Room 1046, 1717 H Street, N.W., Washington, D.C.

00

18) 8:30 - 12:30 P.M. Preparation of ACRS Reports (0 pen / Closed) 18.1) Discuss proposed ACRS reports to NRC regarding:

18.1-2) Advanced Reactors - R(gulatorf Requirements (DAW /MME) 18.1-3) B&W Safety Reassessment (CJW/RXM) 18.1-4) Coment on NRC Themal Hydraulic Research Program (DAW /PAB) 18.1-S) Generic Issues Priorities (CPS /SD) 18.1-6) Protection Against Radiation

(. (10 CFR Part 20) (DWM/EGI) 18.1-7) SystemsInteractions(tent.)

(DAW /XDH)

(Note: Portions of this session will be a

closed as required to discuss Proprietary Information applicable in the models being proposed.)

. oo evic

12:30 - .1r30 P.M. LUNCH

e t.: s # : L s-

20) 1430 - .h 30 P.M. Miscellaneous

! Complete discussion of items considered during this meeting. i i

4 l

I l

l I

r MINUTES OF THE 338TH ACRS MEE JUNE 2 4, W88 pHilFB G

The 338th meeting of the Advisory Comittee on Reactor Safeguards, held at 1717 H Street, N.W., Washington, D.C., was convened by Chairman William Kerr at 8:30 a.m., Thursday, June 2,1988.

[ Note: For a list of attendees, see Appendix 1. Dr. Steindler did not attendthereeting,andDr.MoellerwasnotpresentonThursday.]

The Chamnan said that the agenda for the meeting had been published.

He identified the items to be discussed on Thursday. He stated that the meeting was being held in conformance with the Federal Advisory Comit-tee Act and the Government in the Sunshine Act, Public Laws92-463 and 94-409, respectively. He also noted that a transcript of some of the public portions of the meeting was being made, and would be available in the NRC Public Document Room at 1717 H Street, N.W., Washington, D.C.

[ Note: Copies of the transcript taken at this meeting are also avail-able for purchase from the Heritage Peporting Corporation, 1220 L Street, N.W., Washington, D.C. 20005.]

I. Chairman's Report (0 pen)

[ Note: Mr. R. F. Frale portion of the meeting.]y was the Designated Federal Official for this Dr. Kerr introduced and welcomed Mr. James C. Carroll as a new member of the Comittee.

Dr. Kerr announced that the Advisory Comittee er Nuclear Waste will become operational on June 19, 1988. Mr. Clifford V. Smith will becene the third member of the new comittee.

Dr. Kerr announced that the ACPS office move to Bethesda, t'd. has been tentatively postponed to July 29, 1988.

Dr. Kerr pre ented a certificate and lapel pin to Mr. Raymond F. Fraley en the occasion of completion of 35 years of federal service.

II. Standardization of Nuclear Plants (0 pen)

[ Note: Mr. H. Alderman was the Designated Federal Official for this portion of the meeting.]

Mr. Wylie, Chaiman of the Subcomittee er Improved Light Water Peac-tors, said that the Subecmittee met on May 31, 1088 to review a pro-posed part of the NRC regulations,10 CFR Part 52, that would provide for the issuance of early site permits, standard design certifications, and combined constructicn pemits ano conditieral operating license for nuclear power reactors. Mr. Wylie, Mr. Michelson, and Dr. Siess were in attendance at the subcomittee meeting.

330TH ACRS MEETING HINUTES 2

i Mr. Wylie noted some of the topics of interest that arose from the l' subcommittee meeting. Under Subpart A, Early Site Permits, there are requirements for emergency planning for the site, and efforts to obtain local and Statn government agency certification in the application for early site permits.

i Under Subpart B, Standard Design Certification, the Comission has emphasized certification of essentially complete plant designs or major '

portions thereof. The certification is to be done by rulemaking. The severe accident requirements, USIs, and GSis are not factcred into the future standard plant certification requirements.

Mr. Wylie pointed out that another area of interest is the scope and level of design requirements for certification. Section 52.63 of the rule speaks to the finality of standard design certification. It speaks to the requirements placed on the NRC in imposing new requirements. It addresses the limitations or restrictions placed on the applicants for construction permits and licensees and holders of design certification in making changes and amendments. i Mr Wylie stated that a subject of considerable discussion during the !

subcomittee meeting was, what is actually certified in the standard design certification. As it is presently written, changes to anything which is included within the scope of the standard design certificatier, t can only be changed by rulemaking. This seems to be a serious problem.

Mr. Jerry Wilson, RES, remarked that he would present an overview of l where the Staff is going on certification. He listed all organizations '

that have expressed an intention of seeking standard oesign certifica-tion. Part 52 was drafted so it can be used to achieve certification of any design including those for the advanced plants. The Staff has developed a certification-by-test approach so that the advanced reactors can demonstrate that they are ready for certification via a full-sized prototype test.

Mr. Wilson noted that, for the LWRs, the Staff would rely on the existing body of regulations, plus Part 52. He remarked that the certification process would be facilitated if the Commission had a separate severe accident rulemaking for future plants prior to the design specific certification rulemaking.

There is not a complete body of regulations for non-LWRs. For each design, the Staff will have to determine which regulations are applica-ble, which are not, which will have to be modified, and which regula-tions would have to be added.

Mr. Wilson remarked that there were two approaches that the Staff could take to achieve certification of non-LWRs, preactive and reactive. in the reactive process, the review of the requirements would occur after an application has been received. The proactive process wculd occur prior to receipt of an application. The Staff is proposing a proactive approach.

338TH ACPS MEETING MihUTES 3 ,

j

, Mr. Steven Crockett. 0GC, introduced Mr. Stuart Treby, Assistant General Counsel for Rulemaking, and Mr. Martin Malsch, Deputy General Ccunsel, 4

and Mr. Dino Scaletti of NRR.

Mr. Crockett $.oted that the existing regulations have provisions for standardization. He described the existing provisions for standardi-zation by duplication, replication, and manufacturing license. Part 52 ,

does not invalidate the older provisiens for standardization.

He noted that Part 52 includes a paragraph in Appendix 0 which states i that organizations which hold final design approvals can seek Comission l 1 approval of the design by rulenaking. l l

He noted that final cedign approval represents the Staff's signoff on the design. It does not bind the Comission. It does not bind the ,

adjudication panels or the ACRS. A certification would bind all these !

bodies.

He also called attention to the provisions for early site permits, erd

for the ccmbined licen,e.

j The combined license embodies a construction permit and an operating i

license granted on the ccnditions that the plant be completed in

]

conformance with the design that was presented in the construction ,

3 permit hearing. The application for a combined license must include '

proposed inspections, tests and analyses, and acceptance criteria for

Staff use in review of the construction. The operating license is I l converted to a full license upon successful completion of those inspec- l tions, tests and analyses. !

j In response to a question, Mr. Crockett noted there was an ACRS review I

' during the conversion from a conditional tn a final operating license. l 4

Later, he said that he would havo to check that point. ;

Mr. Crockett pointed out that, under current regulations, a hearing for l a construction permit is mandatory, ard there must be an opportunity for 1

a hearing prior to an operating license. Under the proposed rule, a i hearing on the application for a license is not mandatory. .

1 !

< Mr. Crockett said that the phrase "advanced reactors" is not used in !

, Part 52. Instead, there are words to the effect "design significantly r j different from any so far built or operated." The rule calls for ;

j prototypical testing, and there 's a presumption that a full-size proto- 7

type will be tested at an isolated site. The testing criteria have not ;

been deternined as yet.

~

i Mr. Crockett discussed the provision for ACRS review in the proposed

! rule. The ACRS would review applications for early site permits and safety issues raised by the application. .The ACRS would review appli-1 cations for certification of a design and would review applications for j a ccmbined license.

1 1

.----_.---.-,_.--,,-,--..-_--____,--_------m--,-._m - - m ,-_.. - - - . - , - - , . - - - - - - - , ,

. 338TH ACRS MEETING MINUTES 4 a * * .

] ;

t !

i i Mr. Crockett noted that specific requirements are needed regarding ACRS [

review at conversion of a provisional operating license to a full :

j opers. ting license. !

j Fegarding emergency planning, Mr. Crockett noted that applicants for early site permits must contact local and State agencies on emergency planning issues. They have to document, for the Staff, what contacts l

l have been made, and make a good-faith effort to get a certification from t

] those agencies that the site appears to be amenable to ' emergency

, planning for the kind of facility described in the application. !

