ML20059C742
| ML20059C742 | |
| Person / Time | |
|---|---|
| Site: | River Bend, 05200001  |
| Issue date: | 03/02/1993 |
| From: | Shewmon P Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| REF-GTECI-120, REF-GTECI-NI, TASK-120, TASK-OR ACRS-2861, NUDOCS 9311010287 | |
| Download: ML20059C742 (41) | |
Text
-
, v y-i rtifi By. 'I P~ '9emn - 2/15/93~ YI h YduN '1 l3lj. IU1d10 b
$ 1 TABLE OF CONTENTS MINUTES OF THE 392ND ACRS MEETING DECEMBER 9-11, 1992 I. Chairman's Report................................. 1 II. Station Blackout Rule............................. 1 III. Technical Specification Improvement Program....... 5 IV. Advanced Boiling Water Reactor Design............. 6 V. River Bend Nuclear Plant Reliability Monitoring Program................................ 7 7 VI. Protection Against Lightning and Electrical Transients for Nuclear power Plants............... 8 VII. Election of ACRS Officers......................... 10 VIII. Generic Issue-120, Online Testability of Protection Systems........................... 10 IX. ACRS Subcommittee and Members Activities.......... 11 X. Future ACRS Activities............................ 12 XI. Appointment of New Members........................ 14 .
XII. Meeting with the Director, Office of Nuclear Regulatory Research............................... 14 XIII. Preparation for Meeting with NRC Commissioners................................... 16 XIV. Meeting with NRC Commissioners.................. 16 XV. Upgrade of ACRS Conference Room................. 16 XVI. Reconciliation of ACRS Comments and Recommendations................................. 17 '
XVII. Miscellaneous e Computers in Nuclear Power Plant Operations.................................. 17 1 XVIII. Preparation of Other ACRS Reports and .
Memoranda...................................... 17 l XIX. Summary / List of Follow-up Matters............... 18 DES CFATD GPIG!NLL
.. s m 9311010287 930302 SO
2861 PDR .!.a".
y ". l i
1 ii l 392nd ACRS Meeting Minutes l XX. Executive Session e Reports to the Commission................... 19 e Letter...................................... 19 e Memoranda.................................... 19 -
Supplement - Proprietary - Official Use Only
[ SUPPLEMENT REMOVED - FOIA EX(b) (4)]
1 l
l 4
1 i
i
)
- 3
.q iii
)
APPENDICES MINUTES OF THE 392ND ACRS MEETING ,
DECEMBER 9-11, 1992 I. Attendees II. Future Agenda III. Future Subcommittee Activities f IV. List of Documents Provided to the Committee i
e b
-e E
I t
[
i l
f s
I 6
7 I
, . - - . . . - - ., . . . - . _ - . _ r . . - - -. _ - _ _ - -
_m _ _ _ _ _ . --e
M.o i
QY (&z,
, , . . Federal Register / Vol. 57. No. 229 // Friday.. November 27.1992 /.Not 'e 56387 after l'ebru.ary 8.1993..will be . .
Proposal Instructions and Fonns serm : renerstors. Representatives of the nudcar l considered forFY93 funding to the . industry will participate, se appropriate. !
cxtent practicable. Questions c.oncerning the... -precedin.g' s p.m-2 p,m.:Technico/Specifecouans ;
m
. formation, copies ~ci application forms. Impmvement Pmsmm (Open)--ne Funds and applicable regulations'shall be ' Committee will hear a briefing by and hold i For Fiscal Year 93, the U.S. Nudear obtained from or submitted to'(Graitt"~ discussions withwpresentatives of the a j l ~
Regulatory Commission. Office of . epplication packages. Stand &rd Form 4 4 NRC staff on the status of the NRC stafra ;
Nudear Regulatory Rese'a rch' 424. must be requested in writing): U.S. . work on the technical specifications anticipates making a total of Nudear Regulatory Coi6 mission. ATTN; impmvement program. Representatives of th ar dustry wm part(cipate,as approximately $1.240.000.00 available ~
Grants Officer. Division lof Contracts - ( : , ,
for funding research grants to and Pmpeny Managemen%il Stop P- 2p.m.-mp.arAdmacedBolling water educationalinstitutions.Of this amount.. 841. Office of Administration. .
&=xte&sWOpen)-m camim approximately $730.000.00 will be . Washington,DC 20555. ' i 7' * ' , will hea'r a brierms by and hold ~ discussions available for new research grants in FY . The address forhand-carriedf. J with representatives of the NRC staff -
applications U.S. Nuclear R latgry ) : regarding thstafus of the'starre reviedof
' grant 93.Becausedthislimitatbn.
budgets should be restricted to . .
proposed. . Comm%sionJ,is:T7N;Qrpes gcepfy 6e,,,gde,slg ,
. about $50,000.00 per year. with total - 9 Divialon of C@ tracts ap , 4 .nmroday, December to.1902 6 9 - ... .
- project fimpmg nol_texceeding 7,L_ ; en
, d , # -mo.miMiurOR/veEBendRebbility' %
$100 g g y.eq pergpd of,twpyears, . ..Be6esda MDMUFr?' Me
{P ,
... Monitoring pogram (open/ Closed}--ne Evakiation -- Process ;
- i '"l" '. ~ t
~
M.'
'.' I . ' Note:Upo' W appM V.' Cmnsluce wGl bear a briefing by and hold n deh'ery:foithe v
r(td D - discussions with, representatives of the '
Allpropos. als rec.eived as.a result of . the NRC guard desk (at the above address).4, _ '- Gulf State.Utlhties (lleensee)[re this announcement will be evaluated by the guard should be requested to telephonef/ o relisbuity monitodng program.thet is being . .
an NRC review pelial.'~.. the DMalon of Contracta,and Property,s'.x; , used at the Rivpr Bend Nuenger Plant to c.
'-5
- Management (Extension,22054) for a pick-up ; improve the effectivenese of the .
Evaluation Criteria .. '9. * ' of h applicadon/ ' '
- '^ i (g - maintemnce program. RepseediaGves, of
~
The award of NRC grants is Nothlhg la this solicita' tion should be 6e NRCataH wW panidpate, as, _ ',
discretionary. Generally, projects are -
. supported in order of ment to the extent. oc'nstrued as' committing the NRC to 4 ~ be do di permitted by available funds. dividing available funds among all Proprietary information related to this qualified applicants. matter. .
Evaluation of proposals for research 'e-projects will employ the following a day of . m15 ca-Jb5 anuMtio'nfor. .
cntena. N6 level of imgiottance is NovemberJ992. ~
Rulemakirtg-Pmtection Against Lightning 1 and Electrical Tmnsients for Nuclear !
Implied by the order in which these For the U.S. Nudear Regulatory Commission.
ibwerPlants (Open)-ne Committee will criteria are listed. . Dennis Tarner. .
hear a briermg by and hold discussions
- 1. Adequacy of the research design. .Cmnts O/fie.. Division ofContmets cad - ,
with representatives of the NRC staff
- 2. Scientific significance of proposal . PmpatyManosement. Office of,,y ., , , . regarding the status of the stafra review cf .
- 3. Technical adequacy of the Administmtion. - - ' -l f- , - a Petition for Rulemaking to, amend the .
investigators and their institutional (FR Doc.22-2NS8 Filed hM a,i453m)) NRC rules and regulations to add Ughtning' bass. '
a coot - ,.,
em induced and other electrical transients to -
the hat of phenomena est hcemed nuclear
- 4. Relevance to a tesearch area (s) . . ,
i d hd bo ~' I I Reasonab e esa of esti[nated costin. Advisory Comrnittee ott Nector .. I#
P ""I'* "" N "y*"I'IF A *~~~
y ,
{',I'8 relation to the work to be performed and Safeguards; Meeting Agenda .,J -
repon& Planning and PMres anticipated result.- .- .
-In acEordance with the ses 'd.; Subcommittee regarding items proposed for
- 6. Potential benefit of the project to consideration by the fun Committee.-
1 the overall benefit of the institution's uch M % d W? ',
JJap.m-sparPmposedResolution of ;
graduate research program.- ., Eurgy Act (42 U.S.C. 2039,2223b), the Advisory Committee on Re~ actor - Generic 1ssue.rm Online rescobilit l Evaluation of p posals for -, pm,,cgfo, yg ,,,,," gopen)__n, y of professional meet gs, conferences, Safeguards wGM a meeung on Commitwe wm review and comment on the !
symposia, etc., will employ the following December 9-12.1992,in room P-110 NRC staffs proposed resolution of Generic 1 criteria.' 7920 Norfolk Avenue,Bethesda, Issue 1203epresentatives of the NRC staff
- 1. Potential usefulness of the prop sed Mar %and.Nodce d &ls meeung was and 6e derindustry wm pamcipam as project for ihe advancement of scientific published In the Federal Register on appropriate.
2#p.m-Mp.nu Activities of ACRS knowledge. O & M 992. s .-
Subcommittees andMembers (Openl--ne
- 2. Clarity of statement of objectives, Wednesday, December S.1992 - . Committee wm hear reports and hold i methods, and anticipated results.. dJo a.mede o.ou Openly Remorisby . discussions of ACRS Subcommittee .
- 3. Range ofissues covered by the - ACRSChairman (Open). .he ACRS. activity on assigned topics, indwbng the sneeting agenda. .
Chairman will make opening remarks -
conduct of Committee activities by h ;
- 4. Qualifications and experience of regarding conduct of the meeting and Planning and Procedures Subcommittee l project speakers. comment brie 0y regard'eg items of current and the NRC Senior Management Weting
- 5. Reasonableness of estimated cost in interest.De Committee will discuss .
on the Organiz.etional Factors Researth relation to anticipated results. pr6 rities i r preparation of regiorts during Program.
this sendon.
- ~
320 p.m.~4 p.m,.: Election of ACRS Offkers Disposition of Proposals ~ af em-22 Noon-Staten Blockout Rule (Open/ Closed)--ne Committee will select
) tOpen}-ne Committee will review and its Officers for Calendar Year 1993.
Notification of award will be made by comment on the proposed final amendment the Grants Officer, and organnations Portions of this session wm be closed. as whose proposals are unsuccessful will to the Station Blackout Rule (10 CFTL 50 63) appropriate. to discuss information the and the ossociated Regulatory Guide 1.9. release of which would represent a cicarly be so advised. Rev. 3. regarding the rehability of diesel unwarranted invasion of personal pnvacy..
