ML20213A551
| ML20213A551 | |
| Person / Time | |
|---|---|
| Issue date: | 11/06/1986 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2466, NUDOCS 8702030345 | |
| Download: ML20213A551 (25) | |
Text
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SUMMARY
/ MINUTES OF THE JOINT ACRS SUBCOMMITTEES ON OCCUPATIONAL AND ENVIRONMENTAL PROTECTION SYSTEMS ANDSEVERE(CLASS 9) ACCIDENTS SEPTEMBER 26, 1986 WASHINGTON, D. C.
The Joint ACRS Subcommittees on Occupational and Environmental Pro-tection Systems and Severe (Class 9) Accidents, met in Washington, D. C.
on September 26, 1986 to hear a status report on results of the Seabrook Station Probabilistic Safety Assessment (SSPSA) and updates to this report, which include, in part, the impact of the revised source term and the strength and leak tightness of the Seabrook containment.
In addition, the Chairman stated that other considerations of generic nature such as 1) safety goals and their implementation, 2) source term divorced from WASH-1400, and 3) emergency plans in light of Chernobyl may be discussed.
Notice of the meeting was published in the Federal Register on September 9, 1986 and September 19,1986(AttachmentA). The schedule of items covere,d in the meeting is in Attachment B.
A list of handouts kept with the office copy of the minutes is included in Attachment C.
There were no oral statements presented from members of the public at this open meeting. A written statement was received from P. McEachern, Democratic t
Nomine,e for Governor of New Hampshire. The letter to Dr. Kerr, dated September 25, 1986, registered Mr. McEachern's " strong opposition to the reduction in size of the emergency planning zone for the Seabrook MF, I) lant."(AttachmentC).
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S:ptember 26, 1986 Mtg.
2 Seabrook, OEPS & Severe Class 9 Accidents s
About eight members of the public attended portions of the meeting.
E.
Igne/D. Houston were the cognizant ACRS Staff members for the meeting.
Pr,incipal' Attendees ACRS NRC Staff D eller, Chairman
- 5. Long C. Siess, Member R. Hernan F. Remick, Member R. Barrett C. Mark, Member S. Davis M. Corradini, ACRS Consultant V. Noonan D. Houston, ACRS Staff C. Rossi R. Major, ACRS Staff G. Bagchi E. Igne, ACRS Staff E. Doolittle Public Service of New Hampshire (PSNH)
D. Maidrand J. Moody, Jr.
R. Toland R. White J. Stacey P. Littlefield W. Derrickson J. DeVincentis Brookhaven National Laboratory (NRC Consultants)
R. Youngblood G. Bozoki T. Pratt Pickard, Lowe & Garrick, Inc. (PSNH Consultants)
X. Woodard A. Torri K. Fleming Other L. Correia, Energy and Commerce Committee J. Abbotts, Congress George Lobserr, UPT Danie) Beegan, AP Brad Pokovry, The Boston Globe P. Glsss, 0.Harvey News Service E. Weiss, Ham & Weiss P. Dougherty, News CBS, Boston T. Miller, Patomac News David Beyer, AP
S:ptember 26. 1986 Mtg.
3 Seabrook, OEPS & Severe Class 9 Accidents i
s Meeting Summary Minutes In the opening remarks D. Moeller, Chairman of the Joint Subcommittee stated that during this meeting the Subcommittee will hear a status report by the NRC Staff and Public Service Company of New Hampshire (PSHN)ontheSeabrookStationProbabilisticSafetyAssessment(SSPSA) and related reports. He also stated that further Subcommittee meeting (s) will be necessary before the matter on the emergency planning zone can be brought to the full ACRS for action.
V. Noonan, NRR, stated that PSNH requested NRR to review the technical aspects of Seabrook Station Risk Management and Emergency Planning Study (PLG-0432)andSeabrookStationEmergencyPlanningSensitivityStuds (PLG-0465), which are based on a Level 3 (full blown) PRA performed on theSeabrookStation(PLG-0300). The emergency planning studies are essentially aimed at reducing the emergency planning zone at the Seabrook Station.
Based on results obtained from the SSpSA and update studies, NRR focused its review on 1) containment structural integrity, 2)containmentbypass'and3)interfacingsystemsLOCA.
C. Rossi, NRR, stated that interfacing systems LOCA is a LOCA that simultaneously causes core damage with containment by-pass.
Thus far, preliminary results from the NRR review indicate that significant technical issues have been identified and are being evaluated. The NRR evaluation is not yet complete and no NRC position on this matter has been formulated.
l Anothdr subcommittee meeting should be held when the safety evaluation report (SER)onSeabrookemergencyplanningstudiesiscompleted sometime in the October / November 1986 time frame.