4

, In response to a question about the local and State agencies refusing to l certify the emergency planning, Mr. Crcckett replied that the permit l applicant would have to decide if he wanted to proceed without the ;

certification.

, l Mr. Crockett discussed scope of design. He noted that scope can be subdivided into two issues: !

j Would designs be accepted that de no+ include a balance-of-plant?

i How much detail is required on what is offered for certification?

He noted that the preposed Part 52 will allow an application for certi-

.i fication for less than a complete plant. This assumes that everything 4 cssential to safety is included in the scope of design, t

Concerning the required level of detail, Mr. Crockett said that the goal I is for the Staff to get whatever inforration is needed in order to arrive at a decision on the design. ;

}

Mr. Crockett noted that language describing detailed information consisting of design and procurement specifications, perfomance speci- I fications, and acceptance and inspection requirements will be substitut-i ed for nameplate data.

i Mr. Crockett discussed finality. He noted that the NRC can change the (

) design by backfitting af ter certification is granted. The Comission f i

1 can only backfit to remove undue risk or te bring the certification into '

j compliance with regulations at the time the certification was granted.

! Since certification is by rule, changes will have to be made through the l l rulemaking process. j i l j !!!. Emergency Preparedness Rule (0 pen) l I

(Note: Mr. E, ! {

of the meeting.]gne was the Designated Federal Official for this portion l The Committee was briefed by Mr. Michael Jamgochian, RES, on:

I

1. Emergency Preparedness Ruleraking for Fuel Cycle and Other Material I l Licensees, and I

i 1

338TH ACRS MEETING MINUTES 5 r . .

j . . - .

l

c. Emergency planning and Prepared Requirements for Nuclear Power !

j Plant Fuel Lo6 ding and Initial Low-Power Operations. ,

i With respect to item 1, it was stated that rulemaking will codify what f:

q -is now being addressed through orders. The rule is limited in application and will require emergency planning only for those facili-ties which have a potential for significant accidental impact on public

health. The number of such facilities is about 30, and all such !

j facilities already have emergency plans that fulfill the requirements of !

the proposed rule. l t

With respect to item 2, it was stated that the proposed rulemaking would !

1 require the development of limited emergency plans for nuclear power I q plants during fuel loading and ini tit.1 low-power operation. During i

these periuds, the source term is minimal and the preposed degree of r

} emergency preparedness appears commensurate with the risk. A full-scale f 1 emergency plan would be required before a plant is perinitted to operate !

j at higher power levels, j l IV. Metal Components !

i f

! [ Note: Mr. E. Igne was the Designated Federal Official for this portion i-of the meeting.1

) A. Quality of Fasteners f

Over the past year, scme NRC procurement inspections have included j the collection and testing of small samples of fasteners. This

! limited program was initiated in response to a concern by the Industrial Fastener Institute over the potential use of inferior fasteners in military and industrial applications, including j - ' nuclear power plants. Freliminary NRC test results of tests of q fasteners obtained from some domestic nuclear plants, indicate that some fasteners do not meet specification requirements for i 4 mechanical and/or chemical properties. The NRC Staff's preliminary [

! cenclusion was that there is a quality assurance problem, but that j it did not constitute any danger to the health and safety of the t l public. A congressional inquiry on this matter is engoing.

B. In-Service Inspection of BkR Shell Welds !

j fir. Warren Hezelton, hRR. briefed the ACRS. He stated that j i in-service inspection of all accessible shell welds in the reactor -

1 vessels should be performed during each 10-year interval. For l' BWRs. in-service inspection has been perfonned on a very small sample of the welds, about 5-10f of the total weld length, because [

of access difficulty. A proposed A5FE Section XI code change will essentially require 100% shell weld inspecticn at all intervals. ,

The ASME Code Se,ction XI main comittee has passed this matter by i voice vote. Mr. Hazelten stated that reasons for waiving i inspecticn of BWR pressure vessels are as follows* l I

r n.---.-,, - - - _ - . - _ , - _ . - _ - _ - - . .-'

.- . 338TH ACRS HEETING MINUTES 6

. . . o Shop and preservice examinations were perfomed, and the Irradiation effects of the pressure vessel are negligible early in plant life.

'The NRC Staff did not anticipate service-induced failure mechanisms.

The NRC Staff is rcw concerned about BWR pressure vessel integrity because predictions based on recent data indicate significant irradiation damage to the pressure vessel material. Further, recent research suggests that stress corrosion cracking or corrosion fatigue cannot be ruled out in BWRs.

The Committee supported coments on the matter of in-service inspection of shell welds of the pressure vessels for BWRs.

C. Erosion-Cerrosion of Pipe

The sudden pipe rupture at Surry-2 Nuclear Pnwer Plant spurred the industry to inspect susceptible single-phase flow piping systces for erosion-corrosion mechanisms that reduce the wall thickness in piping systens. Plant insper.tions indicate that, of the 54 ruclear power plants first inspected,19 plants had significant pipe wall thickness reductions, and in some cases, were thinner than the code allowed. A great majority of these plants were PWRs (18) while l

only 1 BWR plant was affected. This is due to the higher level of oxygen contents in the feedwater piping of BWRs. Above a certain level of oxygen, significant erosion corrosion does not occur. All susceptible plants have either performed an inspection, or have comitted to do so during the next cutage.

l Mr. B. Chexal, EPRI, presented a brief descriptier of a code developed to predict susceptible treas of thinning based on water i chemistry, plant operating conditions, and thema1/ hydraulic considerations. Preliminary results used for locating thin arets in piping systems for single-phase flow were found to be satis-factory. A program for two-phase flow is being developed.

The NRC Staff has sent an IE Pulletin to all licensees requesting infomation on their pipe thinning monitoring program. The Staff is pleased with the rapid reply from the utilities. It was stated that Section XI of the ASME Cooe will include periodic pipe wall thinning inspections. Since the utilities have respe ded effectively and rapidly on this matter, the Staff did not see a need for a rule.

D. Boric Acid Corrosion Highly concentrated boric acid solution, produceded by boil-off of

, 1 caking reactor coolant. corrodes low alloy steel bolts. Some utilities have ignored leakage of the primary system if it is below the technical specificatiens limit on leak rates. This, in ser'e instances, has produced damaged bolts. The ?$C Staff has issued a gereric letter which states that licensees snall have a progran for

i

, . 338TH ACRS MEET!NG HINUTES 7 l

l evaluating and fixing leaks in bolted joints in the primary system, i s The NRC Staff will ev&luate the utilities' responses when they are received, i 4 Y. World Assectation of Nuclear Operators (0 pen)

[ Note: Mr. S. Schofer was the Designated Federal Official for this portionofthemeeting.] l 1

Dr. Remick introduced Mr. Stanley Anderson, Vice President of the In- l stitute of Nuclear Power Operations (INPO), to discuss the development

of a new organization, the World Association of Nuclear Operators l (WANO). l Mr. Ande* son gave an overview of INP0's current internationel program by 3 identifying the 14 other countries that are members of the Dp0 interna- l l tional program and observing that the international participants receive i essentially the same services as the U.S. utilities receive, except for i plant evaluations and accreditation program. Each participating countrv l 1 supportseitheroneortwoliaisonengineers(Japanhasthreeengineers) :

1 in their work with INPO. The INP0 international program maintains er :

advisory group that meets two or three times a year and provides techni- !

cal exchanges through team visits to individual countries on an invita- !

. tion basis only. INPO also sends individual engineers to participating i countries for extended work periodst for crample, an engineer was loaned i to the Electricite' de France for abcut 18 months. INP0 has sent an t engineer to the International Atomic Energy Agency (IAEA) to be a team <

manager on an Operatienal Reactor Safety Team.

l Pr. Anderson discussed the first meeting of representatives from 29 I countries that had crerating reactors or soon to be operating reactors.

The ceeting, sponsored by INPO and UNIPEDE, was held in October 1987.

The representatives resolved to estabitsh a World Association of Nuclear Operators, with four contdinating centers. The proposed mission of WANO !

is to exchange inforriation, encourage comparisons, and ctimulate ;

emulation ameng all operators. i Mr. Anderson stated that English was accepted as the official language :

by the participatirg countries, including the Soviet Union.

A Steering Comittee was forred with Lord Marshall as the Chairman. The .