.../- l l g f!.
1 mana rederal Register / Vol. 57. No. ::29 / Friday. November 27, 1992 / Notices J o m 4 p m : Apfustment of New Memkrs limited to selected portions of the 1,
[Open/ClosedHThe Committee mil Commission to suspend any I discuss the quahficat6ons of candidates meeting as determined by the Chairrman. consideration of extending or modifying ,
y proposed for appointment to the Information regarding the time to be set - the construction permit for Unit 2 of the '
aside for this purpose may be obtained facility until msolving any proceeding ose d5 u info o th 1 of by a prepaid telephone call to the ACRS on the license for Unit 1.
which would represent a clearly Executive Director prior to the meeting. petitioners asserted as a basis for
) unwarranted invasion of pen onal pnvecy. In view of the possibility that the 5 p.m.-ap.m/ Preparotion of A CRS Reports their Motion that the licensee failed to schedule for ACRS meetings may be j;$ /Open/-The Committee wi# discuss p/PPoSedrPPorts regarding items adjusted by the Chairman as necessary . demonstrate the necessary character
' and capability that are the primary considereddurms this meeting. to facilitate the conduct of theinecting, factors to be considered in granting a Friday. December 11,1992 persons planning to attend should check license, and has shown a " downward with the ACRS Executive Director if spiral"in violations and reportable s.JO a.m.-Ja45 a.m; Meeting with the such rescheduling would result in major incidents. petitioners also assert Driector. O/fice o/Nucicar Regulatory inconvenience. .-
Resectrh (Open/ Closed) -The Committee , wrongdoing by the NRC Region IV staff.
I have determined in accordance with To support this general assertion. the will hear a briefing and hold discussions on subsection 10(d) Public Law 92-483 that the NRC's safety research program. Petitioners alleged that numerous It is necessary to close portions of this specific incidents occurred since meluding the impact of the budget -
M t p meeting noted above to discuss eO November 1991 ine,luding-
_ Proprietary Information applicable to (1)100 mile-per-hour winds in the existing and proposed research contreets. the matters being considered per 5 ,
portions of this session will be closed as U.S.C.552(c)(4),information the access tunnel between Units 1 and 2 lL necessary to discuss Information the premature disclosure of which would be resulted in an employee being blown premature disclosurt! of which would be into a radiation area;
- . likely to significantly frustrate proposed likely to significantly frustrate proposed,. (2) Resin was spilled into the core
- -
, agency action.- agency action per 5 U.S.C. 552b{c){9)(B -
.w and information the release of which ' (3) A " hot" valve was cut in two JJ o.m.-12 Nooni Prepomtion forMeeting causing a radiation release and
' 'would represent a clearly unwa:Tanted
- yNR
, ]Ign *
. invasion of personal privacy per 5 U.S.C.
exposure to severalindividuals; (4) 20 documented" reportable d
' interest with the NRC Commissioners. 5%cM -
. . f:30 a.m.-J p.m; Meetiry with the NRC . Further information regarding topics . Incidents" numerous areas showing 9~ ~ Commissioners (Open).--The Committee to be discussed. whether the meeting concern by Region IV, and at le.ast 8 will meet with the NRC Commissioners to has been cancelled or rescheduled, the. ..
[ discuss topics of mutual interest. Chairman's ruling on requests for the reactor.
(5)The NRC trips; p ; ' ropose.
d fines for it 3:3&o p.m; Pmporotion of A CRS Reports opportunity to present oral statements violations nearing $100.000 for 1992; (j (Open)--The Committee will discuss (6)The spent fuel pool was without
. pmPosed ACRS mports to the NRC . and the time allotted can be obtained by cooling water for approximately 20
^
- regard items considered during this ' a prepaid telephone call to the ACRS Executive Director Mr. Raymond F.
empe t
, Fraley (telephone 301-492-8049)*
(I, . Saturday. December 12.1992 ; between 8 a.m. and 4:30 p.m. e.s.t. (7) A photograph showing control A30 can.-f:Jop.m; Pmporotion ofACRS Dated; November 20,1992. -
room personnel asleep is widely
- RePods (OpmW Conunluee wul cir'culated in the plant; and discuss proposed Committee reports Andrew 1. Bates. (8)The license failed to label and regarding items considered during this. Actirg Committee Monogement Officer. mislabeled pressure valves and limit meeting. - ,
1;Jop.m.-2:30p.m; Miscellaneous (Open)-- IFR Doc. 92-28713 Filed 11-25-02: 8:45 am) switches. - -
e m .o coot neo e The Director of the Office of Nuclear The Committee will discuss mauer:
considered but not completed at previous Reactor Regulation has decided to deny meetings as time and availabili.ty of (Docket Nos. 50-445 and 50-446] the Petition. The reasons for this denial
~
infonnatim Permh. .
M -
are explained in the " Director's Decision Proce'dures for the conduct of an'd . as Under 10 CFR 2.208."(DD42-06) which
- participiation In ACRS meetings were teamh Sta t is availablefor public inspection at the published it; the Federal Register on ' *" 8"*"#" #W8 * *
- Commission's PublicDocument Room, the Celman Building 2120 L Street. NW.,
October 16.1992 (57 FR 47494).In . ' Notice is hereby given that the; '
Washington. DC 20555, and at the local
' .accordance with these'procediires. oral Director. Office of Nuclear Reactor i l or written statements may be presented Public Document Room for the
! ^ by members of the public, reconiings .
Regulation, has taken action with regard C-Ae Peak Steam Electric Station.
- to a Petition for action under 10 CFR -
will be permitted only during those open . 2.206 received from Sandra Library; liong Dow . - at the Government University Publication of Texas at
/ Maps, portions of the meeting when transcri vis being kept, and questions 2nay be'lpt ~
.and R.Micky May 19.1992, Dow(Petitioners) regstding the Comanche dated - 701 South Cooper, P.O Box 19497 asked only by members of the - ArlingtoneTexas 76019. A copy of the
~
Committbe; itfoonsdltants'and staff.
Peak Steam Electric Station. Units 1 and decision will be filed with the Secretary
- 2. - >
Persons desiring toy.ake oral for the Commission's review in
- - The Petitioners requested that the statements should notify the ACRS accordance with10 CFR 2.20S(cl of the
' Commission order the immediate Comrhission's Regulations. As provided Executive Director Mr.Raymond F. shutdown of Unit 1 of the Comanche by this regulation, the Decision wdl Fraley, as far in advance as practicable Peak Steam Electric Station and l constitute the final action of the so that appropriate arrangements can be institute a proceeding to modify.. Commission 25 days after the date of made to allow the necessary time during suspend. or revoke the license held by issuance of the decision unless the the meeting for such statements. Use of Jhe Texas Utilities Electric Company still, motion picture. and television - Commission on its own motion institutes (TU Electric or the licenseel for Unit 1. a review of the decision within that cameras during this meeting may be . 'The petitioners also requested the time.
i
gorco
/ UNITED STATES l !" n NUCLEAR REGULATORY COMMISSION
- l g yc ADVISORY COMMITTEE ON REACTOR SAFEGUA,RDS,_ '
o, WASHINGTON, D. C. 20555 '
'% $g -
Revised: Decemf>er 7, 1992 y * -
U /
SCHEDULE AND OUTLINE FOR DISCUSSION 392ND ACRS MEETING DECEMBER 9-12, 1992 Wedr}esday, Decetnber 9, 1992. Roon P-110, 7920 Norfolk Avenue, Bethesda, Md.
- 1) 8:30 -
8:45 A.M. Openina Remarks by ACRS ChairmaD (Open) 1.1) Opening statement (PGS/SD) 1 1.2) Items of Current Interest (PGS/RFF) 1.3) Priorities for preparation of ACRS i reports (PGS/SD) 1 1.4)
Consider Agenda Item 19, Reconcil-iation of ACRS Comments and g
Recommendations (PGS/SD)
- 2) 8:45 -
12:00 Noon Station Blackout Rule (Open)
(10:00-10:15-Break) 2.1) Comments by the ACRS Subcommittee Chairman regarding the NRC staff's proposed amendment to the Station TAB 2------- Blackout Rule regarding diesel generator reliability (CJW/HWL/DC) 2.2) Meeting with representatives of the NRC staff and the nuclear industry, as appropriate 12:00 -
1:00 P.M. LUNCH
- 3) 1:00 -
2:00 P.M. Technical Specification Inorovement Procram (Open) 3.1) Comments by ACRS Subcommittee Chairman regarding the status of the TAB 3-------
technical specification improvement program (JCC/DC/MDH) 3.2) Meeting with representatives of the NRC staff 2:00 -
2:15 P.M. BREAK
,,lR.
~.
-+ ', i l
l 2
l 3.3) 2:15 -
2:45 P.M. Discuss Proposed ACRS Reports-(Open) 3.3-1) Proposed report regarding the safety implications of. digital technology 14.
nuclear plants (HWL/DC)
- 4) 2:45 -
3:15 P.M. Advanced Boilina Water Reactor Desian (Open) 4.1) Comments by ACRS Subcommittee TAB 4-------
Chairman regarding status of review-(CM/MME/EGI)
Thursday, December 10, 1992, Room P-110, 7920 Norfolk Avenue, Bethesda, Md.
- 5) 8:30 -
10:00 A.M. River Bend Nuclear Plant Reliabilit'y Monitorina Procram (Open/ Closed) 5.1) Remarks by ACRS Subcommittee Chairman TAB 5------- (JCC/EGI) >
5.2) Meeting with representatives of the Licensee and the NRC staff, as appropriate (Note: Portions of this session may be closed as necessary to discuss Proprietary '
Information related to this matter.)
10:00 -
10:15 A.M. BREAK
- 6) 10:15 -
11:45 A.M. Protection Acainst Lichtninc and Electrical Transients for Nuclear Power Plants (Open) 6.1) Comments by ACRS Subcommittee TAB 6-------
Chairman regarding NRC staff response to a proposed petition for rulemaking that requests that the NRC amend its regulations to include protection against lightning and other electrical transients on the list of phenomena that nuclear power plants must safely accommodate (CJW/DC) 6.2) Meeting with representatives of the NRC staff and the nuclear industry, as appropriate
- 7) 11:45 -
12:30 P.M. Election of ACRS Officers (Closed) 7.1) Select ACRS Officers for CY-1993 '
(PGS/RFF)
(Note: Portions of this session will be closed, as appropriate, to discuss intornation the release of which would
,, represent a clearly unwarranted invasion of personal privacy.)