S:ptember 26, 1986 Mtg.
4 Seabrook OEPS & Severe Class 9 Accidents s
The current status of the overall licensing review of Seabrook is listed below:
,,o "The safety review of the fire protection plan is incomplete.
o The onsite emergency planning review is complete.
o The offsite emergency planning review is incomplete. The New Hampshire exercises have been performed; Massachusetts exer-cises needs to be performed.
In reply to a question, the NRC Staff stated that FEMA with its lack of manpower and resources plans to complete its review by April of 1987.
It was also stated that the Massachusetts emergency plan has not yet been submitted and will impact the Seabrook startup schedule.
o Hearings on environmental qualification of equipment, control room design review, and emergency action level determination are not yet complete.
(Scheduled for 9/29 - 10/3/86.)
V. Noonan, stated that results of the latest SALP review resulted in ratings that were all one's except in emergency preparedness where a two was issued because the'offsite exercises were not yet completed. He further stated that to his knowledge this is the best SALP report received from the NRC by any plant, at least in his area of responsibility.
Applitant Technical Presentation W. Derrickson, Sr. V.P. PSNH, presented a brief overview of the project.
Unit 1 is essentially complete and Unit 2 is 24.1% complete and on hold.
S:ptember 26, 1986 Mtg.
5 Seabrook, OEPS & Severe Class 9 Accidents 1
He stated that there are no fuel load open items and that a petition under 50.57 (c) to load fuel and conduct precriticality testing had been submitted in August 1986. With respect to emergency planning, he stated that the Governor of Massachusetts announced on September 20, 1986 his refusal to submit emergency plans to FEMA for review.
In reply to a question, W. Derrickson stated that this had been anticipated and had prompted the Seabrook Station Risk Management and emergency planning study in 1985 to justify a reduction in the emergency planning zone in order to provide PSNH a range of decision options in this matter.
In reply to a question, Mr. Derrickson stated that Unit 1 has 38 licensed people operating in six shifts, and that one Health Physicist has been certified by the Health Physics Board.
D. Moeller encouraged that more health physics people be certified by the Board.
J. Moody, Jr., New Hampshire Yankee and K. Fleming, Pickard, Lowe and Garrick discussed the Seabrook Station Probabilistic Safety Assessment (SSPSA).
The SSPSA was performed at a cost of about three million dollars.
A full-scope Level 3 PSA was performed. NRC contracted Lawrence Livermore National Laboratory and Brookhaven National Laborato-ry to review the SSPSA.
In reply to a question, J. Moody stated that Pickard, Lowe and Garrick have performed about 7-8 PRAs on PWRs in the past. The major conclusions of the SSPSA (completed in 1983) are as follows:
?
6 Early health effects:
The NRC safety goal was met with large margins; interfacing LOCA dominates.
S:ptember 26, 1986 Mtg.
6 Seabrook, OEPS & Severe Class 9 Accidents o
Latent health risks: The NRC safety goal was met with very large margins; support system failures dominate, o
The core melt frequency is low; about 2-3x10~4/ reactor year.
,o Containment was found to be effective; early failure is unlikely to occur and an extended time is required for overpressure.
The SSPSA was updated in 1985 and 1986. The PSA update documents are entitled "Seabrook Station. Risk Management and Emergency Planning Study" or RMEPS (PLG-0432), and "Seabrook Station Emergency Planning Sensitivity Study" (PLG-0465).
The major objective of the latter study was to reexamine the technical basis of the 10-mile EPZ (NUREG-0396) on a plant-specific basis. The key results of RMEPS are listed belcw.
o Early health risk with no immediate protective actions is less than WASH-1400 criteria with a 25 mile evacuation zone.
o Risk reduction by evacuation is very small.
o All NUREG-0396 dose versus distance criteria are satisfied at 1 mile or less, o
The latent health risk is insensitive to assumptions regarding evacuation.
The above favorable results are due to containment effectiveness, source termsiandenhanced(variableortime-dependentparametersincluded)
V-sequ'encemodels(theinterfacingLOCA).
September 26, 1986 Mtg.
7 de dns s
The major conclusions of the sensitivity studies are as listed belcw.
o The WASH-1400 early health risk criteria were approximately
' met with a 1-mile evacuation.
o NRCs individual risk safety goal was met with no immediate protective actions.
o The conditional frequency of exceeding the whole-body dose versus distance criteria was lower for all cases, o
The 1-mile EPZ was justified even assuming the WASH-1400 source term methodology.