Steering Comittee has met twice since October 1987. The Steering !

Comittee created four expert groups. Expert Group 1 is responsible for l global comunications using the INP0 NETKORK and Telenet. Expert Group :

2 is responsible for identifying the infomation to be exchanged, st.ch !

as event reports, operating practices, and opcrator-to-operator sharing l of experiences. Expert Group 3 is responsible for drafting an l organization charter. Expert Group a is responsible for orgenizational ;

operation and planning for future meetings. ;

In response to a questicn, Mr. Anderscn statec that U.S. participation l will be restricted to U.S. utilitics through INFO. I i

I l

l

338TH ACRS MEETING MINUTES 8 1

) .

i Mr. Michelson observed that there are close parallels between the l missions of INPO, WANO, and IAEA, For example INPO has a data base and l j IAEA has the IRS System, and both have voluntary inspection programs. ;

4 A second meeting of the 29 countries will be held in Moscow, USSR, in l May 1983 to femally approve the charter and organization of WANO. ;

Mr. Anderson described his responsibilities as Vice President of INPO !

! International Supply Divisien. INPO sponsors the Supplier Participant !

Advisory Committee that includes among its membership, representatives 6 from AECL, Franatome, Seamans Westinghouse, General Electric, Bechtel, !

Stone and Webster, and Babcock and Wilcox. l

! Mr. Michelson noted that INFO seems to get involved in short-tem )

accident evaluations and feeds out long-term analysis to the Electric t i

Power Research Institute (EPRI). !

Dr. Ptmick thanked Mr. Anderson for his infomative briefing.

VI. USIA-17.SystemsInteractions(0 pen)

] [ Note: Mr. M. D. Fouston was the Designated Federal Official fer this 4 portionofthemeeting.]

)

j Mr. Ward, Chaiman of the Safety Philosophy, Technology and Criteria 1 Subcomittee , introduced the subject of the resolution of USI A-17,

! "Systems Interactions in Nuclear Power Plants " and indicated that no

) Comittee report was anticipated at this meeting but that assignment to an appropriate ACRS subcomittee for future review should be considered, if appropriate.

Mr. Robert Baer, RES, presented backcround information on the resolution of USI A-17 and indicated that the Staff wculd like e letter of endorsuent to send cut the resolution package for public coment.

Mr. Dale Thatcher, RES, discussed the resolution package for USI A-17.

The package, in the fom of a generic letter, would provide the basis for resolution, would provide infomation on lessons learned, and weuld request certification of a flooding evaluation for each plant. He discussed the relationship of USI A-17 to USI A-46, "Seismic Qualifica-tion of Equipment in Operating Plants." He also indicated hcw the results from USI A-17 would be applied as input to GI-128 "Electric Power Reliability " and to the Individual Plant Examinations (IPEs) or PRA studies. Finally, he discussed the follow-on progran at Oak Ridge National Laberatory, "Multiple System Responses Program " that has been developeo to consider concerns raised in studies of USI A-17, USI A-46, and USI A-47, "Safety Implications of Control Systems."

Mr. Michelson expressed concern about the development of flooding analyses and indicated that the analyses ao not go far enough. He asked about the guidance to be provided for certification of flooding evalua-tions. He also questioned the adequacy of plant walkdewns for analysis of seismic-induced interactions in that they consider only physical

,. . 338TH ACRS MEETING MINUTES 9 l

interactions. He further expressed concerns that fire systems and control air systems were not being properly considered.

)

Mr. Ward discussed fault tree development for PRA studies, and asked l

! whether systems interactions have been analyzed by this process. In the i following discussion, it appeared that some aspects of systems interac-i tions have been analyzed while others have not, i

I Dr. Lewis indicated that, if the situation is well enough understood, l input to a PRA could be formulated. However, he expressed a concern

! that, with a multitude of postulated systems interactions, one has to

! celect a finite set or be buried in mostly useless data.

4 In closing, Mr. Ward asked for guidance from the Comittee on a possible endorsement or further subcomittee review. Dr. Siest indicateo a desire for further subcomittee review. Drs. Kerr and Lewis stated that j they would support issuing the report for public coment and let the

Staff develop the "Multiple Systems Respense Program" to resolve further

! concerns in this area. Mr. Michelsen expressed some reservations about closing out US! A-17 VII. proposed Revision of 10 CFR 20 "Standards for Protection Acainst j Radiation" (0 pen)

)

l [ Note: Mr. E. I of the meeting.:gne was the Designated Federal Official for this portion j

l Mr. Harold Peterson, Jr., RES, briefed the Comittee on this matter. He stated that the NRC Staff has tried to make the regulations corpatible a with recemendations of the ICRP, NCRP, as well as with the standards of other federal agencies such as the EPA. The NRC Staff has reviewed and evaluated cements received from about 800 outside organizations and individuals, and has revised the regulations to include the latest scientific data on radionuclide decay schemes and the behavior of

! specific radionuclides within the human body. In addition, the regula-J tions have been expanded to include dose limits for the embryo / fetus in i an occupational setting as well as for merters of the public, i

} There was discussion of the use of comitted effective dose equivalent i versus anrual effective dose equivalent. The Comittee agreed that the l application of the comitted effective dose equivalent is the proper 1 approach to follow in planning fer radiation protectier and in j controlling exposures from nuclear activities. However, the Comittee

sided with the NCRP position which states that the committed effective

, dose equivalent alore does not constitute a basis for evaluating the i potential health effects of radiation exposures in individuals. Such i evaluation should be based on estimates of the actual absorbed dose for the period of exposure appropriate to the individual case. For this

reason, the Comittee suggested that a licensee should be given the

option of using the annual effective dose equivalent in determining

] compliance with this rule.

I 1

i l

, 338TH ACRS HEETING MINUTES 10 VIII. Executive Sessions A. Subcommittee Reports

1. AdvancedBoilingWaterReactors(0 pen)

[ Note: Mr. R. Major was the Designated Federal Official for this portion of the meeting.]

Mr. Michelson, Chairman of the ACRS Subcomittee on Advanced Boiling Water Reactors (ABWR), reported that during a meeting on June 1,1988, the Subcomittee began its review of this project. He explained the strategy he intends to use to review this standard plant concept.

The ABWR review is divided into four modules. For each module the NRC Staff will conduct a review and issue a Safety Evaluation Report. The Committee will review each module, and issue a letter report on each. There will be a fif th ACPS report comenting on the overall final design approval review.

Prior to each ACRS letter, a review module will be discussed at three subcomittee meetings. At the first subcomittee meeting an overview will be given. Detailed questions will follow at the second meeting, and any will be resolved during the third (letter report due>:roblemssession.

Mr. Michelson noted that the scope of the ABWR review has increased. The APWR plant design has been expanded to include the balance-of-plant (turbine island and radioactive waste systems) in addition to the nuclear island. The effects this expanded scope will have on the review schedule is not yet certain. 1 The goal of the current review is to obtain infonnatinn required to justify a Final Design Approval (FDA) for the i ABWR. GE intends to carry the ABWR review beyond the FDA process to receive design certification.

Mr. Michelson announced that the rext subccmittee meeting in ,

the ABWR review is tentatively scheduled for November 15-16, 1988. During this meeting, the Subconnittee will consider detailed questions on Module 1 and an overview of Module 2.

Mr. Michelson believes only problem areas need to be con-sidered by the full Comittee.

Fotential problem areas in the ABWR review were highlighted by Mr. Michelson. These areas included: a potential problem if the EPRI standardization effort gets out of phase with the ABWR effort; how to address severe accident considerations, such as accident mitigation features and a containmcrt d e'-

signed for the traditional design basis accident; and resolutien of the collection of Unresolved Safety Issues and Generic Safety Issues.

, , 338TH ACRS MEETING HINUTES 11 ,

l '

2. Regional Programs (0 pen)

[ Note: Mr. P. A. Boehnert was the Designated Federal Official for this portion of the meeting.]

l l Dr. Remick, Chairman of the Regional Programs Subcomittee, I reported on the May 24. 1988 Subcomittee meeting with repre-l sentatives of NRC's Region, !! Office: ;

l Dr. Remick believes the Region staff appreciates ACRS visits. Their discussions with the Subcomittee have

been quite candid.

Eight of 10 states under Region !! purview are Agreenent States. There are 32 power reactors in this Region.

