ML19322D681
| ML19322D681 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/15/1979 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| 791025-01, 791025-1, ACRS-1664A, NUDOCS 8002210137 | |
| Download: ML19322D681 (17) | |
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N I1j 3 ISSUE DATE: 10/15/79 48!60Bi UL d J mhu/n MINUTES OF THE MI-2 ACCIDENT IMPLICATICUS (SALEM) SU3CCMMITTEE MEETING JULY 27, 1979 WASHINGTON, DC A meeting of the Ad Hoc Subcommittee on the tree Mile Island 2 Accident Implications was held in Room 1046, 1717 H Street, Washington, DC on July 27, 1979. We purpose of the meeting was to develop information that will assist the full ACRS in reaching a decision on what requirements from the W I accident will be applied to plants in the near-term license stage, specifically a Westinghouse-type reactor, Salem 2.
We meeting was noticed in the Federal Register dated July 12 and 20, 1979, which are included as Attachment A.
"ihe schedule of the meeting and the attendee list are in-cluded in Attachment B and C, respectively. Handouts at the meeting are included as Attachment D.
No request to make a statement at the meeting from the public was received. We meeting was held in open session.
EXECUTIVE SESSION Dr. Siess opened the meeting by stating that the ACRS at the June meeting had reached a position on how it plans to handle plants with near-term OLs.
He then read the pertinent portion of the letter that was transmitted to the Staff, as follows: "The Committee expects that the NRC Staff will keep it informed regarding the additional requirements arising.from consideration of the IMI-2 accident being imposed on those plants in which the ACRS has already reported to the Commission on OL applications but for which the OL l
has not yet been issued. We information supplied to the ACRS may be pro-vided either case-by-case or in generic form, as appropriate. The ACRS expectes to review this information and any actions proposed by the Staff and to report thareon to the Commission 'atten considered appropriate by the l
Committee, or as requested by the Commission."
o
THIS DOCUMENT CONTAINS POOR QUAllTY PAGES 800'2' 10 J
,o c
. The Staff had chosen to present this information in generic form as NURDG-0578, "TMI-2 Lessons Learned Task Force Status Report, Short-Term Recommendations."
This repart includes recommendations relating to all operating reactors and to all pending operating licenses.
Dr. 'Siess suggested that the scope for today's meeting should be limited to those things which affect the near-term OLs.
Additional recommendations will be forthcoming from the Bulletins and Orders Task Force for the six near-term OLs of the highest priority interest, the Westinghouse plants. These additional recomendations will be in a Westing-house generic report being written by the Bulletins and Orders Task Force.
There will also be other recommendations in the near-term associated with operator training and licensing.
The Staff stated that the 23 recommendations in NUREG-0578 have been trans-mitted to Mr. Denton for action. The Staff feels that all 23 recom.rendations will be approved with only minor changes.
BULLETINS AND ORDERS - S. Israel, NRC Staff Mr. Israel discussed the requirements that the Bulletins and Orders nystem group will be applying to the PWR plants.
Since there is an overlap in some of the recommendations with the Lessons Learned Task Force, only those not in the Lessons Learned Task Force were discussed by Mr. Israel.
In the area of the auxiliary feedwater system, the following items were discussed:
single suction valve
- alternate water source
- condensate storage tank low level alarm
- pump endurance test
. - water hammer flow
- valve position on loss of air
- actuation on loss of all AC
- technical speci'ications
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In the area of instrumentation, core exit thermocouples that will be monitored in the control room was discussed.
In the procedures area, smll LOCA, extended loss of feedwater, and steam generator dump valve operation were discussed.
2 e program discussed above will be implemented before the near-term OLs are issued.
E.v.ERGENCY PLANNING - J. Miller Mr. Miller represented a group that reviewed emergency planning for all sites including the near-term OLs. He stated that the charter of the group is to implement Regulatory Guide 1.101 to assure the implementation of the Lessons Learned Task Force on operating reactors and near-term OLs, and to assure that the relationship between licensees, and state and local agencies concerning the emergency plans is firmed up.
He further stated that emergency planning will be applied to a distance of 10 miles from the plant, and that test exercises of j
emergency plans involving both state and local levels, including the licensee, will be required. Implementation schedule is July 1,1980.
i TRAINING - R. Bursey Mr. Bursey discussed new training requirements for operators to be licensed in new plants. We training requirements are listed in a Commission paper which will be subnitted for considereatien at a later date. Some of the requirements of the oral and written examinatior.s include all of the MI-related material, response to the Bulletins and Orders, and expansion of the material on heat transfer, fluid flow, and thermodynamics.
