ML20141E552

Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl

ML20141E552
Person / Time
Site:	Dresden, Peach Bottom, Browns Ferry, Fermi, Catawba, Wolf Creek, Point Beach, Hope Creek, Byron, Turkey Point, Callaway, Waterford, Maine Yankee, 05000000
Issue date:	09/26/1985
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-2350, NUDOCS 8601080151
Download: ML20141E552 (14)

Text

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SUMMARY

/ MINUTES OF THE SEPTEMBER 10, 1985 MEETING 0F THE ACRS REACTOR OPERATIONS SUBCOMMITTEE WASHINGTON, D. C.

A meeting was held by the ACRS Subcommittee on Reactor Operations on September 10, 1985 in Washington, D.C. The purpose of the meeting was to discuss recent operating occurrences. Notice of this meeting was published in the Federal Register on Tuesday, August 27, 1985 Attach-ment A). Attachment B is a copy of the meeting schedule. Attachment C is a list of meeting slides kept on file at the ACRS Office. The entire treeting was open to the public. Richard Major was the cognizant staff member for the meeting. The meeting began at 1:00 p.m.

Participants:

NRC Staff ACRS E. Rossi J. Ebersole, Chairman R. Hernan D. Ward, Member E. Weiss C. Wylie, Member G. Hammer C. Michelson, Member J. Henderson G. Reed, Member V. Hodge R. Major, ACRS Staff H. Bailey T. Colburn Others J. T. Beard R. Gilbert D. Whittier, Maine Yankee T. Alexion A. Wegele, Detroit Edison Wm. Jones E. Oesterle, Bechtel G. Gears J. Trotter, NUS F. Cherny J. Carter, Morris News Papers A. Dromerick S. Keselenio, Nevan & Holtzinger N. Chrissotinos J. Kelly W. Hazelton Seabrook 12/84 Main Steam Safety Valve Flow Deficiency Mr. G. Hammer of NRR made this presentation. The concern was that full flow test results indicated spring-actuated main steam safety valves may not achieve rated flow capacity. This could create a possible inadequate overpressure protection of the secor,dary system in PWRs using these valves. During the tests adjustments were made to ring setting 1[k 8601080151 850926 y g ", cT:.% L PDR ACRS u Coctif!M P7.

7 .>l REACTOR OPERATIONS 2 September 10, 1985 Meeting adjustments. Following the adjustment full lift and rated flow were achieved. There may be generic implications to this event for other plants using similar valves and discharge piping. Normally full flow tests to adjunct ririgs are not used. An IE information notice is being prepared. This item may be pursued as a generic issue. Fermi 2 7/2/85 Premature Criticality Mr. E. Weiss of IE made this presentation. The reactor was brought critical prematurely from startup. There was a significant procedure violation but safety limits were not violated. An error in following procedures caused this event. Instead of pulling each rod in a group four steps as a first increment, the operator pulls each rod 48 steps (full out). The operator should have been made aware of several short period alarms while pulling the group 3 rods to their full out location, but was not. When it was recognized the reactor had gone critical all rods were inserted and the event terminated. The rod worth minimizer was operating at the time, but does limit a rod pull to four steps rather than 48 steps. The corrective action is additional operator training. Hope Creek 9/4/85 CO Release 2 Mr. J. B. Henderson, IE, made this presentation. This event was an inadvertent actuation of CO used in the plant fire protection system. 2 The system ~is programed to discharge 2 tons of CO but actually 2 discharged 10 tons during this event. The licensee believes the problem was caused by a faulted control panel which has been returned to the manufacturer for evaluation. The plant is still under construction. There are doors that have not yet been installed. This situation allowed the C0 to spread more than it would have at the completed 2 - plant. -The event was also complicated by the fact a site emergency response drill was underway. When the event happened warnings were not