These plants have a heavy load of reactor inspections. :

i SALP reviews are seen as very useful by both the ,

I licensees and the Region staff. The licensees pay close ,

attention to SALP ratings. l The new operator examination program is considered a ruccess. Dr. Remick said he believes it is the wave of the future.

1 Discussion of prob 1cns plants / licensees was candid and l straightforward.

There is a continuing shortage of NRC operator examiners.

l Major problems are the federal salary limit and the l perception that it is a "dead-end job."

QA inspections are becoming performance-based. l Safety conscience is evident at all plants, but the ;

j intensity varies. Region II staff agretd, as have the ;

I staffs of all other Regions visited by the Subcomittee, !

that "safety conscience" must pervade the licensee's entire organization. ;

Fitr.ess for Duty (FFD) problems are pervasive; all :

licensees have experienced FFD incidents. Most licensees .

are employing random drug testing programs, j Dr. Moeller agreed that the Region !! staff was generally !

pleased with the visit. He was impressed with the cerrpe- (

tence displayed by the Region's representatives. Mr. l Wylie noted that the Region staff did not see a need "or l all reactor operators to be degreed individuals, nr. :

Ward noted that the Region staff believed a mix of !

degreed and non-degreed people is preferred. He said the !

Japanese are planning to go to a similar type of ap- i proach. j L

[

l !

l

. 338TH ACRS NEETING MINUTES 12 Dr. Kerr, citing the May 24, 1988 Subcomittee meeting minutes, asked if Region 11 is really concerned with complacency brought on by a plant's having too high a SALP rating. Additional discussion indicated Comittee concern that the NRC may be going beyond the regulations toward managing of the plants.

B. Reports,LettersandMemoranda(0 pen)

1. Proposed Friority Rankings of Gencric Issues: Fifth Group (Memorandum to Mr. V. 5tello from R. Fraley, dated June 7, 1988)

The Comittee reviewed the adequacy of the proposed priority rankings for a fif th group of Generic !ssues, offered its coments, and requested that the NRC Staff provide written responses to the ACRS coments.

2. NPC Research Related to Heat Transfer and Fluid Transport in Nuclear Power Plants (Letter to Chairman Zech, dated June 7, Tf88)

The Comittee made a number of recomendations regarding future research on heat transfer and fluid transport with respect to the traditional thermal-hydraulic area, large scale codes, traditional code development and the need for a cadre of experienced research people.

3. NRC Proposed Rule on Early Site Permits, Standard Design Certification, and Combined Licentes for Nuclear Power Reac ,

tors (Letter to Chairman Zech, dated June 7, 1968)

The Comittee provided coments on the proposed rule to improve the regulations and alternatives to rulemaking regarding design detail.

4 The Babtock & Wilcox Ovners Group Safety and Ferformance Imarovement Program (letter to Chairman Zech, dated June 7, 1938)

The Comittee agreed with the Staf f findings that B&W SPIP improverents will irprove safety by reducing the frequency and complexity of transients. The Comittee also offered cements regarding several "spin-off" efforts by the NRC Staff and the BWOG.

5. Proposed Revisions of 10 CFR 20 "Stand 6rds for Protection Against Radiation" (Letter to Chairman Zech, dated June 7, 1988)

The Cemittee provided coment s , including suggesting an option with respect to use of the comitted effective dose equivalent.

338TH ACRS MEETINC MINUTES 13 !

6. Rulemakino on Emergency Planning and Preparedness (letter to f Chairman Zecn, dated June 7, 15iS8) l The Comittee concurred in the proposed rulemaking for fuel cycle and other material licensees, and in the proposed rule-mt king that would require tne development of limited emergency 4 plans for nuclear power plants during fuel loading and initial ;

low-power operation.

l

7. Inservice Inspection of Boilint Water Reactor Pressure Vessels ;

(Letter to Chaiman Zech, dated June 7,1958) t The Comittee comented that the inspection program is ;

desirable to maintain the appropriate defense-in-depth.

8. USI A-17 "Systems Interactions in Nuclear Power Plants" l (Memorandum to Mr. V. 5tello from R. Fraley, dated June 9, 1988)

The Comittee stated that ACRS plans to continue its evalua-tion of the proposed resolution plan, but would not object to ,

publication for coment during this review period.

9. Issuance of NUREG-1150 (Heborandum to Mr. V. Stello from R. i FraleydatedJune8,1988)

The Comittee requested an opportunity to discuss this matter I further if the EDO intends, as indicated, to erphasize early l

} issuance without peer review. !

i I C. OtherConclusions(0 pen / Closed) l f

1. Advanced Reactor Designs (0 pen) [

[ Note: Mr. M. El-Zeftawy was the Designated Federal Of fici .1 :

l for this portion of the meeting.] [

4 L

The Comittee discussed the latest version of the draft !

Comissicn paper which identifies four key licensing issues !

i for the DOE-sponsored advanced reactors. These four key I i issues are: (

Accident selection !

, Siting source term selection and use (

Adequacy of containment system J Adequacy of offsite energency planning. !

, i

! itr. Ward, Chairman of the Advanced Reactor Designs Subcomit- [

tee, indicated that the three DOE advanced reacter designs ;

4 have a containment system different from the conventional ones t used for the LWRs. In the high-temperature gas-cooled reactor (FTGR), the fuel coating provides the containment function in :

4 the plant. In the liquid-metal design, a guard vessel that !

j surrounds the reactor vessel and the reactor vessel closure ;

I :

, f

)

L

7 , ,. 338TH ACRS MEETING MINUTES '14 head providt.s for containment of fission products and radioac-tive sodium.

Those responsible- for one design of the LMR [ power reactor inherently safe module (PRISM)] propose to utilize testing of a prototype plant, preferably on a DOE site, as a demonstration. Those responsible for the other LPR design

[ sodium advanced fast reactor (SAFR)] propose to utilize testing of the first comercial unit, not necessarily on a DOE site, for demonstration. The NHTGR design group propose that R&D program results, combined with the normal startup testing of the first cemercial unit, not necessarily en a DOE site, be accepted as sufficient for demonstration.

Mr. Ward comented that the above four key licensing issues are very important. The Comittee will continue its discussion on this subject during the Jgly 1988 ACR5 meeting.

The Comittee agreed.

2. Importsnt Safety-Related_!ssues (0 pen)

[ Note: Mr. Sam Duraiswamy was the Designated Federal Official forthisportioncfthemeeting.)

Dr. Siess stated that the Comittee has already been censider-ing several of the issues identified by various ACR$ rembers.

He proposed that, if the Comittee does not have any objec-tion, he would go through the list of renaining issues and dispose of those issues that beve already been, or are being, considered by the Cemittee and submit a revised Itst of issues for discussien during the July 14-16, 1988 ACRS reeting. The rembers agreed to this proposal.

l 3. International Conference on Ouality Meeting (Orte)

[ Note: Mr. S. Schofer was the Designated Fedual Official for i tnis session; Dr. S. A. Arndt. ACRS Fellow, wrote this portionoftheminutes.]

The Comittee was briefed by Dr. Siess and Pr Ward en the status of the planned International Conference on Quality.

The Comittee plans to co-host the conference with the Merican Society for Quality Control (ASQC). Tbc conference is scheduled for late Pay or June 1969. The site has not been selected. The confereece will be four days in length with the first morning reserved for an opening session including a orceting from Chairman Zech, or an ACRS representative, and a keynote adcress. ACRS rembers Dr. Siess and Mr. Ward, and ACRS consultant John Stevenson, will serve on the Technical Progran Comittee to provide guidance regarding the technical issues that the Comittee would like to set addressed at the conference.

, , 330TH ACRS MEET!!<G MINUT,ES 15 The Planning Comittee met on May 10 and on June 1,1980. The ASQC is movint forward in all areas of conference planning, including site selection, program, f'nancial arrangements, and ,

publication of proceedings. The ACRS Staff will assist the ASQC in the areas of international contact, speaker selection, and interface with the NRC Staff.

Cr. Lewis and Dr. Remick expressed concern that the scope of the conference had become too broad. tr. Siess commented that, although the scope was broader than he would like, especially in the area of operational quality, the concerns of the Committee will be addressed. Dr. Remick expressed inter-est in having an end-of-conference workshop at which the Comittee would discuss additional topics.

The ASQC asked the Comittee, through Dr. Siess, to send Dr. Kerr and Chairman letterstoof Zech, invitation,speakers.

conference to be signed The Com b,ittee approved.