In addition, all Unit 1 personnel of a multi-unit facility of the near-term OLs will be evaluated on the basis l
. of grades achieved during the last annual requalification examination.
If an individual received a grade less than 80 percent (formerly 70 percent) overall, he will be required to take a regular examination; if he is an SRO, he will have to take the regular RO and SRO examinations.
The Staff is attempting to requalify current operators of operating plants.
The problem, in part, stems from the unavailability of training slots at a simulator.
In the meantime, the operators of the near-term OLs will be more thoroughly trained than the operators of operating plants.
NUREG-0578, LESSONS LEARNED Dr. Siess then,went through, item by item, the 23 short-term recommendations delineated in NURE-0578. 'Ihese recommendations are deemed by the Task Force to provide substantial additional protection for the public health and safety.
Some of the items of particular interest to the Subcommittee are listed as follows:
Post-Accident Hydrogen Control Systems
- Instrumentation to Follow the Course of an Accident
- Shift Tehnical Advisor
- Revised Limiting Coditions for Operations GENERAL DISCUSSION The Chairman asked if Salem had any problems in meeting the requirements in NUREG-0578. The Applicants stated that, in general, no problems exist in implementing the recommendations in NURE-0578, but they may have space prob-blem for the on-site technical support center. The Staff stated that it should not be a problem because proximity was meant by the Staff to mean that people could be sent to and from the plant conveniently. The center can be "a block" away from the plant.
. i de Subconmittee is still concerned that some plants still require AC power j
for the auxiliary feedwater system to operate. We Staff stated that this concern is now bei.9 addressed by a dedicated task force.
Ice condenser and BWR plants were not covered at this meeting, but were sched-l uled to be addressed at future meetings.
We Subcommittee then agreed to present the Salem 2 matter at the full ACRS meeting scheduled for August.
NOTE: For additional details, a complete transcript of the meeting is available in the NRC Public Docunent Room,1717 H St., NW, Washington, DC 20555 or from Ace-Federal Reporters, Inc., 444 North Capitol St.,
NW, Washington, DC.
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T Federal Register / Vol. 44. No.141 / FrMay.' July ?0.1979 / Notfees 428:7 i
es af ve'e incidents involvirs toniting ail other !! ems regarding this meettrig result [n any signiDeant environmental ratanon ne Agen:y contanwes lo prepare remain the same as announced in the impact and that pursuant to 10 CE for aweb nspor.se ey provid.ra the fcCows'T Faderal Register oc Ju!y 12,1979 (44 E Sectaen $1.5(dK4) an e Mrennental (1) trained s:a? fer advisament required to 4G739k impact statement, or negative Fur *.her informa tion can be obtatnad dec!aration and environmentalimped pped sta'! br by a prepaid telephone call to the appraisal need not be prepared in tr ne a e e.ne gency f.e!d attmtaes.
p; trans;o at.on by automobile to site of Designated Federal E=ployee Icr this connection with issuance of this ine cent meetmg. Mr. Richard K. Majar.
amendment.
14: erabt.s%d f.ason wth a;;topnate (telephone 202/6'#4-1414) between It15 Fcr farther deta:ls with respect to this NP C aad DOE 0;ershons Of".ces. and s.m. and 5.00 p.=, EDT.
action see (1) the application for (5) trame to key personnel of other state /
amendment dated October m Pr78. as DHed My 16.194 local a ges supplemented Jenttery 24.19~S.G)
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Rad.olycal assistance in the forts of John C. Hoyla.
Amendment No.18 te Ucense No. DPR-vionncnng Laison with apprepnate Adnsory Cownittee. Msecrement Oficer.
- 7. and (3) the Commissien's related Sefery balushon. M oMese Hems an se u y a d cles p ep id b.
available for public inspection at the
' ** '4 Agtney ne contawunaan gedes used by 3
Commission's Pubhc Document Room.
the Agency are in Table tilof the Protectaa 1717 H Street. NW. We shington. DC Acton c.mb c:.r.is.n,d to Append.x xL All (Doc M 56-133]
and at the Humboldt County Library, Agency person. el ad be rna.ntained al an 636 F Street. M* a. Cahfornia."A copy operaton-ready leset of tran ira Part of tNo Pacific Cas & Electric Co.;lasuance of of iterna (2) and (3) may be obtained trainrg wf.l te preuded through co:peranen Amendment to Facility Operatane upon request ad&essed to the U.S.
af the NRC m Las Vegas. Nevada.