REACTOR OPERATIONS 3 September 10, 1985 Meeting believed. Twenty-three people were taken to a local hospital. The extent of injuries was not known. Turkey Point 3 7/21/85 Post Trip Loss of Auxiliary Feedwater Mr. J. Henderson, IE, discussed this event with the subcommittee. The event started when Unit 3 tripped due to a lightning strike. AFW was used for a time. The plant was being brought back to line using one main feed pump when the unit experienced a second trip. During this second trip all three turbine-driven AFW pumps became inoperable during the post-trip recovery period. It was noted that Turkey Point is the only site other than Davis-Besse with no electric driven AFW pumps. The safety significance of this event was the impairment of decay heat removal capability. Two of the turbines tripped to lock out on a mechanical overspeed trip. The flow control valve on the third unit failed. It is felt that the governors on the turbines malfunctioned due to high pressure control oil, created during the period after the first trip. The third AFW pump turbine cycled running to the overspeed (electric) reset position (which was set too low) and dropped below the full speed position. Water was being pumped by this third AFW pump, but without much control. Main feedwater was recovered and the plant was cooled down. The Staff believes the overspeed trip problem may be generic to a sizeable class of turbines. NRC follow-up actions were as yet undefined. Turkey Point 3, 4 7/23/85 Potential MSIV Failure at Low Steam Flow Mr. V. Hodge, IE, made this presentation. The issue centered on the fact MSIVs won't close without steam assistance because air accumulators are too small. The problem applies to Turkey Point and Robinson. The current requirement is fcr MSIVs to close in 5 seconds, even at low steam flow. The threshold steam flow is not known, but it is assumed to exceed AFW capability. For a MSLBA continued blowdown is possible. As A

REACTOR OPERATIONS 4 September 10, 1985 Meeting justification for continued operation, sufficient instrument air is assured by:

1) a diesel air compressor that backs up the plant system,

2) fossil plant systems are tied in for backup and 3) the plant will shut down on failed instrument air supply. Design modifications will be made to assure MSIV closure in the tech. spec. 5 seconds, without steam assistance. It was also noted that testing of these valves was inadequate. They should have been tested with loss of actuator power which includes both electric and instrument air power. This has now been corrected.

Turkey Point 4/8/85 Recent Multiple Inverter Failures Mr. H. Bailey, IE, presented this issue. Turkey Point has experienced 16 inverter trips in 4 months. Five inverter losses resulted in reactor trips in two months. These events challenge safety systems and interaction between plants whice could result in a potential dual-plant trip. The fact both Units shcre DC buses raises the potential for interaction between the units. The old "EXIDE" inverters are being replaced by new " SOLID STATE CONTROLS" inverters. The new inverters are designed to minimize interaction between Units 3 and 4 when loading and unloading inverters. Procedures have also been upgraded and operators retrained in dealing with the loss of the 120V instrument panel. Point Beach 1 7/25/85 Loss of Offsite Power Mr. H. Bailey, IE, presented this incident. The plant was operating at 100% power when a loss of offsite power resulted from the lockout of 1X04 low voltage station auxiliary transformer. Several buses including safeguards buses were affected. The EDGs started immediately and loaded onto the safeguards buses. The licensee commenced shutdown per tech, specs. Within the hour power was restored to the remaining buses from the main generator. Approximately three hours later the IXO4 transformer was declared operable and offsite power was restored. The l ~

REACTOR OPERATIONS 5 September 10, 1985 Meeting Unit began to return to full power. In another 20 minutes, normal offsite power supply was restored to safeguards buses. All systems functioned as designed. Point Beach 1 and 2 7/23/85 Safety Injection Recirculation Line Design Deficiency Mr. T. Colhurn, NRR, presented this issue. The problem centers on the ) single failure of control circuitry for either safety injection recirculation line isolation valve which could result in overheating and damage to both safety injection pumps. The failure of the control circuitry would also fail the control room annunciator (the valve could be shut and the operator be unaware of it). The problem is only applicable for spurious safety injection signals and small break LOCAs where primary pressure is maintained above safety injection shut off head. The problem was discovered during an emergency operating procedures review and verification. Administrative controls were l enacted to provide a short-term fix. Sever 1 long term fixes are being considered, and a schedule is being developed. A Part 21 notice was issued by the licensee; this problem may be generic to other Westinghouse two-loop plants. Maine Yankee 8/7/85-9/3/85 Comon Mode Problems with Steam Generator Pressure Indication J. T. Beard, NRR, presented this topic. On 8/7 it was found that root valves were "not fully open" for 9 of 12 n%ure transmitters. On September 3 during a refueling outage test, it was revealed the "A" pressure channel for each steam generator would not trip due to a design i modification error in the grounding. The significance of this event is that the pressure instrumentation would not have responded properly to a steam line break accident; both the closed valves and grounding error 1 I I