4. Fourth Regular Bilateral Meeting on Nuclear Regulatory Matters (Note: Mr. E. G. Igne was the Designated Federal Official for thisportionofthemeeting.] l Mr. Ward and Dr. Shewmon reported on the Fourth Regular Bilateral Meeting on Nuclear Pegelatory itatters which was held l in Japan on May 12-18, 1988. The Japanese officials are l concerned about the first organized antinuclear reaction i caused by the return to Japan of pleterium from overseas l reprocessing of reactor fuel. Also reported were plans for a i new nuclear fuel center on the Shimokita Peninsula. There will be at.least three complexes builti a reprocessing plant, high- and low-level waste storage sites 9nd a centrifuge enrichment plant. They hope to build in a few years.

Attachment A contains a preliminary report of Dr. Shewmon en the meeting with HITI and with the utility, Kanzai Electric, of the OHI plant.

4 Prioritiration of Generic Issues (0 pen)

[ Note: Mr. S. Duratswary was the Cesignated Toferal Official for this portion of the meeting.]

Dr. Siess stated that in 1983 the ACRS decided to review the adequacy of the priority rankings proposed by the NRC Staff in batches rather than one by w e, as they are received. So far, corrents on thf.s matter have been provideo to the EDO en four different occasions; the last set cf comments was provided on t;evember 13, 1956.

Dr. Siess said that the list of items sutaitted to the ACPS for review at this tire includes 29 issues. Most of these issues sterred from the evaluation cf the loss-of-feedwater

. 338TM ACRS MEETING MINUTES 16 I event that occurred on June 9, 1985 at the Davis-Pesse nuclear ;

plant. These issues were assigned to six different ACRS subcomittees for review. The results of the review are as follows:

Subcomittee chairrien and/or subcomittees have agreed with the NRC Staff-proposed priority rankings for 26 Generic Issues.

They have agreed with the propnsed priority rankings for two Generic Issues, but provided some coments.

One of the subconmittee chaimen has disagreed with the proposed priority ranking for one issue.

During the discussion of Generic !ssue 136 "Storage and Use of 1.arge Ouantities of Cryogenic Cembustibles," Mr. Carroll

- asked whether this issue includes BWR off-gas systems. The Staff says it does not.

Stating that operating experience showed that there had been j problems with BWR off-ges systems, Mr. Carroll suggested th6t the Staff evaluate the problems associated with this system under one of the existing Generic Issues or urder a new Generic !ssue.

Af ter further discussicn. the Comittee approved, with a few changes, the coments p'ovided by various subcomittee chair-i men, and asked Mr. Fraley to transmit these coments to the i EDO.

i

D. Future Activities (0 pen)

1. Future Agenda i The Comittee agreed to the tentative future agerda shown in Appendix 11.

2. Future Subcomittee Activities

A schedule of future subcommittee activities was distributed j to members (Appendix !!!).

4 The creting was adjourned at 1:25 p.:n., Saturday Jure 4,1988, 1

st . .

a APPEf;0:0E0 MINUTES OF THE 338TH ACRS MfETING JUNE 2-4, 1988

1. Attendees

. II. Future Agenda III. Future Subcomittee Activities IV. Other Documents Received e

s: . .' . .

4 337 338 339 340 341 342 343 344 345 346 ACRS MEETING DATE h a ';L- 4 M q s ATTENDEES Thursday Friday Saturday Dr. William Kerr, Chairman / ./ /

Dr. Forrest J. Remick, Vice Chairnan ,/ / /

Dr. Harold W. Lawis _i_ v /

Mr. Carlyle Michelson _f_ / /

Dr. Cade W. Moeller ,.

/ /

Dr, Paul G. Shewon v' _, v' /

Dr. Chester P. Siess l_ _f /

Dr. Martin J. Steindler _ _ , .

Mr. David A. Ward / / /

Mr. Charles .]. Wylie / v' /

'l / /

i lir. Janes C. Carroll (observer) i I

APPENDIX !

L

I ATTENDEES 338TH ACRS MEETING JUNE 2-4, 1988 JUNE 2,1988 JUNE 3, 1988 NRC Attendees NRC Attendees A. Cappucci, NRR A. Cappucci, NRR J. Wilson, RES 0. Cool, NF.SS M. Malsch, OGC D. Scaletti, NRR

0. Scaletti, NRR H. Peterson, RES S. Treby, OGC D. Cool, NMSS Stewart W. Long, ACRS ,

Public Attendees Public Attendees K. Boyd, Heritage Reporting i Peter F. Riehm, KMC Kim Arn, SERCH Licensing ! Karen Unnerstall, Newman &

Steve Poltorak, SERCH Licensing ; Holtzinger Martin W Fbert, NUS Corp. ! Mark Stella, ITC Rob ','uolley, Ua Inte - Service i D. Knuth, KMC Catherine Cooney, AECH t Brian Farrell, EE!

Joan Rose, Heritage ! Elizabeth E. Len, Bishop, Edward Murphy, Texas Utilities ; Cook James Williams, Heritage i Lynne A. Fairobent, NUMARC Lillian Cuoco, Fried, Frank ; Diane Flack, ORAU/CIRRPC Candis Allen, SAIC/00E l Joan Rose, Heritage Martin W. Ebert, NUS Eve Fotopoulos, SERCH Licensing, Bechtel Mark Phillis, Bishop Cook, et al. '

Gil Brown, NUMARC Stan Anderson, INPO '

Chet Harris, INP0 s

I-2

[ APPENDIX II FUTURE AGENDA JULYi4-16,198q-Itemsaretentativelyscheduled.

Safety Related Issues (0 pen) (CPS /50) Estimated time: 2 hrs. Discuss proposed hiirarchical structure for important safety related issues.

USI A-48, Hydrogen Control (0 pen) (WK/MDH) Estimated time: li hrs. - Briefing regarding proposed resolution of hydrogen control requirements for Mark III and ice condenser containment types.

Evaluation of Oseratinc Experience (0 pen) (HWL/HA) Estimated time: I hr. -

Briefing by AEO) regarcing systematic evaluation of au).iliary systems operating performance in nuclear power plants.

Equipment Qualification (0 pen) (CJW/FA) Estimated time: li hrs. - Review and comment regarding Equipment Qualification Scoping Study performed by Sandia National Laboratories.

NRC Policy on Severe Accidents (0 pen) (WK/MDH) Estimated time: ? hrs. -

Review and coment regarding proposed integrated plan for closure of severe accident issues.

Modular High Tenperature Gas Cooled Reactor (0 pen) (DAW /MME) Estimated time:

2 hrs. - ACR5 review and coment regarding proposed standardized gas-cooled reactor concept proposed by D0E.

Diagrostic Evaluation Program (0 pen) (HWL/HA) Estimated time: li hrs. -

Briefing regarding NRC diagnostic evaluations of the McGuire and Dresden nuclear power stations.

l NRC Policy on Working Hours for Nuclear Power Plant Operators (0 pen) (FJR/HAJ Estimated time: 3/4 hr. - Review and coment regarding proposed NRC requirements for working hours for nuclear power plant operators.

l Operating Events and Incidents (0 pen) (HWL et al./HA) Estimated time: i hr. -

! Discuss procedures for selection / review / evaluation of nuclear power plant l incidents, transients, and accidents.

Operating Procedures and Practices (0 pen) (HWL/RFF) Estimated tine: I hr. -

, Discuss proposed change in ACRS practice regarding participation in meetings l not sponsored by the ACRS.

ECCS Evaluation Models (0 pen / Closed) (DAW /PAB) Estimated time: 2 hrs. -

Review and coment regarding proposed changes in ECCS evaluation models for Westinghouse nuclear plants with upper-plenum injection.

! Future Activities (0 pen) (WK/RFF/MWL) Estimated time: I hr. - Discuss

! anticipated ACRS subcomittec activity and items proposed for consideration by the full Comittee, i

338th ACRS MEETING II- 2 New ACRS Members (Closed) (FJR/NSL) Estimated time: A hr. - Discuss qualifications of candidates proposed for appointment to the ACRS.

Valve Reliability (0 pen) (CJW/RYM) Estimated time: 3/4 hr. - Briefing and discussion regarding proposed resolution of MOV testing.

AUGUST 11-13, 1988 Pilgrim Nuclear Station (0 pen) (WK/PAB) Estimated time: 2 hrs. - Discuss proposed restart of operations.