"' ' }
~
12:30 -
2:00 P.M. LUNCH
4 i
3
- 8) 2:00 -
3:30 P.M. Generic Issue-120, Online Testability of Protection Systems (Open)
- 8.1) Comments by ACRS Subcommittee TAB 8------- Chairman regarding the NRC staff's proposed resolution of this generic safety issue (CJW/DC/MME) 8.2) Meeting with representatives of the NRC staff and the nuclear industry, as appropriate 3:30 -
3:45 P.M. BREAK
- 9) 3:45 -
4:30 P.M. ACRS Subcommittee and Members Activities (Open) 9.1) 2:45-3:15 P.M.: Planning and Procedures Subcommittee meeting (PGS/RFF)
TA B----------- 9 . 2 ) 3:15-3:30 P.M.: Report on the NRC Senior Management Meeting on the organizational Factors Research Program (JCC/PAB)
.10) 4:30 -
5:15 P.M. Future ACRS Activities (Open) 10.1) Discuss recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the Committee (PGS/RPS)
- 11) 5:15 -
6:00 P.M. Apoointment of New Members (Closed) 11.1) Discuss qualifications of candidates ;
proposed for appointment as members l (PGS/MFL) l (Note: Portions of this session will be !
closed, as appropriate, to discuss information the release of which would represent a clearly unwarranted invasion of ;
personal privacy.) )
i Friday. December 11, 1992, Room P-110,'7920 Norfolk Avenue, Bethesda, lid.s
- 12) 8:30 -
10:45 A.M. Meetina with the Director, Office of Nuclear Reaulatory Research (Open/ Closed) 12.1) Comments by ACRS Chairman (PGS/PAB)
TAB 12------ 12. 2 ) Briefing by and discussion with Eric Beckjord, Director, Office of Nuclear
,s.
Regulatory Research, regarding the NRC research program (Note: Portions of this session will be closed as necessary to discuss information
j 4
1 the premature disclosure of which would be likely to significantly frustrate proposed agency action.)
10:45 -
11:00 A.M. BREAK
- 13) 11:00 -
12:00 Noon Preparation for Meetina with NRC Commissioners (Open) 13.1) Discuss. topics of mutual interest TAB 13-------
f r the meeting with NRC Commis-sioners as follows:
13.1-1) Digital Control and Protection Systems (HWL/DC) 13.1-2) Implementation of Plant Life Extension Rule (PGS/EGI) 13.1-3) Risk-Based Regulation (HWL/MDH) 13.1-4) Status of Advanced Reactor Reviews as needed (CM/JCC/MME/EGI) 12:00 -
1:00 P.M. LUNCH
) 1:00 P.M. Depart for One White Flint North
- 14) 1:30 -
3:00 P.M. Meetina with NRC Commissioners'(Open) 14.1) Meeting with NRC Commissioners to discuss topics noted above (PGS/SD) 3:15 P.M. Depart for Phillips Building
- 15) 4:00 -
5:00 P.M. Unarade of ACRS Conference Room (Open) 15.1) Briefing by J. C. Carroll, Mike MacWilliams, and Mark Stella
- 16) 5:00 -
6:00 P.M. Preparation of ACRS Reports (Open) 16.1) Discuss scope and content of proposed reports to the NRC regarding matters considered during this meeting Saturday, December 12. 1992. Room P-110. 7920 Norfolk-Avenue. Bethesda. .
Md. l
- 17) 8:30 -
11:30 A.M. Discuss Proposed Reports to NRC '(Open) 17.1) Discuss proposed reports on:
17.1.1) Amendment to Station Blackout Rule (CJW/HWL/DC).
-)
17.1.2) Generic Issue 120, Online N-Testability of Protection Systems (CJW/DC/MME)
I' s
0 %
g 5
- 18) 11:30 -
12:30 P.M. Reconciliation of ACRS Comments and Recommendations (Open)
- 18.1) Discuss replies from the NRC ;
Executive Director for Operations regarding proposed reconciliation of .
ACRS comments and recommendations (PGS, et al./SD)
- 19) 12:30 -
1:00 P.M. Miscellaneous (Open) 19.1) Complete discussion of matters considered.during this meeting and matters considered but not completed.
at previous meetings as time and availability of information permit
=
1
]
l
$ N j h
'l f'E I: ?; (
Certified By: .J P. Shewmon - 2/15/93 i MINUTES OF !
392ND ACRS MEETING DECEMBER 9-11, 1992 The 392nd meeting of the Advisory Committee on Reactor Safeguards was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Md., on December 9-11, 1992. The purpose of this meeting was to discuss and take appropriate action on the items listed in the attached i agenda. The entire meeting was open to public attendance, with the exception of a portion that dealt with the selection of new Committee members and other matters of a personal nature. There i
were no written statements nor requests for time to make oral statements from members of the public regarding the meeting.
A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room. (Copies of the transcript are available for purchase from Ann Riley & Associates, Ltd., 1612 K Street, N.W., Washington, DC 20006.)
l ATTENDEES ACRS Members: P. Shewmon (Chairman) , J. Carroll (Vice Chariman) , J.
E. Wilkins (Member at Large), I. Catton, P. Davis, H. Lewis, W.
Lindblad, C. Michelson, T. Kress, and C. J. Wylie.
I. Chairman's Report (Open)
Note: Mr. S. Duraiswamy was the Designated Federal Official for this portion of the meeting.
Dr. Shewmon, ACRS Chairman, opened the meeting at 8:30 a.m. and mentioned the following matters:
e The agenda for this meeting. i e Welcomed Mr. Peter Davis as an official ACRS member.
e Discussed priorities for the proposed ACRS reports and letters to be discussed at the meeting.
- Acknowledged the license renewal comments that commissioner Curtiss made in a memorandum on this subject.
II. Station Blackout Rule (open)
Note: Mr. S. Duraiswamy was the Designated Federal Official for this portion of the meeting.
l Introduction Mr. Wylie, Chairman of the Control and Electrical Systems Subcommittee, and Dr. Lewis, Chairman of the Probabilistic
4 392nd ACRS Minutes 2 Risk Assessment Subcommittee, introduced the matter regarding the NRC staff's proposed amendment to the Station Blackout Rule on diesel generator reliability.
Los Alamos National Laboratory' Presentation Dr. Martz, Los Alamos National Laboratory - consultant to the NRC staff, presented the results of his research on alternative trigger procedures, which he conducted for the NRC Office of Nuclear Regulatory Research. A Sequential Probability Ratio Test (SPRT) method was studied as an alternative to the staff's proposed trigger values for detection of any degradation of the underlying reliability of emergency diesel generators. Monte-Carlo simulation was used to analyze the performance of the SPRT methods relative to the -
staff's proposals.
Dr. Martz's conclusion was that SPRT methods, which were designed to provide a false-alarm probability similar to that of the staff's proposed triggers, were observed to provide generally better detection of reliability degradation than the proposed triggers. Other SPRT methods could be made even more superior, at the cost of increased false alarms.
Committee Members comments Dr. Kerr, ACRS consultant, asked if it is possible to depend on sources of emergency power that are not Class 1E. Mr. F.
Rosa, NRR, answered that some plants will provide non-Class lE diesel generators separate from the required Class 1E diesel generators to meet the requirements of the Station Blackout Rule.
Dr. Lewis pointed out that the proposed methods are not able to discern, in a practical period of time, the change in a given diesel generator's reliability from 0.96 (just above the i 0.95 threshold) to 0.94 (just below the threshold).
Mr. Carroll noted that industry data indicates some diesel generators are being tested 120 times per year, far in excess of the usual Technical Specification requirements. Mr. Rosa acknowledged that it might be appropriate for the NRC to consider the reasons for this number of tests. Dr. Lewis said that even those diesel generators with acceptable underlying reliability that receive a large number of tests will have
" false alarms." Mr. Rosa added that the staff has reviewed industry data and has concluded that the amount of testing did not significantly affect the reliability of the diesel generators.
a 392nd ACRS Minutes 3 Mr. Lindblad observed that the simulation analysis does not account for the repair of the cause of the failure, and i therefore does not model actual diesel generator reliability '
af ter restoration from a test failure. Dr. Martz replied that the simulation only accounts for the " worst case" situation in ;
which the diesel generator is restored to service without l having corrected the underlying cause of failure, so that the assumed reliability has not changed.
Dr. Lewis pointed out that the SPRT method appears to differ from a Bayesian approach in that past performance history is used to assess the current state of diesel generator reliability. Dr. Martz agreed.
NRC Staff Presentation Mr. Minners, Director of the Division of Safety Issue Resolution, noted that the proposed rule amendment was not fundamentally changed during the reconciliation of public and industry comments. As a regulator, his concern is that although diesel generator performance has improved generally, it could just as easily degrade in the future. Data provided by resident inspectors indicates that in general the maintenance unavailability of diesel generators is about two percent while at power, and about 12 percent while shutdown.
This unavailability would be prevented from becoming excessive through compliance with the Maintenance Rule. Although the staff's efforts have been directed toward preparing a Station Blackout Rule amendment, the Commission' paper discusses four options, ranging from implementation of the proposed amendment to no action. The staff will not recommend a single approach, or order the options in any way.
Dr. Kerr pointed out that the Brookhaven study, provided as background material to the Committee, suggests that changes in unavailability from two percent to six percent give rise to approximately double the overall core damage frequency, which is not significant given the uncertainties of the analysis.
Mr. Minners replied that in spite of the uncertainties, the proposed amendment will standardize how the industry monitors diesel generator performance.
Mr. Abramson, RES, noted that the proposed amendment was not intended to require estimation of underlying reliability, which could not be done well due to the uncertainties involved, but rather to require monitoring of diesel generator performance. Dr. Lewis *:ook exception to the inference that statistical methods can not provide a basis for estimating reliability, noting that it is a question only of quantifying the uncertainty.
392nd ACRS Minutes 4 Mr. Carroll pointed out that the staff has enforcement means available, without the proposed amendment, to encourage licensees to maintain highly reliable diesel generators, and has used these means in the past. Mr. Minners replied that although the staff historically has been able to get licensees to respond to these issues, the proposed amendment makes an NRC response to a future degraded diesel generator "more enforceable." Mr. Lindblad noted the staff's statement in the draft Commission paper that if a plant should exceed the double trigger for no other reason than chance, this circumstance will be taken into account in determining the appropriate enforcement action. Several Committee members and Mr. Minners expressed disagreement with this position.