The above results and conclusions were reviewed by a peer group consisting of R. Budnitz, D. Aldrich, J. Hendrie, N. Rasmussen, R.
Ritzman, W. Stratton and R. Wilson.
In essence, the peer group concurred with the findings of the studies and indicated that the conclusions were robust even in light of uncertainties in the PSA methodologies. The Seabrook containment strength was a major factor in the favorable conclusions.
It was stated the NRR/BNL have reviewed and approved the stress /st'rength analysis of the Seabrook containment.
The major contribution to early release frequency was an assumed scenario of an earthquake with an open purge of the containment. This scenario contributed to about 87 percent of the frequency of occurrence.
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J. Moddy stated that the Seabrook risk management and emergency planning activities are continuing.
September 26, 1986 Mtg.
8 Seabrook, OEPS & Severe Class 9 Accidents s
NRR Presentation S. Long, NRR, presented the scope and focus of the Staff's review. The purpose o' the review is to identify and review the portions of the f
principal conclusions study that are most sensitive with respect to the applicant's study, which are listed below, o
The individual risk of early fatalities at Seabrook is within the safety goal.
o The 1-mile evacuation at Seabrook provides a similar level of risk of early fatalities to the WASH-1400 results with 25 miles evacuation.
o The probabilities of specific radiological exposure levels at 1 mile from Seabrook are less than the corresponding probabil-ities shown at 10 miles in NUREG-0396.
In reply to a question, D. Mathew, I&E, stated that FEMA is not involved in determining the technical validity of the risk management study al-though at some point FEMA may be involved.
S. Long stated that the basis for comparison will be WASH-1400 source term methodology with respect to early fatalities and whole body doses.
In reply to Subcommittee questions, S. Long stated that the effective dose qquivalent method will not be used.
In addition, PSNH agreed that the CRACIT code does not include the latest health effects model.
September 26, 1986 Mtg.
9 Seabrook, OEPS & Severe Class 9 Accidents W. Pratt, C. Hofmayer and R. Youngblood, BNL, discussed the status of BNL review of the Seabrook Station Emergency Planning Sensitivity Study.
The f,ocus of their review will be on containment structural integrity, maintaining containment function with respect to isolation failures and interfacing system LOCA and study completeness (investigations of other accidents sequences that might lead to early large releases).
At the conclusion of the meeting Dr. F. Remick called attention to a paper entitled "A Rational Approach to Emergency Planning Zone Definition," by M. Hazzman and E. Warman, dated September 22-23, 1986, TP86-86, which was presented at the ANS First Regional Conference (Pittsburgh,PA.). He suggested that this paper be read and studied by the NRC Staff and PSNH.
In this paper, analyses of exposure risk with past and present source terms illustrate the substantial reduction in calculated risk resulting from new improved knowledge and understanding, l
as compared with WASH-1400 Technology.
[ Note: ThereportwasgiventotheNRCStaffandPSNH.]
i j
Subcommittee Actions f
l The Subcommittee decided to provide a status report on SSPSA and update studies to the full ACRS during the October 1986 meeting with PSNH participation. Another Subcommittee meeting on this matter is planned when the NRC Staff's SER is completed (October / November 1986).
NOTE:
A transcript of the meeting is available in the NRC Public Document Room, 1717 H St. NW., Washington, D. C or can be purchased from ACE Federal Reporters, 444 N. Capitol Street, Washington, D. C. 20001 (202) 347-3700.
m ATTACHMENT A y ggg g
O*['h 32154 Federal Register / Vol. 51 No.174 / Tuesday. September 9,1986 / Notices m part. oy the DBA hydrogen connection with the " Final containment. A status report on recombiner s3 stem when it is fully Environmental Statement Related to emergency planning around Seabrook tested.
Operation of Nine Mile Point Nuclear will also be heard.
The applicant has stated that the DBA Station, Unit No. 2", dated May 1985.
Oral statements may be prescrited by r combiners can only perform a function Agencies ondPersons Consulted:The members of the public with the during a post LOCA with degraded core NRC staff reviewed the applicant's concurrence of the Subcommittee condition. The applicant further stated submittals that support the requested Chairman: written statements will be that this condition is not possible until exemptions A through E above.The accepted and made available to the after mitial power operation.