Decay Heat Removal (0 pen) (DAW /PAB) Estimated time: 2 hrs. - Review and coment regarding proposed resolution of USI A-45.

Human Factors (0 pen) (FJR/HA) Estimated time: I hr. - Briefing and discussion regarding AEOD report on availability of excess infonnation to nuclear power plant operators during transient conditions.

Standardization of Nuclear Plants (0 pen) (CJW/HA) Estimated time: 3/4 hr. -

Briefing regarding status of EPRI Requirements document for Advanced LWRs.

Meeting with _NRC Comissioners (Tentative) Estimated time: I hr. - Briefing and discussion regarding May 10, 1988 ACRS report on Individual Plant Examinations and the Proposed Integrated Safety Assessment Program II.

Licuid Metal Reactors (0 pen) (DAW /MME) Estimated time: 4 hrs. - ACRS review anc comment regarding proposed design concepts for DOE standardized LMCR (SAFR andPRISM).

USI A-47, Safety Implications of Control Systems (0 pen) (HWL/GRQ) Estimated time: li hrs. - Discuss proposed reply to questions from the NRC Staff regarding assunptions and limitations regarding evaluation of issues associated with USI A-47 (could slip to September).

Nuclear Power Plant License Renewal (0 pen) (CJW/RDi) Estimated time: li hrs.

- ACRS review and coment regarding proposed NUREG-1317, Regulatory Considerations Pertaining to Nuclear Power Plant License Renewal, status report.

SEPTEMBER 8-10, 1988 Operating Procedures for Severe Accidents (0 pen) (WK/MDH) Estimated time: 11 hrs. - Briefing hy NRR representatives regarding status of procedures for managing severe accidents.

PeachBottomNuclearStation(0 pen)(WK/PAB)Estinatedtime: 2 hrs. - Restart of the Peach Bottom Station.

APPEND 1X Iff ACRS SUBCOMitITTEE/ACNW MEETINGS Reliability Assurance, June 14, 1988, 1717 H Street, NW, Washincton, DC (Major), 8:30 a.m., Room 1046. The Subcommittee will be briefec on the final outcome of the Equipnent Qualification-Risk Scoping Study. An update on the implementation of the resolution of USI A-46, "Seismic Qualification of Equipnent in Operating Nuclear Power Plants," is also planned. Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of June 13:

fir. Wylie DAYS INN (VA) Dr. Siess ANTHONY Mr. Michelson DAYS IliN (DC)

Maintenance Practices and Precedures, June 15, 1988, 1717 H Street, NW, Washington, DC (Alderman), 8:30 a.m., Roem 1046. The Subcomittee will be briefed by the NRC Staff on the current status of the Maintenance Rule.

Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of June 14:

Mr. Michelson DAYS INN (DC) Mr. Wylie DAYS INN (VA)

Thermal Hydraulic Phenomena (0 pen / Closed), June 21, 1968, 1717 H Street, NW, Washington, DC (Boehnert), 8:00 a.m., R. 1046. The Subcocnittee will continue its review of the Westinghouss.: rr lsed ECCS Evaluation Model for 2-Loop Upper Plenum Injection (UPI) pire. Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the nights of June 20 and June 21:

! Ilr. Ward CANTERBURY Dr. Plesset LOMBARDY Dr. Kerr L0ftBARDY Mr. Schrock LOMBARDY l Mr. Wylie DAYS INN (VA) Dr. Sullivan NONE

Dr. Catton DUPONT PLAZA Dr. Tien LOMBARDY Advanced Reactor Designs, June 22, 1988, 1717 H Street, NW, Washington, DC (El-Zeftawy), 8:30 a.m., Room 1046. The Subcomittee will review the draf t SER of the Modular HTGR conceptual design. Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of June 21:

Mr. Ward CANTERBURY Dr. Siess ANTHONY Dr. Kerr LOMBARDY Mr. Wylie DAYS INN (VA)

Dr. Remick NONE Dr. Avery NONE Dr. Shewmon NONE Dr. Lee NONE

t First Meeting of the Advisory Committee on Nuclear Waste, June 27 and 28, 1988, Room 1046, 1717 H 5treet, NW, Washington, DC and June 29, 1988, Room WF-2F17, 11555 Rockville Pike, Rockville, FD (Parry). The Comittee will review the following pertinent nuclear waste management topics: (1) DOE's proposal to petition for rulemaking on the Design Basis Accident Dose Limit for a geologic repository, (2) A DOE presentation on Alternative Conceptual Models of the Yucca Mountain site, (3) an NRC Staff briefing on concrete LLW forms and polyethylene high integrity containers (HICs), (4) a DOE aresentation on the Consultr. tion Draft Site Characterization Plan, (5) a ariefing on the licensing procedures used to authorize at reactor LLW processing and spent fuel compaction and dry storage operations, and (6) on June 29 the full ACNW will meet with the NRC Commissioners to discuss future Comittee plans. Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the nights of June 26, 27, and 28:

Dr. Moeller LOMBARDY Dr. Parker LOMBARDY Dr. Kerr LOMBARDY Dr. Moody GUEST QUARTERS Dr. Shewmon NONE Dr. Orth ANTHONY Dr. Steindler LOM3ARDY Dr. Thompson ANTHONY Dr. Carter ANTHONY Meeting on the International Workshop on QA/QC, July 6, 1988, 1717 H Street, ,

NW, Washington, DC (Arndt/Igne), 8:30 a.m., Room 1046. Planning session by the Energy Division of the American Society for Quality Control is assisting the NRC and its ACRS in presenting an international conference to be held in the spring of 1989 in the U.S. Attendance by the following is anticipated, and reservations have been made at the hetels indicated for the night of July 5:

Mr. Ward CANTERBURY Dr. Stevenson ANTHONY Dr. Siess ANTHONY Severe Accidents, July 12, 1988, 1717 H Street, NW, Washington, DC (Houston), ,

(P.M. only), Room 1046. The Subcomittee will discuss SECY-68-147, "Inte-gration Plan for Closure of Severo Accident Issues." Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of July 11:

Dr. Kerr LOMBARDY lir. Wylie DAYS INN (VA)

, Dr. Siess ANTHONY Dr. Catton DUPONT PLAZA l Dr. Shewmon NONE Mr. Davis HOLIDAY INN l Mr. Ward CANTERBURY Dr. Lee NONE l

TVA Organizational Issues July 13, 1988, 1717 H Street, N'd, Washington, DC

(Houston), 8: 30 a.m., Room 1046. The Subcomittee will review the generic l 1essons learned from the Staff's review in regard to the restart of Sequoyah l 2. Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of July 12:

Mr. Wylie DAYS INN (VA) Dr. Remick NONE l Mr. Michelson DAYS INN (DC) Mr. Ward CANTERBURY Mr. Carroll NONE L _ _ _ _ .. _ _ _ _ _

339th ACRS Meeting, July 14-16, 1988, Washington, DC, Room 1046.

Decay Heat Removal Systens, July 20, 1988, 1717 H Street, NW Washington, DC (Boehnert), 8:30 a.m., Room 1046. The Subcommittee will continue its review of the NRC Staff's resolution position for USI A-45. Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of July 19:

Mr. Ward CANTERBURY Mr. Wylie DAYS INN (VA)

Dr. Kerr LOMBARDY Dr. Catton DUPONT PLAZA Mr. Michelson DAYS INN (DC) Mr. Davis HOLIDAY INN Thermal Hydraulic Phenomena, July 21, 1988, 1717 H Street, NW, Washington, DC TBeehnert), 8:30 a.m., Room 1167. The Subconnittee will review the status of the MIST Phase III and IV Programs and the proposed OTSG Follow-on Program.

Attendance by the fo11cwing is anticipated, and reservations have been made at the hotels indicated for the night of July 20:

Mr. Ward CANTERBURY Dr. Catton DUPONT PLAZA Dr. Kerr LOMBARDY Dr. Plesset LOMBARDY Mr. Michelson DAYS INN (DC) Mr. Schrock LOMBARDY Mr. Wylie DAYS INN (VA) Dr. Sullivan NONE Dr. Tien LOMBARDY Second Meeting of the Advisory Connittee on Nuclear Waste, July 21-22, 1988, Washington, DC, Room 1046.