NUMARC Presentation, Mr. Alex Marion, NUMARC Mr. Marion stated that NUMARC's position is to support a performance-based or results-oriented approach to the regulatory process, but that additional regulations for diesel generator performance were not necessary in view of existing industry initiatives and regulatory requirements. NRC action to create new enforcement options in this area would send a
" strong message" to industry regarding how the NRC will deal with self-initiated improvement programs.
Mr. Carroll asked if any utility has ever reached a trigger threshold. Mr. Marion replied that based on discussions with member utilities, NUMARC is aware that several utilities had l at one time exceeded the NUMARC trigger, and one utility recently reached the double trigger.
Mr. Carroll asked if the wide disparity in number of tests performed on different diesel generators was a concern. Mr.
Marion indicated that NUMARC was looking into the need for further action with regard to this matter.
Mr. Davis asked if NUMARC had any data that showed diesel generator start successes / failures as a function of actual events (not testing) . Mr. Marion replied that NUMARC included both testing data and plant event data in its plant performance indicator program. Mr. Rosenthal, AEOD, added that AEOD had done a study of diesel generator demands due to loss of power to the emergency bus, and in each case over a ,
five year period, all diesels started and ran.
Conclusions The Committee prepared a report on this matter to Chairman Selin, as noted in Section XX below. Also, the Committee directed Mr. Fraley to send a letter to Alex Marion, NUMARC, ;
)
i 392nd ACRS Minutes 5 requesting clarification of some information that he had previously sent to the Committee.
III. Technical Snecification Imorovement Procram (TSIP) (open) 1 Note: Mr. M. D. Houston was the Designated Federal Official for this portion of the meeting.
Introduction Mr. Carroll, Chairman of the Plant Operations Subcommittee, introduced this topic to the Committee and indicated that this would be a periodic briefing on this topic.
NRC Staff Presentation Mr. C. Grimes, NRR, made some brief introductory remarks. He noted that the staff had last. briefed the Committee on this matter in December 1991. At that time, the staff has received a large volume of comments (about 27,000) directed toward the draft standard technical specifications. Since then, and following a briefing to the Commission, the staff had received a Staff Requirements Memorandum dated January 30, 1992 that requests the staff to address various aspects of the TSIP.
Mr. Schulten, NRR, briefed the Committee on the status of the TSIP. During his presentation he discussed the following topics:
e Specific Improvements e The Resolution of Comments e Major Technical Issues e Implementation Policies and Practices ,
e STS Conversion Plans e Future Actions Mr. Schulten indicated that 60% of the comments on the draft Standard Technical Specifications (STSs) were editorial changes. As part of the resolution process the staff has scheduled about 20 public meetings with the commenters. Many of the issues in previous technical specifications, which'are i part of the operating license, were deleted and transferred to l owner controlled documents. In this way, the original )
requirements remain in force at a plant but can be changed i without going through the license amendment process. '
i
4 392nd ACRS Minutes 6 Mr. Schulten presented a listing of the lead plants that had agreed to convert to STSs. The first plant, Crystal River 3, which is a Babcock and Wilcox NSSS, is expected to complete the conversion in 1993 and all other lead plants, i.e.,
Westinghouse, General Electric and Combustion Engineering plants, are expected to be converted by the end e? 1994.
In response to a question about looking at risk-based technical specifications, Mr. Grimes indicated that he is aware of the presentations on this subject that have been made to the Committee and the Commission and that his staff will support whatever process NRR or the Commission decides.
Conclusions This was a briefing for information only. The Committee took >
no action on this matter at this meeting.
IV. Advanced Boilina Water Reactor Desian (Open)
Note: Dr. M. El-Zeftawy is the Designated Federal Official for this portion of the meeting.
Committee Members Discussion Mr. Michelson, Chairman of the Advanced Boiling Water Reactors !
Subcommittee, briefed the Committee on the status of the i Subcommittee's review of this matter. He noted that during recent Subcommittee meetings to discuss the staff's draft Final Safety Evaluation Report (FSER), the staff was not ready to discuss Chapter 7, Instrumentation and Control, Chapter 18, Human Factors Engineering, and Chapter 19, Severe. Accident Considerations and PRA. The Subcommittee is ready to complete its review at such time as the staff and GE work is reasonably complete and ready to support a meeting. In addition, the Subcommittee is ready to review the Fire Hazards Analysis, to l be provided in Appendix 9A, and the proposed Technical Specifications, to be provided in Chapter 16, at such time as the staff and GE are ready. He noted that there are over 300 open items in the draft FSER.
I Mr. Michelson said that it is the Subcommittee's view that the remaining FSER chapters and other items that are needed, as mentioned above, must be reasonably well completed and- !
provided to the Committee during the March 1993 ACRS meeting in order for the Committee to issue its final report in June 1993.
Conclusion This was only a briefing of the Committee by Mr. Michelson regarding the status of the ABWR review. He noted that he 7
l
't
+ -
392nd ACRS Minutes 7 would provide this same information to the Commission at an upcoming meeting with them.
V. River Bend Nuclear Plant Reliability Monitorina Procram (open)
Note: Mr. E. Igne is the Designated Federal Official for this portion of the meeting.
Introduction Mr. Carroll, Chairman of the Plant Operations Subcommittee, introduced this matter and called on the Gulf States Utilities representatives to discuss the River Bend Nuclear Plant Reliability Monitoring Program.
Gulf States Utilities Presentations Apolvina the System Reliability Proaram to Improve Reliability, Availability and Performance at River Bend Station Mr. Holbert, Gulf States Utilities, noted that the System Reliability Program at River Bend started in 1988 as a pilot program to optimize maintenance on the feedwater system.
Their Engineering Analysis Group has performed a PRA E.nalysis for reliability and availability, along with a cost study.
These analyses show quantitatively how changes in the feedwater system affect reliability and availability, which indicates that resources could be allocated in a cost effective manner to enhance maintenance effectiveness. Mr.
Holbert stated that management was pleased with the results and added more systems to the pilot program. Presently 24 systeme are included in the program.
The System Reliability Program provides plant specific data for the PRA analysis. A unique feature of the program is the implementing of a living program through a feedback monitoring program. The plant reliability output data is plotted and used to enhance system reliability and availability. Examples on the RCIC, control building chillers and turbine building chillers were presented to the Committee. Of particular interest was the higher reliability of the non-safety grade turbine building chillers as compared to the safety-related control building chillers. This was attributed to the turbine building chillers running more hours continuously as compared 1
l
392nd ACRS Minutes 8 to the less running time, e.g., more stop and go operation of the control building chillers.
Usina PRA Methods for Enhanced Reliability at River Bend Station - Mr. J. Burton, Gulf States Utilities Mr. Burton, presented the uses of PRA at the River Bend Station. He stated that one of their major uses of PRA is to improve system reliability by optimizing plant maintenance.
Critical ranking of important components in systems is ,
obtained for preventive maintenance and establishing risk significant events leading to core damage. He mentioned that their PRA analysis integrates severe accident issues and human factor actions. River Bend core damage frequency was reported to be 1.55E-5/yr. Of this value, the station blackout event contributes about 90 percent of the core damage frequency (CDF) and other transients about 10 percent. Mr. Burton stated that for River Bend, there is no single system, component or operator action that dominated the CDF. The preventative maintenance program was then described in detail.
In reply to a question by the Committee, Mr. Burton stated that valve reliability data, accounting for operability during severe design conditions such as a pipe break downstream of the valve, is not accounted for.
In conclusion, Mr. Burton, noted that NRC concurrence to risk-based regulation methods is needed on issues such as technical specification improvements and thermo-lag risk significance.
Conclusions This was a briefing for information only. No ACRS action was taken at this time.
VI. Protection Acainst Lichtnina and Electrical Transients for Nuclear Power Plants (Open)
Note: Mr. S. Duraiswamy was the Designated Federal Official for this portion of the meeting.
Introductions
Mr. C. Wylie, Chairman of the Control and Electrical Power Systems Subcommittee, introduced this topic to the Committee.
1 i
l 1
. f, .
392nd ACRS Minutes 9 NRC Staff Presentation Mr. Rourk, Office of Research, discussed a petition submitted by Richard Grill for rulemaking on electrical transients, PRM-50-56, requesting that the NRC staff provide regulations requiring licensees to protect their plants from the adverse effects of lightning and other electrical transients. Mr.
Rourk noted that the staff's conclusion, after an . analysis of the need for further regulations in this area, was that the.
petition should be denied.
Mr. Rourk suggest'ed that the petition, based on the existing requirements of General Design Criteria 2 and 4, was denied based on numerous things. These included the following:
e Staff's cursory look at lightning protection during pre-licensing reviews (most of which were not documented) e Additional qualification testing on digital system retro-fits e A study of the historical record of lightning induced failures / trips, which indicated that there is no significant core damage risk from lightning alone e Inclusion of lightning in IPEEEs for plants in which it has affected more than just loss of offsite power.
Independent of the petition, Mr. Rourk described the staff's plan to produce a regulatory guide on electromagnetic interference (EMI), and reconsideration of a regulatory guide on lightning protection.
Mr. Lindblad noted that historical lightning protection codes have included the concern for preventing fire and loss _of life, but that for a nuclear plant the issue is more with regard to equipment availability, with greater emphasis on adequate grounding schemes. He stated that although plant grounding schemes may not be closely regulated by the NRC, utilities do an adequate job because of the potential for adverse impact on plant operations if they do not. However, he offered that this was probably not a significant public.
safety risk.
Conclusions The Committee provided a report on this matter to Chairman !
Selin, as noted in Section XX below, i
]
392nd ACRS Minutes 10 !
VII. Election of ACRS Officers (Closed)
Results of the elections held for Committee officers for the 1993 Calendar year are as follows:
Chairman - Dr. Shewmon '
Vice Chairman - Dr. Wilkins i Member at Large - Mr. Carroll It was noted that the ACRS Bylaws require that another election be held within two months of the time that Dr. Shewmon's term expires -!
on May 31, 1993, to elect a new member at large.