De Annen C Na! eat Accident orin:5dee Ucenae Nuclear Regulato y Commisslan,
!$eEe drUe ne U.S. Nuc!esr Regulatoe7 Wa shingtor. DC 20555. Attenooa:
a re Commissoon (the Commission) ban Direet:rr. Divisaca of Operating Reactsrs.
a (DCrAl a in:! deJ in Appenia X1 n.a p!an issued Amendment No.18 to Facility Dated a' Be beedatar% nd. this tyh day addresses both transportation a::adents and off s.ie releases fro i f.ned f.cd ties It Operstmg License No. DPR-7. issued to or p, g,3 r,waee cat t e Siate Poke f;rst net.'y Pacific Gas and Dettne Cocipany (the pg gy
. c,,
h DCF A w 5ach ir t -n no*Ies the R atat.c9 licensee). which revised Techsical somas AJ,potto.
Cont ol Agenq tt is the respm sibility c4 the Specifications for cperation of the Ch"l OPl"8 '8C'#"' 85"ch N' 1 R
Asen:) to aduse t>e DCPA the entent of th*
Humboldt Bay Power Plant. Unit No. 3 Demion of Opemters Aractorr bstard to the pubi:: health end safety and (the facihty) located near Eurcia.
recorrsend protectae actions as necessary, Cahfornia. De amecdment is affective N ""'8 "" ** *"4 All hcensees willbe anen rep.e4 cf the plan d b de h hm
'" * " 8C"E "
- sad instructed us proper reporteg cf The amendment revises the Technical incidents wbc.h occur odside of their fa:C;ty, SpeciGcati ns to extend on a oce ti=e
[ Doc M no,so-arsj ino.
uro.a m e.i..i basis the interval for containment integrated leat rate testing unta Pacific Gas & Dectric Co. (Diablo immediately prior to returning the Canyon Nuclear Power Plant. Urdt 1);
,,,Jacihty to power operation.ne Ordee Extending Construction 4
Advisory Committee on Reactor amendment also includes the followttg Completion Date Safeguards. Ad Hoc Subcommittee on adminstrative changes to the Technical Pacific Can and Eectric Company is the Three MJe Island, Unit 2. Accident Specificatient the holder of Cor.structacc Peemit Nps.
Implicat,ons Re Nuclear Power Plant
- 1. Expression of an a3ewable CPPR-39 and CPPR-89 issued by the Design; Add; bon to Agende tolerance for performing sureeulance Atomic Energy Commissioc* os April intervals.
23.1968 and December 9.1970..
De agenda of the July 26-27.19,3 L Addition of a membe'r totheP! ant respectively, for construction of the ' T ~-- ~
meeting of the ACRS Ad Hoc Subcommittee on the Three Ele Island.
Sta!! Redew Committee.
Diablo Canyon Nuclear Power Plant. -
Unit : Accident-Implications Re
- 3. Correction of a typog sphical error.
Urtits 1 and 2 presently under.
Nuclear Power Piant Design, wi!!1ach3de and construction at the Company's siteIn
- 4. Clarification of Ceneral Of5m San Luis Obispo Coimty. California.
the following-Nuclear Power Plant Redew and Asadtt On May 24,1979. Pacific Cas and v
E!ectric Company filed a request foe It'd8F/uly21.28'8 Committee respondbilitzen.
De subco+nnurtee wi!! add ess the tapte of he app!! cation Ice the ameridrnant axtenai.on of the completion date for
~'
1 further ACRS review of pend.rg appbcanons li e & M ards d UML f
requirements of the Atomic Energy Act On Novembee 15.1978, the e
I Is!a L.ru 2 cc d a d
of 1954. as amended (the Act), and the Commission *a staff published M '- r specifically, the Salem Nudeat Power Sashort Urdt : revie w.
Commission's rules and regulationa.De Supplement No. 8 to the Safety Bad ground inforraatton regarding the Commission has made appropriate.
Evaluation Report for the Diablo Saism Nuclear Pow er Station. Unit I can be findings as required by the Act and the Canyon Nuclear Power P! ant -..-
food in occaments on Ce and evacable far Commission *a rules and regula tions in 10 documenting the need to make certain..
pubbe inspection at the NRC Pubbc CFR Chapter I. which are set forth la the modtScations. Consequen'.!y additional.'
Document Roorn.17tr H St. N.W.
license amendment.Pdor pdblic nonce time wm be required to complete the
~ ' * *
% a shrytoet. DC 20551. and at the Salem Tree of this amendment was not required b t.tarary It2 %est Broadwsy.SAIan Since the amendment does notInvolVS A
- Ef'ech, fannery a tes, & Absic Emew
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.ir cani hasarda consideraison.
an v..