NRC staff did not consult other agencies Committee. Recordings will be permitted
.Wdfor the P vposed Action:The or persons.
only during those portions of the it he bility to Finding of No Significant Impact meeting when a transcript is being kept.
he a p$ica pro d and questions may be asked only by load fuel without hasing the DBA The Commission has determined not rnembers of the Sdcommmee, Hs,,
hydrogen recombiner sy stem to prepare an environmentalimpact c nsultants and Staff. Persons desinng operat.onal. Preoperational testing of s'atement for the proposed exemptions.
t m ke oral statements should notify Inis s3 stem w;il be completed prior to Based upon the foregoing the ACRS staff member named below as mitial criticality. This exemption would environmental assessments. the far,m advance as is practicable so that provide the applicant mth greater Commission concludes that the appt pnate arrangements can be made.
preoperational fletb.hty and, therefore, proposed actions will not have a expedite the start of power operations.
significant effect on the quality of the During the intial.,jortion of the Ennronmentcl/moact of the Proposed human environment.
meetmg. the Subcommittees, along with Action The esemption would allow the For further details with respect to this any of their consultants who may be applicant to defer operability of the action. see the requests for the present, may exchange preliminary i
DBA hydrogen recombiner system until exemptions as listed herein, which are siews regarding matters to be l
sfier the fuel is loaded but prior to initial 'available for public inspection at the considered during the balance of the criticality.
Commission's Public Document Room, meeting.
Smce prior to initial criticahty the 1717 H Street. NW., Washington, DC The Subcommittees will then hear DBA hydrogen recembiner system 20555, and at the Penfield Library, State presentations by and hold discussions performs no function as DBA post University College, Oswego, New York with representatives of the Public LOCA conditions are not possible until 13126.
Service Company of New Hampshire.,
l the NRC Staff, their consultants, and (fler initial criticality the staff Dated at Bethesda. Maryland.this 3rd day concludes that granting the proposed of September 1986.
other interested persons regarding this l
res ic w.
g relief will not increase the probability of For the Nuclear Regulatory Commission.
an accident and will not result in post-Elmot G. Adensam, Further information regardiiig topics t
cecident radiological releases that are D, rector, a WR Pmiect Directorate No J.
to be discussed, whether the meeting greater than those presiously Da,,,on of s wR iacensieg has been cancelled or rescheduled, the d;termmed for the Nine Mile Point IFR Doc. so-20289 Filed 1HMs. 8 45 cml Chairman's ruling on requests for the Nuclear Station, Unit 2. Moreover, the opportunity to present oral statements auseo cooe neww proposed relief will not otherw1se affect and the time allotted therefor can be r:diological plant effluents not result in obtained by a prepaid telephone call to rny significant occupational exposure.
Advisory Committee on Reactor the cognizant ACRS staff member, Mr.
Likewise, the relief does not affect non.
Safeguards; Joint Meeting of the Richard Major (telephone 202/634-1414) radiological plant effluents and has no Subcommittees on Seabrook and between 8.15 a rn. and 5 00 p.m. Persons cther ensironmental impact. Therefore.
Occupational and Environmental planning to attend this meeting are the Commission corcludes that there are Protection Systems urged to contact the above named to significant radiofogici or non*
individual one or two days before the r:diological environmental impacts The ACRS Subcommittees on scheduled meeting to be advised of any associated with this proposed relief.
Seabrook and Occupational and chang es in schedule, etc., which may Altmo. e to the Proposed Action Environmenal Protection Systems will hase occurred.
The staff has concluded that there is no hold a joint meeting on September 25, 2
measurable environmentalimpact 1986. in Room 1046.171711 Street. NW.,
Dated September 3.1986.
Casociated with the proposed Washington, DC.
Morton W. Ubarkin, cxemption. Any alternatises to the The entire meeting will be open to A ssis tant riccurac Derectorfor Project proposed esemption will have either no public attendance.
Be "* ".
environmental impact or greater The agenda for the subject meeting lFR Doc. e6 20287 Filed IMM6. a45 aml shall be as follows: Thursday, aumo cooe neww environmental impact The principal alternative would be to September 25.1966--l.00p.ar. until the deny the requested relief and conclusion ofbusiness.
cxemption. Such action would not The Subcommittees will gather and PACIFIC NORTHWEST ELECTRIC reduce environmentalimpacts of the exchange information with the NRC POWER AND CONSERVATION
- Nine Male Point Nuclear Station. Unit 2 Staff and PSNil.The Subcommittees PLANNING COUNCIL cperations and would result in reduced will review preliminary efforts by the (perational flexibihty and unwarranted, applicant to reduce the size of the Advisory Committee Meeting; delays in power ascension.
emergency planning zone (EPZ).This Correction Notice Alternative Use of Resourt:es:These etfort uses results of the Seabrook
. actions associated with the granting of Probabilistic Safety Assessment to AGENCY: Pacific Northwest Electric the proposed eternptions as detailed justify a smaller EPZ. A primary focus Power and Conservation Planning will be the credit taken for the strength Council (Northwest Power Planmng above do not involve the use of.