VIII. Generic Safety Issue-120. Online Testability of Protection Systems (Open) -
Note: Mr. S. Duraiswamy was the Designated Federal Official for this portion of the meeting. ,
Introduction Mr. Wylie, Chairman of the Control and Electrical Power Systems subcommittee, introduced this matter to the committee. '
Staff Presentation >
Mr. T. Y. Chang, Office of Research, discussed the staff's closure package for Generic Safety Issue 120 (GSI-120). The requirements for online testability of protection systems and
- engineered safeguard features (ESFs) during operation are '
included in the General Design Criterion 21 and Regulatory Guide 1.22 (1972).
The staff has recommended closure of GSI-120, indicating that the staff is satisfied that licensed plants have test programs ;
that adequately test all ESP system components at an approved ;
frequency. This recommendation is based on an independent '
review made by INEL acting as the : staff's consultant that concluded that the several representative plants that they :
reviewed did have an appropriately low failure rate and that on-line testability was adequate.
The Committee was not satisfied with the information provided and asked the staff to provide a discussion on several matters at a future meeting. The staff was asked to respond to the following: -
- 1. Provide tore detail on the origins of GSI-120.
- 2. The EPRI Utility Requirements Document (URD) specifies that for Evolutionary Plants (Vol. 10, para. 3.6.2)
Regulatory Guide 1.22 is a requirement for testability of ,
392nd ACRS Minutes 11 protection systems. The latitude allowed by this guidance appears to have been at least partly responsible for GSI-120. Will the resolution to GSI-120 address the i continuation of this guidance, either by endorsement of-or exception to the EPRI URD requirement?
- 3. How does staggered testing of ESF relays increase the probability of detection of common-mode failure?
- 4. The title of GSI-120 is "On-line Testability of Protection Systems," but the focus of the resolution is i limited to Engineered Safeguards Features. How does the resolution address the more global concern in the title of GSI-120?
- 5. Provide examples (i.e., one-line electrical diagrams of
" slave-relays").
Conclusions This matter will be continued at the January 7-9, 1993 ACRS meeting.
IX. ACRS Subcommittee and Members Activities (Open/ Closed)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting.
Report of ACRS Planninc and Procedures Subcommittee Meetina on December 9, 1992 (Open/ Closed)
The minutes of the December 9, 1992 Planning and Procedures Subcommittee meeting were discussed. There was general agreement with the minutes of that meeting with the following comments: !
Impact of ACRS Workload on ACRS Budaet Staff Resources (Closed) l This session is reported in a special closed meeting j supplement, which is attached. -l Impact of ACRS Workload on ACRS Staff Resources (Closed)
This session is reported in a special. closed meeting supplement, which is attached.
Report on the NRC Senior Manacement Meetina on the Orcanizational Factors Research Procram (Open)
J. Carroll, Chairman, Human Factors Subcommittee, reported on the subject NRC Senior Management Meeting. Mr. Carroll
1 392nd ACRS Minutes 12 reminded the Committee that it has heard briefings on the status of the RES Organizational Factors (OF) Research Program in the past. The initial goal of the OF research was to.
identify factors and elements that impacted on the effectiveness of licensee management in the conduct of their operations. Dr. T. Murley was instrumental in initiating this work when he was the head of the NRC Region I Office.
On November 12, 1992 a Senior Management meeting was held.
Representatives of the NRC staff and the OF contractors were ,
present. The OF contractors detailed the elements of the OF '
Program and the status of the associated work products. ,
Emphasis is being given to incorporating these work products ,
into PRA analyses. Besides Mr. Carroll, Messrs. Lindblad, t Ward, and Leamon attended the November 12 meeting. Committee Members were urged to peruse the meeting reports from D. Ward and T. Leamon that were provided them in the Committee notebooks.
Mr. Carroll noted that the OF program is being terminated. He said that he believed that this work should be continued, and opined that " human factors" is of greater risk significance than is the risk contributor due to seismicity; yet much more money has been, and still is being, spent on seismic research.
Mr. Lindblad provided his perspectives on the OF issue. He agrees that: (1) this work is important, (2) if it's pursued, then NRC senior management must support it, and, (3) he did not see any evidence that NRC management will support this work.
Mr. Carroll recommended that the Committee be briefed on this issue during its January, 1993 Meeting. Mr. J. Kramer (RES) noted that due to problems with availability of contractor personnel, the briefing would have to be postponed to February. RES is preparing a SECY paper to inform the Commission of the termination of the OF program and subsequent plans to have NRR and AEOD make use of the work products developed to date.
Committee Action:
The Committee agreed to schedule a briefing on the Organizational Factors Research Program for the February 1993 ACRS Meeting.
X. Future ACRS Activities (Open)
Note: Dr. R. Savio was the Designated Federal Official for this portion of the meeting.
392nd ACRS Minutes 13 The Committee agreed to discuss the following during its 393rd meeting, January 7-9, 1993:
o Performance Indicator Report - The NRC staff will Brief the Committee on their proposed revisions to the NRC performance indicator report. Representatives of the nuclear industry will participate, as appropriate.
e Kev Policy Issues for Advanced Reactor Desians - The Committee will review the key policy issues applicable to MHTGR, PIUS, PRISM, and CANDU 3 advanced reactor designs. Representatives e
of the nuclear industry will participate, as appropriate.
Replacement of Analon Instrumentation with Dicital Instrumentation regarding The NRC staff will brief the Committee the staff's proposed generic letter on the replacement of analog instrumentation with digital instrumentation in operating plants. Representatives of the nuclear industry will participate, as appropriate.
- Annual Report to the U. S. Conaress on the NRC Safety Research Procram and Budaet - The members will discuss the Committee's annual report to Congress on the NRC safety research program and budget.
- Atomic Safety and Licensing Board Panel Activities -
A representative of the ASLBP will discuss the current and anticipated activities of the ASLBP.
e Reactor Operatina Experience - The NRC staff will brief the Committee regarding reactor operating events and occurrences, including an incident at the Barseback Nuclear Plant in Sweden which involved dislodging of thermal insulation material inside containment and resulting in partial clogging of two of five ECCS strainers. Representatives of the nuclear industry will participate, as appropriate.
bCRS Subcommittee Activities - The Committee will heer and discuss reports of designated subcommittees regarding the status of assigned activities, including conduct of ACRS business by the Planning and Procedures Subcommittee. '
Representatives of the NRC staff will participate, as appropriate.
- Future ACRS Activities -
The Committee will discuss topics proposed for consideration.
Reconciliation of ACRS Comments and Recommendations -
The Committee will discuss replies from the NRC staff regarding staff reaction to recent recommendations of the Committee.
- Generic Issue 120. Online Testability of Protection Systems -
The Committee will complete its review and will report on the proposed resolution of this generic issue. Representatives of the NRC staff and the nuclear industry will participate, as appropriate, e
NRC Procedures for Incident Investiaation - The Committee will discuss an NRC staff proposal for changing the existing procedures for the NRC investigation of incidents at licensed facilities. Representatives of the NRC staff will participate, as appropriate.
, s. ,
392nd ACRS Minutes 14
- Miscellaneous -
The Committee will discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of topics that were not completed during previous meetings as time and availability of information permit.
XI. Appointment of New Members (Closed)-
This portion of the meeting is reported in a special closed meeting supplement, which is attached.
XII. MeetJno with the Director. Office of Nuclear Reaulatory Research (Open) !
Note: Mr. P. Boehnert was the Designated Federal Official for this portion of the meeting.
Mr. Eric Beckjord, Director of the Office of Nuclear Regulatory Research (RES), briefed the Committee on the status 1 of their research efforts. He noted that the completion of l the research programs on aging and severe accidents is in sight. Programs ' to continue include: licensing support, seismic hazards, controls (digital I&C), and human factors.
Programs to receive new emphasis include research in passive advanced reactors areas and cooperation with eastern Europe and the Commonwealth of Independent States.
Research Funding for FY 1993 RES funding for FY-93 was decreased by $8M to help accommodate a $10M Agency budget reduction mandated by Congress. The long-term funding outlook is for research funding to hold level, with no big budget increases expected.
Fesearch Accomplishments l Mr. Beckjord discussed the accomplishments of their Programs on Reactor Aging and License Renewal, Severo Accidents, Reactor Licensing Support and Regulatory Standards, Seismic Hazards, Controls Operations and Human Factors, and Passive l Advanced Reactors. During discussions associated with these ;
programs, Dr. Shewmon suv asted that the research programs related to aging that have been conducted to date are a disservice to the nuclear industry, i.e., they were taken to extremes and the information obtained is too conservative to be of practical use. He suggested that the NRC not allow use of cast iron for fabrication of spent fuel storage casks.
With regard to RES's plans to reconcile the differences between the seismic hazard curves developed by LLNL and EPRI, ;
Dr. Lewis expressed concern that forcing agreement here may .
result in destruction of valuable information, i.e., !
l l
. I 392nd ACRS Minutes 15 suppression of diverse viewpoints. Mr. Beckjord solicited the '
Committee's advice on this matter. Dr. Lewis said he'd raise this issue in another context. j ROSA Facility Tests Concerning the test program underway at the Japanese ROSA facility in support of the AP600 design certification effort, Dr. Catton requested a copy of the relevant document (s) pertaining to the facility's configuration and associated '
instrumentation package.
Research Priorities ,
Mr. Beckjord noted that the research programs that have priority are matters related to primary system integrity (including the reactor vessel and steam generator tubes),
advanced LWR issues, and severa accident issues. Dr. Catton noted that following the steam generator tube rupture event at the Japanese Mihama nuclear power plant, Japan has embarked on an extensive program of research into the phenomena surrounding flow induced vibration of steam generator tubes, ,
and asked why there is no interest in this issue by RES. It >
was noted by RES representatives that a similar event occurredand was investigated at North Anna about six years ago. The North Anna event occurred as a result of synergistic effects caused by both a missing anti-vibration bar in the ;
upper tube bundle and the pinning of the 2 ailed tube at the support plate, due in turn to the " denting" phenomenon.
Oraanizational Factors Research Procram l The Organizational Factors (OF) Research Program is being '
terminated, largely due to a lack of a readily identified user need for this work. Current plans are to interact with NRR ;
and AEOD in an attempt to incorporate the OF Work products into human reliability analysis for use with PRAs. Comments !
by Messrs. Lindblad and carroll were to the effect that the OF program is important and should not be terminated. Mr.