V ne Commisslon has detennined that D ','f,',7,# D J,r' Y M M*".
s.ed.wer a-the issuance of this amendment will met c
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Fedees) Rogiste? ' Vol 44. No.135 / "Utursday. July 22. 1979 / Woticos 40739
)
i Endow 7nent for the Ar's. Washington.
consultants. and Staff. Pepsens desiring Date July 10.18-E D C. 20506. or cal (202) $34-6070 to make oral statements should notify John C. Hoyle.
the Designated Federal Employee as far
,4dnsory commme, Morcsement 0$cer.
lohn H Cart arector. C%ce of Coune:londpseef in advance as practicable so that p o.,6 3.n u re t-u,e mm.*
Opa crons Nettonolfndowmentfor the Arts appropriate a*rangements can be made sumo cooe 'see ei e to allow the necessary time durmg the p o.m. s.r ess N t-u-m a as ue meeting for such statements.
sc.no ecce nr.*i-a K'ocket Nos. So-C2 eM M31 The agenda for subject meeting shall be as foHows:
Puget Sound Power & Ught Co, et a!.
Federei Craphies improvement Advisory Panet, Mettmg Thuasday. faly 25 cnd fndJr. fuly 27.
(Skagit Nuclear Power Project Uruts 1 1979. 8 A7 a e untd the concksion of and 2); Order for Evidentiary Hearing Pursuant to sectien to(a)(2) of the and Related Matters busmess each day.
Federal Advisory Committee Act (Public
- 1. MusM to agnemed among d.e Law 92--453) notice is hereby g:ven that The Subcornmittee may meet in parties at a conference in Seattle.
a meetmg of the Fede al Craphics Executive Session. with any ofits
% ashington. on Apnl 24.1979. the Improvement Adviso y Panel to the consultants who may be present. to evidentiary heanng is scheduled to National Endowinent for the Arts will be explore and exchange their preliminary resurne at 9.30 a.m Tuesday. July 1<.
held en July 19.19 9 from 9 30. m. to epmions regarding matters whu.h should 1979.The location of the resumed 4 30 p m. in room 1125. Co!umbia P: ara be considered donng the meeting and to heanns will be at Room 3038. New Office Building 2401 E Street NW.,
! mulate a up n and nec==endation Federal Building 915 Second Avenue.
Washmg'on D C.
the full Committee.
Seattle. Washmgton.
This rneetmg will be open to the At the conclusion of the Executive
- 2. At the begmnmg of the hearuu.
public on a space available basis.
Session. the Subcom:.nttee will discuss hmited appearances pursuant to 10 CFF Accommodations are hmited. Interested with representatives of the NRC Staff.
2.715 will be permitted. Paragraph (a) j persons may submit wntten statementa the nuclear industry. various utilities.
thereof is pertment.
t to the panej and their consultants. state and local f a) A pers:n who is not a par *y may. in the The agenda for this meetms will include a d;scussion of the Graph;c officials and other mterested persons.
d,,:retion or the presiding omer de j
matenal of the Consurner Prod et Safety the implications of the Three %le permit:ed to make a hmited a;pearance by 1
Comrn.ssion.
IslandsUnit 2 Accident.
makma ora! or mntten sta'ement of h:s Furth r mformat.;n with refe ence to in adition. it may be necessary for PC' *" C" O' 'sson at am susion of de heanng or preheanng conference mi
.n such this meeting can be obtained fro = Mr.
the Subecmmittee to hold one or more lance lay Brown. Coordmator of c!csed sessions for the purpose of
[or$r e
not Federal Graphics. National Endowment exploring matters involvir,g proprietary otherwise parucipate m the proceed 2:3 for the Arts. Washmgton. D C. 20506. or information I have determined. in
- 3. Persons wd.ing to mah a btea call ( m ) m 2ao accordance with Subsection 10(d) of 8'
Dated luh e. tra Pubhc Law 92-463. that. should such
, [*n ly 17 99a re ues ed to John H Carl sessions be required it is necessary to gne advance notification to the arcrroa ONe o CocnertendPanel clost these sess:ons to protect Secretary United States Nuclear r
operotons Notena/ Endo m aient for ce.4rts.
propnetar) mformation (5 U.S C.
Regulatory Commission. Washmgton.
p c= %-e ::: r o r.u.* w.m 552b(c)(4)).