andleak tightness of the Seabrook Council).
resources not previously considered in
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to be discussed whether the meeting to make oral statements abound actify has been canceUed or rescheduled, the the ACRS staff member named below as september 12. tese, Chairman's ruhng on requests for the far in advance as is practicable so that
[FR Doc. es-atto3 Filed 6-to-se; tes am]
opportunity to present oral statements appropriate arrangements saa be made.
aussa osos rem and the time allotted therefar can be During the taltial portion of the obtained by a prepaid telephone cab to asseting, the Submunedtten, along with *
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,I NUCt. EAR, REGULATORY 3.G.lgne (telephone 302/634-1413) present, may exchange preliminary g,33 between 8:15 a.m. and 5:00 pm Persons views regarding matters to be 3
planning to attend this meeting are considered during the baianas of the
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. Advisory Committee on Reactor urged to contact the above named meeting.
i, Safeguards, Subcommittee on indivudust one or two days before the ne Subcommittee willthenhear.
Standardtaation of Nuclear Facetties; scheduled meeting to be advised of any presentations by and bold discussions P.
Meeting changesinschedule,etc whichmay with representatives of the NRC Staff. -.
%e ACRS Subcommittee on
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Its consults, and other Interested
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persons regarding this review. ~ ~ ^ ~
will hold a meeting on October a,1eso, tsorten W.laarkin.
Further information regarding topios -
4 Room 1066,1717 H Street. NW.
Assissue hecutiee Dirvesarfor Pnvest to be discussed, whether the meeting has been cancelled or rescheduled, the p
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y%e entire meeting will be open to p h mos h p tesW Qairman's ruhng on equats fu b -
'o Opportunity to present oral statemente Public attendance.
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Advfoory Committee on Reactor the cognizant ACRS staff member,Mr.
J til the Conclusloo of Businese Safeguards, Subcommittee on M. El-Zaftswy (telephone 202/634-82s7) e Westinghouse Reactor Plants; Meeth0 between t15 a.m. and 520 pm Persons i
ne Subcommittee will review the
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%e ACRS Subcommittee on ct a
ve n e im !ement the NRC standardization Westinghouse Reactor Plants will hold a y
po{ icy ststement.
meeting on September 25,19e6, Room scheduled meeting to be advised of any Oral statements may be prwented by 1066,1717 H Street. NW., Washington, changes in schedule, etc, which usay -
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only during those portions of the
(. t meeting when a transcript is being kept.
He first portion of the aseeting will be (FR Doc.es-213os Filed 614-en; a:45 amj
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and questions may be asked only by closed to discuss proprietary members of the Subcommittee,its information regardin6the PDA review of p;
. consultants. and Staff. Persons desirlag the Westinghouse Advanced
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to make oral etstements should notify Pressurized Water Reactor (RESAR $P/VAdvloory Committee on Reactor
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'as far in advance as is practicable so la addition, at approximately lik45 Subcommittees on Seabrook,.'
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any of its consultants who mey be members of the public with the.
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32154) contained notice of a joldt *.*;.
views regardina matters to be Q
considered dur{ng the balance 6f the Chairman: written statements wl!! be' meeting of the ACRS Subcommittees es Seabrook,Occupationaland v.t.L.
accepted and made available to theCommittee. Recordings will be per i~
meeting.
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presentations by and hold discussions only d those portions of the Severe Accidents scheduled for,; f,s.
with representstives of the NRC Staff,, meeting w en a transcript is being kept, ' September 25.1986 ha reacheduledforfriday,Septembera,'
its consultants and other interested and questions may be asked only by( -
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Fcd:ral Reg!st:r / Vcl. 51, No.162 / Friday September 19, 1986 / Notices
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.. Street, NW., Woshington. DC. All other River Unit No. 3 Nuclear Generating reduce the need for unnecmary 1
items regarding this meeting remain the Plant, located in Citrus County, Florida.
removal of the reactor vessel head.%1s In accordance with the Ifeensee's would result in the reduction of same es previously announced.
application dated August 14.1986, the unnecessary personnel radiation 5
Further information regarding topics Proposed amendment would extend the exposure involved with this evolution a to be discussed.whether the meeting surveIDance interval from once per 18 wou as a reduction in the probability of has been cancelled or reacheduled, the months tb once per fuel cycle, a reactor vessel head drop.
ne licensee reports that since 1978, Chairman's ruling on requests for the Permanently for reactor vessel internals the eight RVVVs at CR-3 have each opportunity to present oral statements vent valves (RVVVs) and for Cycle 6 and the time allotted therefor can be on! for high pressure inject'on (HPI) been tested six t(mes for a total of 48 g
tbtained by a prepaid telephone call to an low pressure injection (LPI) pumps functional tests without a single failure.