Lindblad also noted that this work would have benefit for international reactor safety as well.
International Procrams -
RES has a number of international cooperative research programs underway or planned in the areas of severe accidents and aging. Of particular note, is that the Russians have i planned a large-scale core melt test (RASPLAV) to study melt attack on the lower vessel-head. Joint programs are planned ,
in the areas of aging degradation mechanisms, piping integrity, materials research, and cable aging. Other !
international research activities include: a multi-national l l
l l
4 392nd ACRS Minutes 16 thermal hydraulic code assessment program, research at '
Norway's Halden Project on digital I&C, and studies on risk and human factors in cooperation with the UK, Spain, and Switzerland.
Budget .
Discussion on the details of the RES budget was' deferred due to lack of time. Mr. Beckjord noted for.the record that he disavows the remarks of the Office of the Comptroller to the effect that the 10% cut taken in the FY-93 RES budget had no impact on the research program.
Conclusion This was an information briefing only. No ACRS action was taken on this matter at this meeting.
XIII. Preparation for Meetina with NRC Commissioners (Open)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting.
Members discussed their individual thoughts and the conclusions of the Committee with regard to the following matters in preparation for the meeting with the Commission:
The status of ACRS review of advanced reactor designs, including design acceptance criteria (DAC) and inspections, '
tests, analyses, and acceptance criteria (ITAAC) e Digital control and protection systems t e The transition to risk-based regulation e Implementation of the license renewal rule XIV. Meeting with NRC Commist;ioners (Open)
The Committee met with the Commission and discussed the matters listed in Item 12 above.
Attached to a Staff Requirements Memorandum from S. Chilk to Paul Shewmon, dated December 16, 1992, Commissioner Curtiss requested that the ACRS consider how the maintenance rule might be used as a means to address the activities required by licensees in the license renewal rule, such that the maintenance program would supplement the need for much of the component-by-component analysis expected in the license renewal rule.
392nd ACRS Minutes 17 XV. Uparade of ACRS Conference Room (Open)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting.
Mr. Mike MacWilliams, ACRS staff, discussed the current proposal for the layout,' audio / visual, and computer support facilities in the ACRS/ACNW spaces and conference roorc at the new Two White -
Flint North facility that the Committee expects to occupy in late 1993/early 1994. A detailed floor plan and specifications of "
equipment were passed out to the members.
Mr. Stella, ACRS Fellow, provided some detail of the computer equipment that might be available for the Committee members use at the new facility and passed out a questionnaire requesting feedback from the members.
XVI. Reconciliation of ACRS Comments and Recommendations (Open)
Note: Mr. S. Duraiswamy was the Designated Federal Official for.
this portion of the meeting.
i An EDO letter dated December 2, 1992 that responded to the Committee's report of October 16, 1992 on SECY-92-287, " Form and Content for a Design Certification Rule" was scheduled for Committee discussion at this meeting. Due to the shortage of time ,
available, this matter was not discussed at this meeting but was rescheduled to be discussed at the January 1993 ACRS meeting.
XVII. Miscellaneous (Open)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting.
Computers in Nuclear Power Plant ODerations Dr. Lewis discussed the need he perceives for a short workshop on the relationship between digital systems reliability and nuclear safety by the National Academies of Sciences and -
Engineering. The Committee reviewed a draft proposed letter to the Commission but did not endorse it. ,
Drs. Lewis, Kress and Wilkins did send a personal letter, not approved by the Committee, on this matter to Chairman Selin, dated December 11, 1992.
XVIII. Prenaration of Other ACRS Reports and Memoranda (Open)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting, i
/ '
'392nd ACRS Minutes 18 In addition to those matters discussed with representatives of the staff and industry during this meeting, the merbers discussed and s completed the following reports and memoranda:
, e Safety System Status Monitorina i
The Committee directed Raymond F. Fraley to send a memorandum ;
to Warren Minners, Director of the Division of Safety Issue Resolution in the Office of Nuclear Regulatory Research, as '
noted above.
e Traininc and Oualification of Nuclear Power Plant Personnel The Committee directed Raymond F. Fraley to send a memorandum to James M. Taylor, Executive Director for Operations, as ,
noted above. i e Spent Fuel Storace Casks The Committee directed Raymond F. Fraley to send a memorandum to Eric S. Beckjord, Director for the Office of Nuclear Regulatory Research, as noted above.
e Fitness-for-Duty Procram The Committee directed Raymond F. Fraley to send a memorandum Taylor, Executive Director for Operations, as 4
to James M. ;
noted in Section XX below. i XIX. Summary / List of Follow-uo Matters e
A list of journals and other publications should be developed for future announcement of ACRS member vacancies so that experts in the areas of digital instrumentation and controls, as well as other specialty type experts that might be considered for ACRS membership, are aware of the vacancies.
(Ms. Lee has the follow-up on this matter.)
e The members were asked to fill-out a questionnaire concerning the future conference room computer equipment to be considered for the new White Flint building. It was requested that the questionnaire be returned by January 4, 1993. (Mr. Stella has i the follow-up on this matter.)
-l e Dr. Catton requested a copy of the relevant document (s) pertaining to the configuration and associated instrumentation package being used for tests at the ROSA facility. (Mr.
Boehnert has the follow-up on this matter.)
Note: RES has contacted this Office and will provide a report in response to this request.
i 392nd ACRS Minutes 19 e Mr. Beckjord offered to brief the Committee in the near future '
on details on aging matters affecting license renewal of plants. (Mr. Boehnert has the follow-up on this matter.)
e Dr. Catton noted that a problem with electrical cable insulation may be that gasses emitted when they are burned are toxic. Mr. Beckjord offered to look into this issue and determine what action RES has already taken on this matter.
(Mr. Boehnert has the follow-up on this matter.)
XX. Executive Session (Open)
Note: Mr. R. Fraley was the Designated Federal Official for this portion of the meeting.
During its 392nd meeting, December 9-11, 1992, the Advisory Committee on Reactor Safeguards discussed several matters and completed the Reports, Letter, and Memoranda as noted.
Reports e NRC Staff Response to the Petition Submitted by Richard Grill for Rulemakina on Electrical Transients PRM-50-56 (Report to Chairman Selin, dated December 17, 1992) e Resolution of Generic Safety Issue B-56, " Diesel Generator Reliability" (Report to Chairman Selin, dated December 18, 1992)
Letter e Letter to Alex Marion, Nuclear Management and Resources Council, from Raymond F. Fraley, Executive Director of the ACRS, dated December 18, 1992. Requesting information regarding diesel generator performance data.
Memoranda e Task Action Plan for Generic Issue I.D.3, " Safety Syste_nj Status Monitorina" (Memorandum to Warren Minners, Director of the Division of Safety Issue Resolution in the Office of Nuclear Regulatory Research, from Raymond F. Fraley, Executive Director of the ACRS, dated December 18, 1992) e Proposed Amendments to 10 CFR Parts 50 and 52 Related to the Trainina and Oualification of Nuclear Power Plant Personnel (Memorandum for James M. Taylor, Executive Director for Operations, from Raymond F. Fraley, Executive Director of the ACRS, dated December 18, 1992) e Proposed Final Amendmant to 10 CFR Part 72 to Add Two Spent Fuel Storace Casks to the List in 10 CFR 72.214 (Memorandum
y w ,
- 392nd ACRS Minutes 20 for Eric S. Beckjord, Director for the Office'of Nuclear Regulatory Research, from Raymond F. Fraley, Executive Director of the ACRS, dated December 18, 1992) e Proposed Modifications to Fitness-For-Duty Proctram .
Reauirements (Memorandum for James M. Taylor, Executive
Director for Operations, from Raymond F. Fraley, Executive Director of the ACRS, dated December 22, 1992) e Appointment of ACRS Members (Memorandum for Chairman Selin from Raymond F. Fraley, dated December 16, 1992)
Meeting was adjourned at 5:30 pm on December 11, 1992 i
1 e
-APPENDICES MINUTES OF THE 392ND ACRS MEETING DECEMBER 9-11, 1992 i
I. Attendees I
II. Future Agenda III. Future Subcommittee Activities j IV. List of Documents Provided to the Committee f r
t t
)
i E
t L
1
.I i
l P
t i
, ."~
APPENDIX 1 MINUTES OF THE-392ND ACRS MEEllNG DECEMBER 9-11 December 9. 1992 -
Public Attendees NRC Attendees Theresa Meisenheimer, Bechtel, SERCH Faust Rosa, NRR-Judith Sikorski, Bechtel,-SERCH Lee Abramson, RES Nozer Singpurwalla, GWU, Self G. R. Mazetis, RES.
Alex Marion, NUMARC Paul Norian, RES Robert Draper, Winston & Shawn A. W. Serkiz, RES Bob Helfrich, Winston & Shawn J.'J. Burns, RES Roger Huston, TVA 0m P. Chopra, NRR Byung-Sik Lee, HNUS/KEPC0 . Dave Trimble, OCM .
Mike Chesk, HNUS Ted Cintula, AEOD John Massidda, Devonrue Helen Pastis, NRR Les Toth, Gasser Associates Dale Rasmuson, AE00 Jim Eaton, NUMARC Jack Rosenthal, AEOD Mat Taylor, OEDO ;
T. R. Tjader, NRR-C. L. Hoxie, NRR T. Foley, NRR C. Petroni, NRR C. I. Grimes, NRR C. S. Schulten, NRR B. Grimes H. Li, NRR C. Poslusny, NRR i D. Crutchfield,NRR -
I l
I
W APPENDlX 1 MINU1ES OF THE 392ND ACR$ MEETING. '
DECEMBER 9-11 December 10, 1992 Public Atte.n_dces NRC Attendees J. E. Booker, Gulf States Utilities P. O'Reilly, AEOD J. L. Burton, Gulf States Utilities Pat Baranowsky, AE00 t D. A. Holbert, Jr., Gulf States Utilities Tom Foley, NRR Bob Christie, Reliability and Performance Associates Victor Benaroya, AE00 Earl Hill, NUS Faust Rosa, NRR Roger Huston, TVA Chris Rourk, RES Charles Hallon, Newman & Holtzinger. Eric Lee, NRR A. J. Kapsalopoulois, NJ Dept. Environ. Protect. & Energy Helen Pastis, NRR K. M. Giraney. SERCH Licensing /Bechtel T. Y. Chang, RES John M. Fehringer, EG&G Washington Technical Office N. P. Kadambi, RES Robert C. Evans, NUMARC Mat Taylor, OE00 Leon Reiter, NWIRB T. R. Tjader, NRR J. J. Kramer, RES 9
)
-)
+ - - - ~ - - - - - -
1 I
I i
'APPENDlX 1 !