D C. 20555. Those planning to make a sec ccee nm Further information regarding topics hmited appearance at the heanng to be discussed. whether the meetmg begmnmg on July 17 are directed to has been cance!!ed or rescheduled the check with the Board's clerk at 9 00 a.m.
NUCt. EAR REGULATORY Chairman's ruimg on requests for the that day at the heanng room.
COM WlSSJON opportunity to present oral statements Done this 58 day of july 19 9 at and the time allotted therefor can be Wa shing% D C.
Advisory Committee on Reactor obtained by a prepaid telephone call to Atomic Safer > and Licensing Board.
Safeguards, Ad Hoc Subcommittee on the Designated Federal Employee for Valentine B. Deale.~
the Trwe+ Mile Island, Unit 2 Accident.
this muting. Mr. Richard K Major.
c3effmen.
Impkcations Re Nuclear Power Plant (telephone 202/634-1414) between 8.15 g3
.,m,.utmsm Desagn; Meeting 8
8 sec com nm I
The ACRS Ad Hoc Subcommittee on
' 'ckground information concerning the Three Mila Island. Umt 2 Accident-this nuclear station can be found in i
Imphcations Re Nuclear Power P! ant documents on file and available for N ATIONAL TRANSPORTATION Desip. will hold a meetmg on July 28-27.1979 in Room 1167.1717 H St NW.
public inspection at the NRC Pubhc,
SAFETY BOARD Documents Room.1717 H Street. N.W Wa shmgton. DC 2c555
{
in accordance with the proceduns Washington. DC 20555 and at the
[N.AA M-29]
Government Publications Section. State outhned m the Federal Registse on October 4.1978 (43 Fst 45926) oral or I.ibrary of Pennsylvania. Education Annual Report to Congress, Accident "wntten statements may be presented by Building. Commonwealth and Welnut Reports, Safety Recommendations, members of the public, recordmgs will Street. Harrisburg. PA 17126.
and flesponses; Availability be permitted only during those portions Annuo/ Report to Congress -The I
of the meetint when a transcript is being National Transportation Safety Board I
kept, and questions may be asked only released its report on June 29 and copies I
by members of the Subcor:=ruttee,its are now avai!able to the public. Sing!e I
..,.. e,.m 7.c.. p,, w. g p.,.. y.,.
4 REVZSION 1 7/19/79 TENTATIVE SCHEDULE ACRS A3 HOC SUSCOMMITTEE MEETING ON THE TMI-2 ACCIDE 1717 H STREET, NW, WASHINGTON, DC, ROOM 1046 JULY 26 & 27,1979 l
N EI$$ @ h[$
kbAbIIPAd[j ITE"5 FOR DISCUSSION ON JULY 26, 1979 - (2:30 am - 7:00 pn What should be the design basis for hydrogen build-up for LWRs? Why?'
1.
Examine events having the potential for overfilling the secondary side of steam generators (e.g., the March 20, 1978 Rancho Seco event).
2.
Examine events ineclving debris arising from structural failure of 3.
pieces within process lines.
to resolve the question of the adequacy of the single failure criterion.
4.
How How to exar.ine the influence of control systems on safety.
5.
6.
Hcw to evalJate the reH t o# possible design changes for future LWRs:
a.
Mcre RHR loops?
b.
Full pressure RHR?
Containment modifications?
c.
d.
Others 7.
How to review EWRs for T".1 Implications.
8.
Generic Ir.plications of Recent LERs:
Loss of pressurizer level indication at Oconee - 3/6/79 a.
b.
Maintenance at Fitzpatrick c.
Others 9.
Auxiliary feedwater system Requirements:
What should be the quantitative reliability requirements? Why?
a.
b.
Others NRR's use of probabilistic techniques in the licensing process.
10.
What is the state-of-
- 11. Control Room Computer Systems for Data Processing.What information is being giv affairs in other plants?
Inexpensive off-the-shelf type equipment is now an order of magnitude L' hat is being asked of utilities inprcvement over the TMI-2 systems.
in this area?
QC.,
l 12; How are decisions nade regarding backfitting requirements?
i l
Discussion of diffuser screens in the surge line entrance to the pressurizer.
13.
postulating a break at the top of the p'ressurizer, will the pressurizer water dump?
la. Which operating procedures will be handled in the short-term? How will the adequacy of other operating procedures be determined? Examples :
(1) Operating Procedures for the SSE.
p g,3 l (2) Operating procedures for a steam line break coupled with a s all primary side break.
i
- 15. Others 4
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. !TE!!S F02 DISCUSSION ON JULY 27, 1979 - (3:30 am - close of business) 1.