4 the cognizant ACRS staff member, Mr.
and valves.
This data pars!!els that of the other
,i E. Igne (telephone 202/634-1413)
Before issuance of the proposed Babcock and Wiledx(B&W) operating between 8.15 a.m. and 5:00 p.m. Persons license amendment, the Commission reactors. Industry records (from 1973 planning to attend this meeting are will have made findings required by the through the present) indicate, in B&W urged to contact one of the above named Atomic Energy Act of1954. as amended operating reactors with an approximate Individual one or two days before the (the Act) and the Commission's total of 80 reactor years of operation, that not a single RVVV has ever failed scheduled meeting to be advised of any regations.e Commission has made a proposed to demonstrate satisfactory operability chang:s in schedule, etc., which may have cecurred.
determination that de amendment in over 420 functional tests, and no Dated: September 15.1986-request involves no s!gnificant hazards RVVV has ever stuck open.
consideration. Under the Commission's The RVVVs are constructed of Morton W.ubarkin.
Assistant Executive Directorfor Project regulations in 10 CFR 5092, this means materials that have satisfactory that operation of the facility in corrosion resistance to the reactor Aertew.
(FR Doc. 86-21M0 Tued M8-86. 8.45 am) accordance with the proposed coolact environment. Tight reactor amendment would not (1) involve a coolant chemistry controls are also owns coot neo.es-=
algnificant increase in the probability or maintained to assure any corrosion that is in fi ul consequences of an accident previously evaluated; or (2) create the possibility of not c sidered eyta pe abilif (Docket No. 50-249 EW; Special a new or different kind of accident from of these valves willbe affected by Proceedinsi any accident pr eviously evaluated; or (3) corrosion.
Edward Wallace, GPU Nuclear involve a significant reduction in a story of ene vakes C;rpiration,Three Mile f aland Nuclear margin of safety
- demonstrates they are very reliable.%e only previous degradation of these Statlin, Unit No.1; Assignment of Reactor Vessel lnternals Vent Valves valves, due to wear, did not affect their b
Atomic Safety and Uconalng Appeal The Crystal River Unf t 3 (CR-3) operability and has been corrected.
)
D So:rd reactor design includes eight RVVVs Since then. no further wear indications r
Notice is hereby given that,in that would be used to relieve the on the RVVVs have been discovered at recordance with the authority conferred pressure generated by steaming in the CR-3.
by to CFR 2.787(a). the Chairman of the core following a loss of coolant Similar amendments have been issued Atomic Safety and Ucensina Appeal accident.This assures that the reactor to other B&W plants. Industry data and Panelhas assigned the follewing Panel core will remain covered with water.
plant specific date on these valves members to serve as the Atomic Safety However if the valves are stuck in the indicate that the existing surveillance tnd Ucensmg Appeal Board for this open position during normal operation, a interval may be permanently changed to cperating hcense proceeding: Alan S.
portion of the coolant will bypass the
- 'at le ast once per fuel cycle" without Rosenthal, Chairman. Dr. W. Reed core.Therefore, the operabfIfty of the impacting the operability of these Dhnson, and Thomas S. Moore.
RVVVs must be assured. Existing valves.
Technical Specifications require testing Based on the above, the amer.dment Dated: September 12.1986.
of these valves once per 18 months will not:
C. Jean Shoemaker, during shutdown.
L Mn a spant basein b Secretary to the AppeclBoard Due to de knge oMe last refueling probability or consequences of an
[m Doc. 86-2Du Fded MS-46. 8.45 am) and the recent forced reactor coolant accident previously evaluated because pump (RCP) outage at CR-3, the past operating experience of thsee surevillance for the RVVVs will be valves in the industry and at CR-3 has 4
J' required to be performed prior to the shown they may be expected to remain
[}
(Docket No.50-3021 end of the current fuelcycle, operable for periods far greater than 18 Surveillance was not performed on the months.
Florida Power Corp. et al.t RVVVs during this recent forced outage
' 2. Create the possibility of anew or i
CInalderation of laauence of since the surveillance necessitates different kind of accident from any Am:nd:nont to Fac!!!ty Operating removal of the reactor vessel head, accident previously evaluated because Uc;nse and Proposed No Significant which was not done.ne surveillance the proposed change introduces no new Hazards Conalderation Determlaation for the RVVVs is currently required to mode of plant operation nor does it and Opportunity for Hearing be completed by November 1988 The U.S. Nuclear Regulatory.