MINUTES OF-THE.392ND ACRS MEETING .i DECEMBER 9-11 December 11. 1992 Public Attendees NRC Attendees' ;,
A. J. Kapsalopoulois, NJ Dept. Environ. Protect. &~ Energy J. Heltemes, RES Carl Snyder, NUS George.Sege, RES Robert C. Evans, NUMARC Brian Sheron, RES R. T. Curtis, AECLT Joel Kramer, RES Elise Heumann,- OC -
H. Pastis, NRR Shah Malik, RES Joe Muscara, RES 1 Mat Taylor, OED0 t
}
l 1
l APPENDIX II MINUTES OF THE 392ND ACRS MEETING l DECEMBER 9-11, 1992 FUTURE AGENDA s
The Committee agreed to discuss the following during its 393rd meeting, January 7-9, 1993:
- Performance Indicator Report - The NRC staff will Brief the -
Committee on their proposed revisions to the NRC performance indicator report. Representatives of the nuclear industry will participate, as appropriate.
e Kev Policy Issues for Advanced Reactor Desians - The Committee will review the key policy issues applicable to MHTGR, PIUS, PRISM, and CANDU 3 advanced reactor designs. Representatives of the nuclear industry will participate, as appropriate. -
e Replacement of Analoa Instrumentation with Diaital InstruAentation - The NRC staff will brief the Committee regarding the staff's proposed generic letter on the ,
replacement of analog instrumentation with digital instrumentation in operating plants. Representatives of the 3 nuclear industry will participate, as appropriate.
- Annual Report to the U. S. Conaress on the NRC Safety Research Procram and Budaet - The members will discuss the Committee's annual report to Congress on the NRC safety research program and budget.
- Atomic Safety and Licensino Board Panel Activities -
A representative of the ASLBP will discuss the _ current and anticipated activities of the ASLBP.
- Reactor Operatina Experience - The NRC staff will brief the Committee regarding reactor operating events and occurrences, including an incident at the Barseback Nuclear Plant in Sweden which involved dislodging of thermal insulation material :
I inside containment and resulting in partial clogging of two of five ECCS strainers. Representatives of the nuclear industry will participate, as appropriate.
- ACRS Subcommittee Activities - The Committee will hear and-discuss reports of designated subcommittees regarding the status of assigned activities, including conduct of ACRS- '
business by the Planning and Procedures Subcommittee.
Representatives of the NRC staff will participate, as appropriate.
- Future ACRS Activities - The Committee will discuss topics proposed for consideration.
e Reconciliation of ACRS Comments and Recommendations - The ,
Committee will discuss replies from the NRC staff regarding.
staff reaction to recent recommendations of the Committee.
l
e Generic Issue 120, Online Testability of Protection Systems -
The Committee will complete its review and will report on the proposed resolution of this generic issue. Representatives of the NRC staff and the nuclear industry will participate, as appropriate.
e NRC Procedures for Incident Investiaation - The Committee will discuss an NRC staff _ proposal for changing the existing procedures for the NRC investigation of incidents at licensed facilities. Representatives of the NRC staff will participate, as appropriate.
e Miscellaneous -
The Committee will discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of topics that were not completed during previous meetings as time and availability of information permit.
APPENDIX II r
a P
b
1 APPENDIX III MINUTES OF THE 392ND ACRS MEETING ,
DECEMBER 9-11, 1992 FUTURE SUBCOMMITTEE ACTIVITIES 50th ACNW Meetina, January 27-28, 1993, Bethesda, MD Joint Meetina of the ACNW Workina Group /ACRS Subcommittee on Occupational and Environmental Protection Systems, February 5, 1993, 7920 Norfolk Avenue, Bethesda, MD (Gnugnoli/Igne), 8:30 a.m., Room P-110. The Working Group / Subcommittee will review the following proposed final regulatory guides implementing 10 CFR Part 20: (1) DG-8006, " Control.of Access to High and Very High Radiation Areas in Nuclear Power Plants," (2) DG-8009, "Interpre-tation of Bioassay Measurements," and (3) DG-8005, " Assessing External Radiation Doses from Airborne Radioactive Materials."
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of February 4:
Wilkins HOLIDAY INN Shapiro NONE Moeller HOLIDAY INN Kathren NONE Foster NONE Underhill NONE Comouters in Nuclear Power Plant Onerations, February 9, 1993, 7920 Norfolk Avenue, Bethesda, MD (Coe), 8:30 a.m., Room P-110.
The Subcommittee will discuss current and proposed methods used to evaluate software for safety-critical applications, including the use of risk-based criteria. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of February 8:
Lewis RESIDENCE INN Wilkins HOLIDAY INN Carroll HOLIDAY INN Wylie HYATT Catton HYATT
2 AdvaDced Pressurized Water Reactors, February 10, 1993, 7920 Norfolk Avenue, Bethesda. MD (Igne), 8:30 a.m., Room P-110._ The Subcommittee will begin its review of the NRC staff's Draft ,
Safety Evaluation Report (NUREG-1462) for certification of the ABB CE System 80+ Design. Attendance by the following is antici-pated, and reservations have been made at the hotels as indicated for the night of February 9:
Carroll HOLIDAY INN Michelson HYATT Catton HYATT Seale Davis NONE Shewmon NONE Kress HYATT Wilkins Lewis Wylie HYATT Lindblad Plannina and Procedures., February 10, 1993, 7920 Norfolk Avenue, ,
Bethesda, MD (Larkins), 3:00 p.m. - 5:30 p.m., Room P-422. The Subcommittee will discuss proposed ACRS activities and related matters. Qualifications of candidates nominated for appointment to the ACRS will also be discussed. Portions of this meeting will be closed to discuss information the release of which'would represent a clearly unwarranted invasion of personal privacy.
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of February 9:
Shewmon NONE Wilkins HOLIDAY INN Carroll HOLIDAY INN 1
394th ACRS Meetina, February 11-13, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110. Agenda to be announced.
51st ACNW Meeting, February 24-25, 1993, Bethesda, MD Joint Materials and Metallurov/ Structural Encineerina, March 10, 1993, 7920 Norfolk Avenue, Bethesda, MD (Igne), 8:30 a.m., Room P-110. The Subcommittees will discuss: (1) the status of the NRC staff's concerns regarding steam generator tube degradation, and (2) the industry proposal on piping design improvements to reflect current technical knowledge for ALWR plants. Lodging will be announced later. Attendance by the following is antici-pated:
Shewmon Wylie Kress Davis Carroll Catton Lewis Bush (tent)
Lindblad Siess Michelson Thompson
4 .
i
'l 3
395th ACRS Meeting, March 11-13, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110. Agenda to be announced. ,
Thermal Hydraulic Phenomena, March 4, 1993 (March 5, as needed)
Idaho Falls, ID, (Boehnert). 'The Subcommittee will review the status of the PWR version of the RELAPS/ MOD 3 code with emphasis on analytical programs in support of the AP600 design certifica-tion effort. Attendance by the following is anticipated:
Catton Schrock Davis Ward >
Kress Wulff Wilkins Zuber Dhir Probabilistic Risk Assessment (tentative) Date to be determined (February / March 1993), Bethesda, MD (Houston). The Subcommittee will discuss a proposed regulatory guide on the use of PRA in design certification and other applications of PRA in the regula-tory process. Attendance by the following is anticipated:
Lewis Wilkins Davis Consultants - TBD Kress Michelson Safety Philosophy. Technoloav and Criteria (tentative), Date to be determined (February / March 1993), Bethesda, MD (Houston). The Subcommittee will discuss a proposed plan for comparing safety goals with regulations. Attendance by the following is antici-pated:
Kress Wylie Davis Kerr Lewis Ward Michelson I
1
1 4
Joint Severe Accidents /Probabilistic Risk Assessment, (tentative)
Date to be determined (February / March 1993), Bethesda, MD-(Hous-ton). The Subcommittees will discuss Chapter 19 of ,the ABWR FSAR and its evaluation in regard to severe accident and PRA issues.
Attendance by the following is anticipated:
Kress Shewmon Lewis Wilkins Catton Kerr-Davis Lee Lindblad Other Consultants - TBD Michelson .
Reliability and Ouality, Date to be determined (February / March 1993), Bethesda, MD (Igne). The Subcommittee will discuss the quality management standard used by the European Community (ISO 9000) and its impact on the domestic nuclear power plant indus-try. Attendance by the following is anticipated.
Lindblad Michelson Carroll Shewmon Davis Wylie Kress Reaional Procrams (Week of March 22, 1993 one-day meeting),
Region II Offices, Atlanta, Georaia (Boehnert), 8:30 a.m. The Subcommittee will review the activities of the NRC Region Ii Office. Lodging will be announced later. Attendance by the following is anticipated:
Shemon Michelson Carroll Wylie T
Decav Heat Removal Systems, Date to be determined (March / April 1993), Bethesda, MD (Boehnert). The Subcommittee will continue its review of the NRC staff's proposed final resolution of Generic Safety Issue 23, " Reactor Coolant Pump Seal Failures." l Attendance by the following is anticipated: '
Catton Michelson ;
Davis Wylie i Lindblad Ward - l l
l l
j
5 Thermal Hydraulic Phenomena, Date to be determined (2-day meet-ing) (April 1993), San Jose, c_A (Boehnort). The Subcommittee will continue its review of both the GE analytical program (TRACG code) and the experimental programs supporting the certification effort for the Simplified Boiling Water Reactor design. Atten-dance by the following is anticipated:
Catton Kerr Davis Ward Kress Wulff Wilkins Zuber Dhir Joint Severe Accidents / Thermal Hydraulic Phenomena, Date to be determined (April /May 1993), Bethesda, MD (Houston). The Subcom-mittees will begin the discussion of the technical positions on severe accident issues for future plant designs. The topics of fuel-coolant interactions and hydrogen will be discussed.