Discussion with the NRC Staff on how to apply the results of the Lessons Learned Task Force and the Bulletins and Orders Task Force to the near-term Westingneuse OL stage plants:
a.
design changes b.
operator actions and operating procedures The discussion should focus on the Salem 2 plant as the Westinghouse near-term prototype. The Subcomnittee wishes to explore the procedures and requirements which will be placed on the near-term OLs by the Staff (e.g., how much of the review will be generic and h~ow much plant specific?)
2.
Discussion with PSE&G on how they intend to implement the Staff's require-ments on the Salen 2 Station. The discussion is not intended to serve as a review of the Salem 2 Station, but rather to address Sale: 2 as the pro-totype near-term 's plant.
The other near-ter., Westinghouse OL stage plants are invited to attend 3.
the reeting. Formal presentations are not required, however, they may be able to respond to Subcommittee questions arising out of design dif-ferences between the plants.
Plants included are: Dicblo Canyon, Morth Anna 2. Sequoyah, Farley 2, and icGuire.
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ATTENDANCE LIST ACRS SUBCOMMITTEE ON TMI-2 ACCIDENT IMPLICATIONS JULY 26 & 27,1979 WASHINGTON, DC ACRS NRC STAFF PUBLIC SERVICE ELECTRIC & GAS D. Okrent, Chairman R. Tedesco E. Liden C. Siess R. Mattson R. Mitti J. C. Mark R. Frahm R. Burricelli H. Etherington J. Milhoan H. Heller M. Plesset J. Olshinski J. Zupko, Jr.
I. Catton, ACES Consultant R. Cudlin C. Veprek M. Lipinski, ACRS Consultant T. Telford T. Taylor C. Michelson, ACRS Consultant C. Long L. Reiter R. Major, Designated Federal Employec P. Mathews L. Leitz E. Igne, ACRS Staff L. Beltracchi J. Wroblewski J. Gormiy R. Patterson EPRI PASNY T. Martin F. Schneider R. Leyse G. Rangarao WESTINGHOUSE ELECTRIC CORP.
MCGRAW-HILL GENERAL ELECTRIC J. Scuss B. Adamson N. Shirley W. Gangloff R. Burch J. Frent J. Hord MORGAN, LEWIS & BOSKINS BABC0CK & WILCOX D. Maire K. Jordan E. Epner R. Borsum M. Hartley SOUTHERN COMPANY SERVICES INC.
T. Knight NORTHEAST UTILITIES D. Lamber'.
D. Jaffe J. Raulston E. Foster R. Hernandez D. Wilson TEPCO NUCLEAR PROJECTS INC.
H. Harmader BECHTEL POWER CORP.
J. Kelly, Jr.
W. House, II KEPCO PCOTMI K. Ota VIRGINIA ELECTRIC & POWER CO.
L. Jaffe MeAk (
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2 OFFSHORE POWER SYSTEM 5_
LEHIGH UNIVERSITY DUKE POWER COMPANY J. Chen T. Heitman D. Aabye R. Sundaram I
PUBLIC T. Manjikian, States News Service J. Hebert, Associated Press H. Yocom, Gilbert Associates Richardson, Ace-Federal Reporters, Inc.
D. Hof fman, Ace-Federal Reporters, Inc.
J. Burns, Ace-Federal Rep'orters, Inc.
i A. Riley, Ace-Federal Reporters, Inc.
K. Loryn, BRD J
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- j NUCLEAR REGULATORY COMMISSION WA$HINGTON, D. C. 20555 g
s July 18, 1979 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Roger J. Mattson, Director TMI-2 Lessons Learned Task Force
SUBJECT:
TMI-2 LES50t45 LEARNED TASK FORCE rep 0RT (SHORT TERM) NUREG-0578 Enclosed is the first report of the 'TMI-2 Lessons Learned Task Force.
It contains a set of short term recommendations to be implemented in two stages over the next 18 months on operating plants, plants under There are construction, and pending construction permit applications.
23 specific recomendations in 12 broad areas (nine in the area of design and analysis and three in the area of operations).
The 23 recom-mendations would provide substantial, additional protection which is required for the public health and safety.
All but one of the 23 recomendations have a majority concurrence by the The exception is the recomended requirement to provide Task Force.
capability to install an external recombiner at each reactor plant forThe post-accident hydrogen control, if necessary following an accident.
majority of the Task Force recommends that this matter deserves further evaluation in conjunction with other hydrogen generation and contrcl questions being reviewed by the Task Force for its final report.