However, the fuel cycle la not scheduled require physical modification to the Ccmm!ss!on (the Commission)is to end until October 1987.
plant.
- 3. Involve a significant reduction in i
The change to the surveillance considering issuance of amendment to interval would eliminate the necessity, the margin of safety.Past testing and 4
operating experience of these valves has Facility Operating Ucense No. DPR-72.
for mid-cycle shutdowns to perform tma
!ssued to Florida Power Co poration(the surveillance.The change would also shown that they are highly reliable.
l licensee), for operation of the Crystal _
l 1
1 ATTACHMENT B c,
TENTA!!VE MEETING SCHEDULE COINT MEETING OF THE ACRS SUBCOMMITTEES ON OCCUPATIONAL AND ENVIRONMENTAL PROTECTION SYSTEMS AND SEVERE (CLASS 9) ACCIDENTS R00M 1086 - 1717 H STREET, NW, WASHINGTON, DC WEDNESEAY, SEPTEMBER 26, 1986 8:30 A.M.
'1.
CHtPIFAN'S INTROCUCTION (15 mins.)
8:45 A.P.
2.
NRC STAFF INTRODUCTION (15 mins.)
A.
Staff Staterent of Purpose B.
Current Status of Seabrook Review (interaction and status of FEMA review)
C.
Results of latest SALP 9:00 A.M.
2.
PUELIC SERVICE OF NEW HAMPSHIRE INTRCDUCTION (15 mins.)
~
A.
Construction Status of Seabrook 1 & 2 3.
Significant Open Activities 9:10 A.M.
4 OVERVIEW OF SEABPC0K STATION PROBABILISTIC (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
SAFETYASSESSMENT(SSPSA-PLG-0300)
(PSNH)
A.
History, Scope, Description of Methodology B.
Prircipal Recommendations, Insights, and Conclusions C.
Gereral Discussion 10:15 A.M.
EREAK ------------------
(15 mins.)
10:30 A.M.
5.
SEAERCCK STATION PROBABILISTIC SAFETY ASSESSMENT (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
UFCATE (PLG-0432, PLG-0465)
(PSNH)
A.
Introducticn B.
Results and Conclusions C.
SSPSA Plant F del Update D.
Scurce Ter.s and Conta'crent Analysis E.
Site Analysis l
12:30 P.M.
LUNCH (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 1,30 P.M.
6.
OVERVIEW OF SCOPE AND FOCUS OF NRC STAFF REVIEW (15 mins.)
(NRC Staff) 1:45 P.M.
7.
STAFF DISCUSSION SSPSA INSIGHTS AND CURRENT (15 mins.)
STATUS (NRC Staff) t
2:00 P.M.
8.
CR TEP.IA FOR COPFARISON REVIE 0F NUREG-0396 (15 mins.)
AS IT RELATES TO PLG-0455 and PLG-0432)
(N?.C Staff) 2:15 P.M.
9.
STATUS OF NEC/ CONTRACTOR REVIE'4 0F THE (I hour) 55PSAMET99:0 LOGY A.
Source Terns B.
Risk Analysis C.
Contairrent Structural Integrity D.
Containrer.t Sypass E.
Interacting System LOCA 3:15 P.M. 10.
CONCLUDING REMARKS BY PSNH (15 mins.)
3:20 P.M. 11.
CONCLUDING PEMARKS BY NRC (15 mins.)
- 3:45 P.M. 12.
SUSC0FMITTEE GENERAL DISCUSSION AND FUTURE (15 mins.)
AC' ION (NOTE:
li hrs. currently scheduled for the Octcher full ACRS Meeting on Friday, October 10,1986) 4:00 P.M.
ADJ0LEM'ENT l
l b
I' TENTATIVE MEETING SCHEDULE JOINT MEETING OF THE ACRS SUBCOMMITTEES ON OCCUPATIONAL AND ENVIRONMENTAL PROTECTION SYSTEMS AND SEVERE (CLASS 9) ACCIDENTS ROOM 1046 - 1717 H STREET, NW, WASHINGTON, DC WEDNESDAY, SEPTEMBER 26, 1986 8:30 A.M.
1.
CHAPIFAN'S INTRODUCTION (15 mins.)
-&45 A.M.
2.
NRC STAFF INTRODUCTION (15 mins.)
E.4o MW WM A.
Staff Statenent of Purpose B.
Current Status of Seabrook Review (interaction and status of FEMA review)
C.