4 s., REACTOR OPERATIONS 6 September 10, 1985 Meeting existed for an entire operating cycle. Diverse instrumentation would have actuated the safety functions if required. It was noted with regard to the root valve problem that they were not on any checklist. If the instrumentation gave a proper pressure indication, the licensee had assumed the valves were open. However, leakage in the closed valves caused satisfactory steady state indications. But the instruments would respond only slowly to a transient. In the case of the design error, a modification was made which tapped off another signal from each loop to provide inputs to the sub-cooling meters. Another signal common was established without checking for a common in the existing circuit for the reactor protection system. This resulted inplacing resistors in parallel and giving an average pressure signal, rather than the auctioneered low signal desired. Design reviews failed to find the error. There was no postmodification testing of the reactor protection system. As a' result of these occurrences the utility will have performed an independent design review of all plant modifications that have ever been made. Secondly, the utility will perform a comprehensive set of tests to verify the function of safety systems. Dresden Unit 2 8/16/85 Loss of Offsite Power Mr. R. Gilbert, NRR, made this presentation. A failed transformer caused the loss of one of two offsite power divisions. Normally the circuit would have fast transferred to a station auxiliary transformer; however, a wiring problem in a lock-out relay prevented the transfer, Loss of feedwater pumps caused a plant trip which caused loss of power to the auxiliary transformer and finally a complete loss of offsite

REACTOR OPERATIONS 7 September 10, 1985 Meeting power. All safety systems worked. Loads were picked up by the diesels and the reactor coolant system was cooled, using the isolation condenser which requires-only DC power to align. RCS make-up was supplied by a single CRD pump. Reactor level and pressure stabilized three hours into the event; offsite power was restored after four hours. The Staff was concerned about the automatic transfer design deficiency. It has been corrected. The Staff has asked the licensee to review their conformance with GDC-17. Electric Power Systems. Browns Ferry 8/19/85 Cable Trays Seismic Qualification Mr. Eric Weiss, IE, presented this topic. It has been known since 1981~ that cable trays at Browns Ferry were overfilled. It was discovered that many hold-down clips have missing bolts. Further review indicated that all seismic loads were not considered in the design _ of the cable tray supports.. There is also a question of cable ampacity due to the flamemastic which was applied to the cables. This problem applies to all three units. The trays are not seismically qualified for interim or long-term operation. TVA has hired eight UE&C personnel to perform an interim evaluation. Callaway 8/20/85 Electrical Power Transient Mr. T. Alexion, NRR, presented this incident. While bumping down the . generator output voltage a voltage regulator was lost. This created a loss of the main generator field which tripped the generator and then the reactor. There was a loss of_ power from the auxiliary transformer to the non-safety related buses and the RCPs tripped. The non-safety buses re-energized 2-3 seconds later. There was no loss of power to the ESF buses. All automatic response systems worked properly. The plant ~ remained on AFW for 5-10 minutes until the RCPs were restored. ~ E

REACTOR OPERATIONS 8 September 10, 1985 Meeting Waterford 3 Wolf Creek Callaway Catawba Byron Start-Up Experience Comparison Mr. W. Jones, IE, presented this topic. A comparison of these five new plants was made. Event reports for each plant were tallied over a four-month period. Significant Event Reports, reactor trips, personnel errors, and equipment problems were counted. Peach Bottom 3 8/19/85 New Pipe Crack Indications Mr. G. Gears, NRR, made this presentation. A reinspection of Unit 3 recirculation and RHR lines for IGSCC revealed new indications. Numerous cracks were indicated by the new GE " SMART" UT system. Cracks were discovered on welds which had no indications under previous inspections. One crack was called at 360*, 35-55% through-wall. The Staff believes there is a high probability cracks were " missed" under earlier inspection programs. Their findings confirm recent test results en cut-out welds that cracks have been missed. Questions are now being raised on the quality of reinspections. It was also noted that between 1983 and 1985 not only has UT equipment been improved, but the training given to UT operators has increased. The BWR Owners Group is being asked to address these questions in a meeting with NRR on September 20, 1985. The meeting was adjourned at 5:35 p.m. NOTE: A complete transcript of the meeting is on file at the NRC Public Document Room, 1717 H Street, N.W., Washington, DC or can be ob-tained at cost from Ann Riley & Associates, Court Reporters, 1625 I Street, N.W., Suite 921, Washington, DC 20006, telephone (202) 293-3950.