Attendance by the following is anticipated:
Kress Shewmon Catton Ward Davis Kerr Lindblad Lee Michelson . Dhir Therrnal Hydraulic Phenomena, Date to be determined (2-day meet-ing), (May 1993), Orecon State University, Corvallis, OR (Boehnert). The Subcommittee will continue its review of the Westinghouse and NRC integral systems and separate effects test programs supporting the AP600 design certification effort.
Attendance by the following is anticipated:
Catton Kerr Davis Schrock Kress Ward Wilkins Wulff Dhir Zuber
,, - . . . - . - - . , - =-
i
'l 6
I Therinal Hydraulic PheELomena , Date to be determined, pethesda, MD (Boehnert). The Subcommittee will continue its review of the NRC staff program to address the issue of. interfacing systems LOCAs.
Attendance by the following is anticipated: ,
Catton Dhir Davis Kerr -
Kress Schrock Wilkins Ward
'Wulff Zuber Joint Thermal Hydraulic Phenomena / Core Performance, Date to be determined, Bethesda, MD (Boehnert). The Subconmittees will continue their review of the issues pertaining to BWR core power stability. Attendance by the following is anticipated:
Catton Dhir Wilkins Kerr Davis Lee Kress Lipinski Shewmon Zuber Joint Severe Accidents / Thermal Hydraulic Phenomena, Date to be determined (Fall 1993), Bethesda, MD (Houston). The Subcommit-tees will continue the discussion of the technical positions on severe accident issues for future plant designs. The topics of basemat penetration and direct containment heating will be discussed at this meeting. Attendance by the following is anticipated:
Kress Shewmon Catton Ward Davis Kerr Lindblad Lee Michelson Dhir ACNW Workina Group on Synercistic Data Needs for Re- l solvina Volcanic and Tectonic Concerns at Yucca Moun-tain (Date to be determined, late 1992 or early 1993),
Hethesda. MD (Deering) l l
L
. < o ,
t APPENDIX IV MINUTES OF THE 392ND ACRS MEETING DECEMBER 10-12. 1992 LIST OF DOCUMENTS RECEIVED BY THE COMMITTEE INote: Some of the materials listed may have been provided for ACRS Internal Committee Use Only or may contain proprietary Information1 ACRS MEETING NOTEBOOK AGENDA ITEM NO.
2 Station Blackout Rule r
. Agenda
. Project Status Report >
Letter for Chairman Selin from David Ward, dated May 19, 1992, re:
Reliability of Emergency AC Power at Nuclear Power Plants Letter for Chairman Selin from David Ward, dated December 20, 1991, ;
re: Resolution of Generic Safety Issue B-56, " Diesel Generator Reliability" Letter for Kenneth Carr from Carlyle Michelson, dated August 14, 1990, re: Proposed Resolution of Generic Safety Issue B-56, " Diesel Generator Reliability" Memorandum for Raymond Fraley from Warren Minners, dated November 6, 1992, re: Resolution of GSI B-56 " Emergency Diesel Generator Reliability" [With Enclosures Draft Commission Paper, Enclosure 1A, IB, 3,'4, 5A, and 5B]
3 Technical Soecification Imorovement Proaram
. Tentative Agenda Status Report Memorandum for James Taylor from Samuel Chilk, dated January 30, 1992, re: Staff Requirements - Briefing on Status of Technical Specifications Improvement Programs Memorandum for Chairman & Commissioners from James Taylor, dated November 6, 1992, re: Technical Specification Improvement Program Federal Register Notice dated November 25, 1992, 4 Advanced Boilina Water Reactor Desian
. Tentative Agenda
. Project Status Report Attachments Attachment A Letter for James Taylor from David Ward, dated April 13, 1992, re:
Review of the Draft Safety Evaluation Reports n the GE Advanced Boiling Water Reactor Design Attachment B Note for E. Igne from C. Michelson, dated August 28,1992, re: Items to include in Future SSAR Revision Attachment C Items from October 21, 1992 Subcommittee Meeting 5 River Bend Nuclear Plant Reliability Monitorina Proaram
. Tentative Agenda
. Project Status Report Attachments Report on PRA and the Maintenance Rule, by J. L. Burton and L. K.
Bedell dated November 24, 1992
s s O 392nd ACRS Meeting Minutes,-Appendix IV 2 Memorandum for J. Carroll and C. Wylie, from S. Mays dated July 7, 1992, re: River Bend Reliability Program (with attachments Prepared for Internal Committee Use Only]
6 Protection Aaainst Lightina and Electrical Transients for Nuclear Power Plants
. Agenda
. Project Status Report Memorandum for Raymond Fraley from Warren Minners, dated November 5, 1992, re: Staff Response to the Petition for Rulemaking on Electrical Transients Submitted by Richard Grill, PRM-50-56 [ Draft Copy Attached for Internal Use Only]
Memorandum for ACRS Members from Steve Mays, dated August 2,1992, re: Lighting Protection for Nuclear Power Plants, by ACRS Intern M.
Lewis Excerpt from Generic Letter 88-20 Supplement 4, Individual Plant Examination for External Events Excerpt from the staff's Safety Evaluation Report for Zion amendments 138 and 127 (" Eagle-21" digital I&C system retro-fit) dated June 9, 1992 8 Generic Issue-120. Online Testability of Protection Systems
- Agenda Project Status Report Memorandum for Raymond Fraley from Warren Minners, dated November 5, 1992, re: Recommended Resolution of GSI-120, "Online Testability of Protection System" [with enclosures]
9.2 Report on the NRC Senior Manaaement Meetino on the Oraanizational Factors Research Proaram Project Status Report i Memorandum for J. Carroll from P. Boehnert, dated December 3,1992, !
re: NRC Senior Management Meeting: Products and Applications Resulting from Organizational Factors Research - Meeting Summary and -
Consultants' Reports [ Prepared for Internal Committee Use]
Letter for Paul Boehnert from T. Leamon, dated December 2,1992, re:
Organizational Factors Research [ Internal Use Only)
Letter for J. Carroll from Dave Ward, dated November 16, 1992, re:
Comments on 11/12/92 Senior Management Meeting " Products and Applications Resulting from Organizational Factors Research"
[ Internal Use Only)
Figures from Handouts provided at November 12, 1992, NRC Senior Management Meeting 12 Meetina with the Director. Office of Nuclear Raoulatory Research Project Status Report Memorandum for Eric Beckjord from Raymond Fraley, dated November 25, 1992, re: Meeting with ACRS Budget for Office of Nuclear Regulatory Research, FY 1992-96
[0fficial Use Only]
Memorandum for Chairman Selin from James Taylor, dated October 29, 1992, re: FY 1993 Appropriation Reduction Excerpts from Minutes of Planning and Procedures Subcommittee Meetings: ACRS Review of NRC RES Programs
..+s 392nd ACRS Meeting Minutes, Appendix IV 3 13 Preparation for Meetina with NRC Commissioners Memorandum for Samuel Chilk from Raymond Fraley, dated December 3, 1992, re: ACRS Meeting with the NRC Commissioners on December 11, 1992 - Background Information ACRS MEETING HANDOUTS AGENDA DOCUMENTS ,
ITEM NO.
7 Election of Officers
- 2. Memorandum for ACRS Members from Richard Savio, dated December 10, 1992, re: Future ACRS Activities - 393RD ACRS Meeting January 7-9, '
1993
- 3. Proposed Agenda Items for the ACRS/ACNW
- 4. Memorandum for Raymond Farley from Warren Minners, dated October 26, 1992, re: Task Action Plan for Generic Issue I.D.3 " Safety System Status Monitoring" [with enclosures]
- 5. Letter for Chairman Selin from Joe Colvin, dated October 20, 1992, re: Overall Industry views on the SALP Program 13 Meetina with the Commissioners
- 6. Memorandum for Samuel Chilk from Raymond Fraley, dated December 3, 1992, re: ACRS Meeting with the NRC Commissioners on December 11, 1992 - Background Information ,
- 7. Item 1: Status of ACRS Review of Advanced Reactor Designs [pp.2-52]
- 8. Item 2: Digital Control and Protection System [pp.53-64]
- 9. Item 3: Implementation of the Plant Life Extension Rule
- 10. Item 4: Risk-Based Regulation 14.1 Implementation of Plant Life Extension Rule
- 11. Memorandum for P. Shewmon from E. Igne, dated December 9, 1992, re:
Highlights of the Commission Briefing on License Renewal Issues, December 7-8, 1992 [with attachments]
18 Beconciliation of ACRS Comments and Recommendations
- 12. Letter for David Ward from James Taylor, dated December 2,1992, response to ACRS Letter dated October 16,1992, re: SECY-92-287,
" Form and Content for a Design Certification Rule" LIST OF HAND 0UTS OTHER THAN ACRS
- 13. Presentation to the ACRS, The Two White Flint North Facility Layout of Spaces
December 10, 1992
- 16. Memorandum for Chairman & Commissioners from James Taylor, dated December 2, 1992 re: Advance Information Copy of Forthcoming Commission Paper - Issues pertaining to the Advanced Reactor (PRISM, -
MHIGR and PIUS)
l 392nd ACRS Meeting Minutes, Appendix IV 4 .-
- 17. RES Staff Presentation by Chris Rourk,. dated December 10, 1992 re. ,
Petition for Rulemaking PRM 50-56 I
- 18. Using PRA Methods for Enhanced Reliability at River Bend Station, by J. L. Burton
- 19. Applying the System Reliability Program to Improve Reliability-Availability and Performance at River Bend Station, by 0. A. Holbert
- 20. NRR Staff Presentation to the ACRS, re: Technical Specifications Improvement Program dated December 9, 1992 by C. S. Schulten
- 21. Letter for Eric Beckjord from David Morrison, ' dated November 16, .
1992, re: Meeting held on April 29, 1992 regarding Research Program for Advanced Digital Instrumentation and Control Systems
- 22. Excerpt from NRC News, Summary of All Employees Meeting with Chairman Selin on November 12, 1992 re: Headquarters Staff Turns Out '
in Record, Employees in the Five Regions Are Able to Participate Via Telephone Hookup ,
- 23. NRC Press Release dated November 16, 1992, re: NRC Invites Public to Submit Nominations for ACRS
- 24. Reports / Letters Scheduled for Consideration During the December 9-12, 1992 ACRS Meeting
- 25. 9 50.63 Proposed Rule Change Presentation to ACRS December 9,1992, by Warren Minners
- 26. Memorandum for James Taylor from James Curtiss, dated November 19, 1992, re: License Renewal.
4 i
I I
l