Results of Latest SALP
-M)0 A. M.
3.
PUBLIC SERVICE OF NEW HAMPSHIRE INTRODUCTION (15 mins.)
W 4'S w IB u QERt Q sov A.
Construction Status of Seabrook 1 &
<s. v.P.
e s p et B.
Significant Open Activities R.syJ
-9 : 10 A.M.
4.
OVERVIEW 0F SEABROOK STATION PROBABILISTIC j 1 hou l
SAFETY ASSESSMENT (SSPSA-PLG-0300)
( PSNH,)3'*
2 5 0)%-
'l e. w i,)
% \\/t t. c c. i. ;
r d) i A.
History, Scope, Description of Methodology O EC '-' -
b " d * '-
," ^/ B.
Principal Recommendations, Insights, and Conclu5'ibn'5'-- q kg.t F L Oa W C.
General Discussion P'6 MA
)
t o. 2c B RE AK - ----- ------------
(15 mins.)
-10:15 A.M.
cro (PSNH) g.12_ hours
-10:3C-A.M.
5.
SEABROOK STATION PROBABILISTIC SAFETY ASSESSMENT W,.
lo S$
UPDATE (PLG-0432, PLG-0465) fad W4 A.
Introduction YS-B.
Results and Conclusions C.
SSPSA Plant Model Update D.
Source Terms and Containment Analysis E.
Site Anslysis
.g (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
LUNCH
-it:-30LP.M.
--1+30 P. M.
6.
OVERVIEW 0F SCOPE AND FOCUS OF NRC STAFF REVIEW (15 mins.)
1: yD (NRC Staff) Den e L og
, Py e3, q y-1:45 P.M.
7.
STAFF DISCUSSION SSPSA INSIGHTS AND CURRENT (15 mins.)
STATUS (NRC Staff)
ans
--2 :00- P.M.
8.
CRITERIA FOR COMPARISON REVIEW 0F NUREG-0396 (15 mins.)
AS IT RELATES TO PLG-0465 and PLG-0432)
(NRC Staff) O AV6 W CT M wi ) %56
-3:15 P.M.
9.
STATUS OF NRC/ CONTRACTOR REVIEW 0F THE (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 7N SSPSA METHODOLOGY c5 g
Source Terms
- A.
Risk Analysis' y
'B.
C.
Containment Structural Integrity D.
Containment Bypass E.
Interacting System LOCA 3:15 P.M. 10. CONCLUD1HG REMARKS BY PSNH (15 mins.)
3:30 P.M. 11.
CONCLUDING REMARKS BY NRC (15 mins.)
3:45 P.M. 12. SUBCOPftITTEE GENERAL DISCUSSION AND FUTURE (15 mins.)
ACTION (NOTE:
li hrs. currently scheduled for the October full ACRS Meeting on Friday, October 10,1986) 4:00 P.M.
ADJ0URNt'ENT l
l l
l
~
~
ATTACHMENT C LIST OF HANDOUTS 1.
Seabrook Station Probabilistic Safety Assessment 2.
Joint Meeting of the ACRS Subcommittee on Occupational and Environmental Protection Systems and Severe (Class 9)
Accident - Seabrook Station, September 26, ]986 Vincent S. Noon, Director, PWR Project Directorate No. 5 Divsion of PWR Licensing-A - slides 3.
NRC Staff Presentation to the ACRS on the Seabrook Emergency Planning Sensitivity Study 4.
10 Mile Emegency Planning Zone Upon 4 Principals Considerations 5.
Status of BNL Review of Seabrook Station Emergency Planning Sensitivity Study - Brookhaven National Laboratory 6.
Arational Approach to Emergency Planning Zone Definition by M. J. Hazzan, E. A. Warman, Stone & Webster Engineering Corp.
Presented at ANS First Regional Conference, Pittsburgh, PA Sept. 22-23,1986 7.
Memo to W. Kerr from Paul McEachern, Democratic Nominee for Governor l
of New Hampshire dated Sept. 25, ]986 8.
Drawing of Seabrook Station, Seabrook, NH l
?
o
E. IGNE OCCUPATIONAL & ENVIRONMENTAL PROTECTION SYSTEN/
ACPS SUBCOMMITTEE MEETING ON SEVERE (CLASS 9) ACCIDENTS LOCATION Room 1046,1717 H St. NW.
DATE September 26, 1986 ATTENDANCE LIST PLEASE PRINT:NAME AFFILI ATION h hohd'r. YWO-N/A bn k S/kuW N&A b+
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DATE September 26, 1986 ATTENDANCE LIST i
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