Three of the recomendations appear to require changes in existing regulatforts for which the Task Force recommends immediately effective rulemaking. They are:
- 1) inerting of MK I and MK II BWR containments that are not already inerted; 2) provision of the capability to install an external recombiner for plants that do not already have recombiners (minority view); and, 3) revised limiting conditions of operation in operating licenses for total loss of safety system availability through The Office of Standards Development has agreed human or operational error.
to develop the required, Commission papers and carry through with these rulemaking actions.
The 23 recommended actions were discussed with the Re'gulatory Requirements Review Committee (June 22, 1979), the Commission (June 25,1979), the 11, 1979), and the ACRS (July 12, 1979).
TMI-2 Subcomittee of the ACRS (July In addition, meetings were held with various groups in the Office of Nuclear Reactor Regulation in the course of the last few weeks to discuss technical aspects of specific portions of the recomended actions and the implementation alternatives.
ARed D
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'2 Harold R. Denton The Task Force recommends that time not be taken to request and evaluate public coments on these short term requirements prior to their promulgation as licensing requirements or rules because they are safety significant matters that require prompt application to operating reactors and operating license Other TMI-2 accident review groups apolications in the late stages of review.
and the Lessons Learned Task Force are continuing to evaluate the longer term implications of the accident. Any public coments on the short term recom-mendations that are received after their issuance (just as in the case of the earlier IE Bulletins) can be factored into those continuing evaluations.
Having identified the 23 specific recomendations for short tern action, the Lessons Learned Task Force will turn to the broader, more fundamental regulatory questions which should be addressed in the longer term (some of them likely to require evaluations that extend beyond the life span of the These longer Task Force) before other regulatory actions are recomended.
term interests of the Task Force are described in Section Three of the The Task Force intends to develop its final recommendations and The topics to be addressed report.
issue a final report in early September 1979.
in the final report could affect the future structure and content of the licensing process to correct deficiencies identified by the TMI-2 accident and to further upgrade the level of safety in operating plants and plants The Task Force does not believe that allowing new plants under construction.
to begin operation in the next few months will foreclose further design changes that may be shown to be desirable by its continuing review of the accident.
On July ll, I solicited the comments of the principal NRR line organizations on the final draf t of the report and its central conclusior regarding the necessity and ' sufficiency of the short term recomendations for continued operations and licensing. General support for the conclusions of the Task Force report was expressed by all of the principal NRR line managers.
We have reviewed and considered the detailed comments supplied by the vario, NRR organizations in the course of their review. Where appropriate, The principal we made clarifying changes in the language of the report.
substantive change occurred in the form and schedules of tne implementation section (Appendix B).
Some of the comments addressed matters that the Task There are Force has deferred for consideration in its final report.
significant differences of opinion within the staff on two of the Task Force a) the need for recomendation 2.2.3 concerning recommendations, as follows:
rulemaking for revised limiting conditions for operation (some agree with the recomendation and others prefer more stringent enforcement actions using existing regulatory machinery) and b) the need for the minority Task Force recomendation 2.1.5.c concerning rulemaking for backfit of recombiner capability (some support the minority recomendation, others do
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Having considered these comments and made changes to the report where not) appropriate to reconcile them with the intent of the Task Force, I recomend that you:
direct the immediate implementation by DPM, 00R or B&OTF, as appropriate, of all the short term recomendations, except the three rulemaking f
a.
matters, through the issuance of licensing positions to operating plant licensees, plants under construction, and construction permit applicants.
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I i
3 Harold R. Denton I
request the formulation of immediately effective rules by the b.
Office of Standards Development for action by the Comission on the three rulemaking matters.
I Another matter that needs to be considered by you in deciding upon the additional requirements for near term CP and OL decisions and for operating reactors is improvements in licensee emergency preparedness.
i i
y Roger J.
attson,' Director TMI-2 Lessons Learned Task Force
Enclosure:
as stated cc: Chaiman Hendrie Comissioner Gilinsky Commissioner Kennedy Commissioner Bradford Comissioner Ahearne ACRS (20)
Policy Evaluation SECY L. V. Gossick, EDO S. Levine, RES R. Minogue, SD V. Stello, IE M. Rogovin, Special Inquiry J. Fouchard, PA (20)
C. Kactnerer, CA (20)
NRC POR 1
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A (42. G.G 1 n-19 I
DEFINITIONS I
PARTIAL EXAMIMTION - EXAMINATIONS BOTH WRITTEN AND ORAL THAT WILL INCLUDE TMI-2 RELATED MATERIAL IE BULLETINS 79-05,79-05A, 79-06,79-06A AND 79-06B RESPONSE MiERE APPLICABLE AND EXPANSION OF MATERIAL ON HEAT TRANSFER, FLUID FLOW, THERM 00TNAMICS AND DIFFERENCE BETWEEN UNITS 1 AND 2.