General E1cetric Reactor Plants, July 29, 1988 (tentative), (Site Visit July l

28th, P.M.) Plymouth, MA (Boehnert). The Subcommittee will review the preposed restart of the Pilgrim plant. Lodging will be announced later.

Attendance by the following is anticipated:

l

, Dr. Kerr Dr. Lewis Mr. Carroll Dr. Siess 1

l Safety Philosophy, Technology and Criteria, August 4, 1988, 7920 Norfolk Avenue, Sethesda, MD (Houston), 8:30 a.m., Room P-110. The Subconnittee will rev~iew the status of NUREG-1251 (Implications of Chernobyl) and the NRC Staff's program (at BNL) to address the implications of Chernobyl in regard to severo reactivity transients. Lodging will be announced. Attendance by the following is anticipated:

i Mr. Ward Mr. Wylie Dr. Kerr Dr. Lee

! Dr. Lewis Dr. Lipinski Dr. Remick l

Site Visit by the Advisory Committee on Nuclear Waste, August 3-5, 1988, Columbia and Barnwell, SC.

Improved Light Water Reactors, August 9, 1988, 7920 Norfolk Avenue, Bethesda, MD (Alderman), 8:30 a.m., Room P-110. The Subcommittee will review Chapters T,' 4, and 5 of the EPRI LWR Requirements Document. Lodging will be announced later. Attendance by the following is anticipated:

Mr. Wylie Dr. Siess Mr. Michelson Mr. Ward Auxiliary Systems, August 10, 1988, 7920 Norfolk Avenue, Bethesda, MD (Duraiswany), 8:50 a.n., Room P-110. The Subcomittee will review the proposed resolution of USI A-17, "Systems Interactions in Nuclear Power Plants." Lodging will be announced later. Attendance by the following is anticipated:

Mr. Michelson Mr. Wylie Mr. Carroll Mr. Ebersole Dr. Siess (tent.) Dr. Okrent Mr. Ward (tent.)

340th ACRS Meeting, August 11-13, 1988, Bethesda, MD, Room P-110.

341st ACRS Meeting, September 8-10, 1988, Bethesda, MD, Room P-110.

Maintenance Practices and Procedures September 13, 1988, 7920 Norfolk Avenue, Bethesda, MD (Alderman), 8:30 a.m., Room P-110. The Subcomittee will discuss and review the maintenance rule and associated NUREG. Lodging will be an-nounced late *. Attendance by the following is anticipated:

Mr. Michelson Mr. Wylie Mr. Cerro11 Mr. Reed

_ Third Meetinc of the Advisory Committee on Nuclear Waste, September 15-16, 1968, Bethesc a, MD, Room P-110, 342nd ACR$ Meeting, October 6-8, 1988, Bethesda, MD, Room P-110.

Advanced Boiling Water Reactors November 15-16, 1988, 7920 Norfolk Avenue, Bethesda, MD (Major), 8:30 a.m., Room P-110. The Subcomittee will continue its FDA review of this standard plant. Detail ACRS questions will be covered on review module 1. An overview of the second review module is planned.

Lodging will be announced later. Attendance by the following is anticipated:

Mr. Michelson Mr. Ward Dr. Kerr Mr. Wylie i Dr. Remick Mr. Ebersole Dr. Shewmon Dr. Okrent '

l

...'l, 343rd ACRS Meeting, November 17-19, 1988, Bethesda, MD s Room P-110.

344th ACRS Meeting, December 15-17, 1988, Bethese,MD,RoomP-110.

Advanced Pressurized Water Reactors, Date to be determined (August),

Washington, DC (El-Zeftawy). T.he Subcomittee will review the draft SER in regard to :he reactor, reactor coolant systen, and regulatory conformance for the WAPWR RESAR SP/90 design. Attendance by the following is anticipated:

Mr. Ward Dr. Remick Dr. Kerr Dr. Shewmon Mr. Michelson Mr. Wylie Advanced Pressurized Water Reactors, Date to be determined (July), Washington, DC (El-Zeftawy). The SubcommitteTwill review the licensing review bases 35cument being developed for Combustion Engineering's Standard Safety Analysis Report-Design Certification (CESSAR-DC). Attendance by the following is anticipated:

Mr. Ward Dr. Remick Dr. Kerr Dr. Shewmon Mr. Michelson Mr. Wylic Severe Accidents /Probabilistic Risk Assessment, Date and location to be determined (July / August) (Houston). The Su5conmittee will review the method-ology for the ' treatment of uncertainties in the final version of NUREG-1150.

Also, the Subcomittee will review the results for the front-end reanalysis of the five plants studied. Attendance by the following is anticipated:

Dr. Lewis Mr. Ward Dr. Kerr Dr. Catton Mr. Michelson Dr. Corradini Dr. Remick Mr. Davis Dr. Sheunon Dr. Lee Dr. Siess Dr. Saunders (another statistician)

Advanced Reacter Designs, Date to be determined (July / August), Washington, DC (El-Zeftawy). The Subcomittee will review the draft SERS for the liquid metal reactors (LMRs). Attendance by the following is anticipated:

l Mr. Ward Dr. Siess Dr. Kerr . Mr. Wylie l Mr. Michelson Dr. Avery Dr. Remick Dr. Lee l

l

.: * * ~

Occupational and Environmental Protection Systems, Date to be determined (July / August), Wcshington, DC (Igne). The Subcommittee will review: (1) the "hot particle" problen, (2) monitoring the quality and quantity of airborne radionuclides in/out of containment following an accident, (3) the emergency planning rule, (4) the control room habitability report by ANL, and (5) other related matters. Attendance by the following is anticipated:

Dr. Remick Dr. Mark (tent.)

Mr. Carroll Dr. Shapiro Mr. Wylic Advanced Pressurized Water Reactors, Date to be determined (August), Bethesda, MD (El-Zefttwy). The Subcommittee will discuss the comparison of WAPWR (RESAR EF/90) design with other rodern plants (in U.S. and abroad). Attendance by the following is anticipated:

Mr. Ward Dr. Remick Dr. Kerr Dr. Shewmon Mr. Michelson Mr. Wylie Containment Requirements, Date to be determined (September / October), Bethesda, MD (Houston). The Subcommittee will review the NRC Staff's document on recommendations for containment performance and improvements (BWR Mark I only). Attendance by the folicwing is anticipated:

Mr. Ward Mr. Wylie Dr. Kerr Dr. Catton 7

Dr. Siess Dr. Corradini Decay Heat Removal Systems, Date to be determined, Bethesda, MD (Boehnert).

The Subcommittee will explore the issue of the use of feed and bleed for decay heat removal in PWRs. Attendance by the following is anticipated:

Mr. Ward Mr. Wylie Dr. Kerr Dr. Catton Mr. Michelson Mr. Davis Systematic Assessment of Experience, Date and location to be determined, (Alderman). The Subcommittee will review the Diagnostic Evaluation Program and other related licensee performance review efforts by the NRC Staff.

Attendance by the following is anticipated:

Dr. Lewis *

. Mr. Ward l Mr. Carroll Mr. Wylie Mr. Michelson l

l l

t

m -

e e

Thermal Hydraulic Phenomena, Date to be determined, Bethesda, MD (Boehnert).

The Subconmittee will discuss the status of Industry best-estimate ECCS model submittals for use with the revised ECCS Rule. Attendance by the following is anticipated:

Mr. Ward Dr. Catton Dr. Kerr Dr. Plesset Mr. Michelson Mr. Schrock Mr. Wylie Dr. Sullivan Dr. Tien Auxiliary Systems, Date to be determined, Bethesda, MD (Duraiswany). The Subconnittee will discuss the: (1) criteria being used by utilities to design Chilled Water Systens, (2) regulatory requirements for Chilled Water Systems design, and (3) criteria being used by the NRC Staff to review the Chilled Water Systems design. Attendance by the following is anticipated:

Mr. Michelson Mr. Wylie Mr. Carroll Decay Heat Removal Systems, Date to be' determined, Washington, DC (Boehnert).

The Subcennittee will review the proposed resolutions of Generic Issue 23, "RCP Seal Failures," and Generic Issue 99, "Loss of RHR Capability in PWRs."

Attendance by the followirg is anticipated:

Mr. Ward Mr. Wylie Dr. Kerr Dr. Catton Mr. Michelson Mr. Devis Auxiliary Systems, Date to be determined, Bethesda, MD (Duraiswamy). The Subcommittee will review the adequacy of the Staff's plans to inplement the recommendations resulting from the Fire Risk Scoping Study. Attendance by the following is anticipated:

Mr. Michelson Mr. Wylie Mr. Carroll I

- ,y ..