REGULAR EXAMINATION - SEVEN CATEGORY RO, FIVE CATEGORY SRO AND ORAL OPER-ATING TEST.
EXAMINATION WILL INCLUDE SUBJECT MATERIAL IN THE PARTIAL EXAMINATION.
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II SALEM 'I - NORTH ANNA II - FARLEY II ALL UNIT I LICENSED PERSONNEL SHALL RECEIVE TRAINING ON DIFFERENCE BETWEEN UNITS I AND II, THI-2 RELATED MATERIAL, BULLETIN RESPONSE AND TO INCLUDE TRAINING ON A SIMULATOR.
ALL UNIT I LICENSED PERSONNEL SHALL BE EVALUATED ON lHE BASIS OF GRADES ACHIEVED DURING LAC.T ANNUAL REQUALIFICATION.
IF M INDIVID-UAL RECEIVED LESS THAN 80.0 PERCENT OVERALL Ht SHALL BE REQUIRED TO TAKE A REGULAR EXAMINATION.
KC WILL ADMINISTER PARTIAL OR REGULAR EXAMINATION TO ALL UNIT I PERSONNEL AS APPLICABLE.
FAILURE TO PASS EXAMINATIONS WILL RESULT IN:
(1) REMOVAL FRCN LICENSED ACTIVITIES ON UNIT I (2) RETRAINED (3)
PIEXAMINED AND MUST PASS BEFORE REstMING LICENSED ACTIVITIES ON UNIT I
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l ALL PERSONNEL WHO HAVE PASSED THEIR WRITTEN AND OR AL EXAMINATIONS BUT HAVE NOT BEEN ISSUED LICENSES SHALL BE REQUIRED TO CCMPLETE ADDITIONAL TRAINING IN TMI-2 RELATED SUBJECTS.
EXAMINATIONS ARE PLANNED FOR FOLH REACTOR OPERATORS AND EIGHT SENIOR REACTOR OPERATORS WHO TET THE COLD ELIGIBILITY REQUIREMENTS.
BASED ON THE RESULTS OF THESE 12 EXAMINATIONS, OLB WILL DECIDE WHETHER OR NOT PARTIAL EXAMINATIONS ARE TO BE ADMINISTERED TO T WHO HAD PREVIOUSLY BEEN EXAMINED BY OLB. A REVIEW WILL BE CONOUCTED OF THE TRAINING RECORDS TO ESTABLISH THAT THE A00!TIONAL TRAINING WAS COMPLETED SATISFACTORILY.
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IV DIABLIO CANYON ALL APPLICANTS HAVE BEEN ADMINISTERED BOTH WRfTTEN MD O TIONS ON Th'0 OCCASIONS.
IN 1978 ALL APPLICANTS WERE REQUIRED TO RECEIVE TRAINING ON THE ZION SIMULATOR PRIOR TO ADMINISTERING THE SECOND SET OF EXAMINATIONS. OPERATOR LICENSES HAVE NOT BEEN ISSUED AT DIABLIO CANYON.
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ALL APPLICANTS SHALL RECEIVE TRAINING IN TMI-2 RELATED SUBJECTS TO t
INCLUDE TRAINING ON THE ZION SIMlX.ATOR. AT THE CONCLUSION OF THE TRAININL AT ZION, NRC WILL ADMINISTER PARTIAL EXAMINATIONS TO ALL i
APPLICANTS.
CANDIDATES WHO FAIL TO PASS THE EXAMINATION ARE TO BE RETRAINED MD I
REEXAMINED.
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McGUIRE ALL APPLICANTS HAVE BEEN ADMINISTERED WRITTEN EXAMINATIONS. ORAL EXAMINATIONS HAVE NOT BEEN ADMINISTERED.
4 ALL APPLICANTS SHALL RECEIVE ADDITIONAL TRAINING IN 1NI-2 AND RELATED SUBJECTS AND WILL BE ADMINISTERED ORAL EXAMINATIONS BOTH ON WE PLANT AND ON THE SIMULATOR.
APPLICANTS WHO FAIL TO PASS THE EXAMINATIONS ARE TO BE RETRAINED AND I
REEXAMINED.
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