.' .' 1. .

~

APPENDIX IV OTHER DOCUMENTS RECEIVED 338TH ACRS MEETING MINUTES JUNE 2-4, 1988 PRESENTATION HANDOUTS Standardization of P!uclear Plants -

1. Tentative Schedule of Improved LWRs Subcommittee Report - l Standardization Rule;

2. RES Staff Presentation to the ACRS entitled "The Road to -

Certification" by Jerry N. Wilson, RES, dated June,2, 1988 Energency Planning

3. Proposed Rule, Emergency P'1anning Requirements for Fuel .

Loading and Initial Low Power Operations by Mike Jamgochian, '

dated June 2, 1988

4. Emergency Preparedness Rulemaking for Fuel Cycle and Other Material Licensees, dated June 2, 1988 Metal Components

5. Integrity of Reactor Vessels, dated June 2, 1988 World Association of Nuclear Operators

6. lementation of a Worldwide Association of Prcgress on the Imp (WAN0) by Thomas Eckered, undated Nuclear Operators

7. Slides presented by Stanley Anderson, INP0 Systems Interactions (USI A-17)

8. Unresolved Safety Issue A-17, "Systems Interactions in Nuclear i Power Plants," dated June 3, 1988

9. Draft Table 7.1, Classification of Concerns by Initiating '

Event (pages 45, 46, & 47), undated

10. Part 20 Revision, dated June 3, 1988 l

I

7

\ i ', i ?> e 338th ACRS Meeting IV-2 HANDOUTS (Staff)

1. Not used

2. Not used

3. a. Proj1ct Statu.< Report

, b. Memo for Renick from Boehnert, dated Fay 25, 1988, re Minutes

. of the ACRS Regional Programs Subcomittee meeting, May 24, 1988, Atlanta, GA *

4. Metal Components - Quality of Fasteners 3 a. Report of Metal Components Meeting on May 26, 1988 on Qu'ality of Fasteners, Periodic Inspection

b. SECY-87-296, Substandard /Cuunterfit Fasteners, dated 12/8/87

c. NRC Compliarce Eulletin No. 87-02, dated November 6, 1987

d. NRC Bulletin No. 87-02, Supplement 1, dated April 22, 1988

e. Memo for P. Shewmon from L. Shao, dated February 29, 1988, re Examination of BWR and PWR Reactor Vessels

5. a. Draft ACRS Report on Proposed Revision of 10 CFR Part 20, "Standards for Protection Against Radiation," dated May 31, 1988

b. 10 CFR 20 Proposed Revision

6. Trip Report to Japan, Fourth Regular Bilateral Meeting on Nuclear Regulatory Matters beld on May 12-18, 1988 by P. Shewmon

7. (notused)

8. Project Status Report on Thermal Hydraulic Phenomena Subcommittee Activity, dated June 3, 1988

9. Project Status Report on USI A-17, Systems Interactions

10. Mano for ACRS Members f rom R. Fraley, dated June 2,1988, re Futuro ACRS Activities, 339th ACRS Meeting, July 14-16, 1988 ,

11. Proposed Changes to the ACRS-NRC Menorandum of Understanding-Supplement ,

,1 l *'. , -

338th ACRS tieeting IV-3 Schedule ar.d Outline for Discussion at 338th ACRS Meeting TAB 3

1. Tentative Schedule

2. Memo for Wylie from Alderman, dated May 24, 1988, re Status Report, Subcomittee Chairman's Report on the Proposed NRC Rule on Standardization of Nuclear Reactors (10 CFR 52) -

3. Proposed Rule

4. ACRS Report, dated August 12, 1986, ACRS Coments on Proposed NRC Standardization Policy Statement

5. ACRS Report, dated October 15, 1986, ACRS Comments on Draft NUREG-1225, "Implementation of HRC Policy on Nuclear Power Plant Standardization"

6. Policy Statement on Standardization of Nuclear Power Plants, Federal Register (43 FR 38954), August 31, 1978 TAB 4

1. Minutes of Planning Meeting for International Conference on Quality, held on May 10, 1988, dated May 16, 1988 TAB 5

1. Final Rule on Emergency Preparedness for Fuel Cycle and Other Radicactive Material Licensees

2. Proposed Rule on Emergency Planning and Preparedness Requirements for Nuclear Power Plants Fuel loading and Initial Low-Power Operations, SECY-88-109, dated April 20, 1988

3. ACRS Report, dated July 16, 1986, ACRS Contents on Emergency Planning Requirements for NRC Licensees TAB 7

1. Project Status Report from the Advanced Reactor Designs Subcommittee, dated June 2, 1988 TAB 8

1. Memo for C. Wylie from R. Major, dated May 25, 1988, re Sumary of the ACRS Subcomittee Meeting on Babcock & Wilcox Reactor Plants, May 3-4, 1988, Washington, D.C.

2. Letter for Major from Davis, dated May 18, 1988, re coments on subcomittee meeting

3. Memo for Wylie from Major, dated May 10, 1988, re coments by Harold,Etherington, ACRS Consultant, Regarding Glenn Reed's Question on a Possible Cold Block to Natural Circulation in a B&W Reactor (Official Use Only) l 4. Memo for Wylie from Reed, dated May 10, 1988, re Reassessment of B&W Reactor Subcomittee Meeting on May 3-4, 1988 i

S. Memo for Wylie from Reed, dated May 4, 1988, re G. A. Reed Deferred Questions from the B&W Subcomittee Meeting on May 3,1988

6. Memo for Major from Catton, dated May 24, 1988, re B&W Subcomittee Meeting, 1717 H Street, N.W., Washington, D.C., May 3, 1988 L

. m , a. v. .

o .u

-o IV-4 TAB 9 ,

1. Memo for ACRS Members / Staff from Duraicwamy, dated May 19, 1988, re

, Status Report - Review of the Proposed Prior!ty Rankings

2. Memo for Michelson et a'l. from Siess, dated March 10, 1988, re Assignments for Reviewing Proposed Priority Rankings for Generic Safety Issues - Fifth Grcup

3. Tele A - Generic Issues Reviewed by the ACRJ During the 338th, June 2-4, 1988 Meeting ,

4. Table 1 - Assignrents for Reviewing the Proposed Priority Rankings i for a Fifth Grcup of Generic Issues

5. Sample Format TAB 11.1

1. Future ACRS Subcomittee Meetings i TAB 11.2 (blank)

TAB 12

. 1. Presentation Schedule ;

2. Memo for ACRS Members from Quittschreiber, dated May 17, 1988, re p Proposed Resolution of USI A-17, "Systems Interactions in Nuclear !

Power Plants" '

3. Draft Memo for Jordan from Beckjord, undated, re CRGR Review of the !

Revised Proposed Resolution of USI A-17 ,

l 4. Executive Sunrary of NUREG-1229 l

5. Draft Generic Letter on Resolution of Unresolved Safety Issue A-17

6. Basis for Resolution of USl A-17 i

7. Draft Verification of Licensee Actions in Response to Generic l tetter l 8. ACRS Report, dated May 13, 1986, ACRS Coments on Proposed Resolu-tion of USI A-17. "Systems Interactions in Nuc1'nr Power Plants"

9. ACPS Report, dated August 1,1986, Response to ACRS Coments on Proposed Resolution of USI A-17, Memorandum dated May 13, 1986 l 10. Memo for Asselstine from Stello, dated July 22, 1986, re Proposed Pesolution of USI A-17 l 11. Pages from 321st ACRS Meeting Minutes, January 1987, discussion en l Systems Interactions l 12. Memo for Fraley from Malsch, dated August 6,1986, re Application ;

of the Backfit Rule to the Resolution of USI A-17 !

l 1

l TAB 13.1

1. Subcommittee Chairman's Report on Advanced Boiling Water Reactor (ABWR) meeting held on June 3, 1988 TAB 17.1

1. Memo for ACRS Members / Technical Staff from Duraiswamy, dated May 24, 1988, re Status Report - Cojoining of Subcomittees

2. List of ACRS Subcomittees by Subject Areas

3. Propos91 by Michelson for Reducing 14 Subcomittees to 7 and t

! Establishing New Subcomittees '

4. Existing Subcomnittees and Tasks l

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