T-J. 34773 Federal Register /' Vel. 50, N.186 / Tuesd.y. August 27, 1985 / N:tices Crosse Boiling Water Reactor (t'he Besed on its review, the staff th1 cognizant ACRS staff member, Mr. f;cility) at the steady. state power levela concludes that issuance of this Richard Majot (telephone 202/634-1414) n exemption will have no significant effect between 8:15 a.m. and 5 00 p.m. Persons lI n:t in excess of 165 megawatta thermal. e facility is a boiling water reactor on plant safety, Further, this action is in planning to attend this meeting are ocated at the licensee's site in VernoQ the public interest sadgood cause has urged to contact the above named k County, Wisconsin.%e license been shown to support the exemption. Individual one or two days before the. provides, among other things, that it is' . Therefore, a 60-day exemption from the scheduled meeting to be advised of any subject to all rules, regulations and date ofissuance of this exemption is changes in schedule, etc., whicitmay '~ Orders of the Nuclear Regulatory being granted for the subinittal of an have occurred.. i C:mmission (the Commission) now or-updated FSAR for the La Crosse Boiling Date: August 21,19s5. hireafter in effect. Water Reactor.

• • '"
• M Pursuant to 10 CFR 51.32, the H

Commission has determined that the A88/8'88' E"c"'i" Di"c80'lo' A'/*c8 A* ** Section 50J1(e)(3)(ii) of10 CR Part granting of this exemption will have no 50 requires that those plants initially significant impact on the environment (FR Doc. abaDem Med bas-a5445 am) " "" C0" **** subject to the NRC's eystematic (30 FR 33656, August 20,1965). evaluation program (SEP) must file a Accordingly, the Commission has complete updated Final Safety Analysis determined that: pursuant to 10 CR Report (FSAR) within 24 months after 50.12. an exemption la authorized by law OFFICE OF MANAGEMENT AieO receipt of notification that SEP has been and will not endanger life or property or BUDGET c:mpleted. By letter dated July 20,1963. the common defense and security and is th2 s'affinformed Dairyland Power otherwise in the public interest. OFPP Po5cy Letter 85-1--Federal Cooperstive that SEP has been Therefore, the Commission hereby Acquieltion Regulation System completed fbr the La Crosse Boiling approves the ic!!u ~ temporary Asassev: Office of Federal Procurement Water Reactor (LACBWR) and that, exemiation from co ance with Policy (OFPP), Office of Management pursuant to 10 CR 50.71(e)ile an(3), the i 50.71(e)(3). licensees was required to. An unds'ed FSAR containing those and Budget. updated FSAR. Dy letter dated July 12, original passa of the FSAR that are still AcTioet Final Policy htter. 1963, the licensee requested an. applicable plus new replacement pages sunsasany: This Policy latter is issued to. cxemption to defer submittal of the shall be filed on or before a date so days update fSAR for 60 days. from the dve ofissuance of tnis Implement c9ttain authorities and ne final report.

• Integrated Plant exemption.This updated FSAR shall responsibilities of the Office of Federal.

Procunment Policy contained in Pub. L Safety Assessment. Systematic bring the FSAR up to date as of a 9F400 as amended by Pub. L 96-43 and Evaluation Program" for the La Crosse maximum of 6 months prior to the date Bolling Water Reactor, NUREG-0827, of filing the uipdated FSAP, with Pub. L 98-191 concerning the definition ( m:odifications.ne licensee *s July 12. b d several open item that required subsequent revisions no less frequently and maintenance of the single system of further evaluation and plant than annually thereafter. simplified Government-wide s procurement regulations. Dated at Bethesda. Maryland, this 21st day oATt The effective date of this Policy 1965 letter states that these changes of August 1985. required the full. time utilization of Letter is October 1,1985. For the Nuclear Regulatory Commission. . LACBWR's small engineering staff and that the majority of the design changes Hugh I. %ompace, Jr* William Maraist, Office of Federal Dimetor Di on o/L'censm.s. Office of Procurement Policy, OMB,726 Jackson were completed during the refueling cutage inMarch April 1985. Since that NuclearReactorRegulation. Place, NW, Weshington, DC 20503. (202-time, the LACBWR staff has been [FR Doc. c5-20400 Filed 6-20-as; 8.45 am) 395-3300). srgaged in conducting the engineering smesesTAny eseromeATiose % a me mm review of the updated FSAR.He / Office of Federal Procurement Policy licensee indicated that it needs an Act (Pub. L 93-400 as t. mended by Pub. cdditional 80 daya to ccmplete the Advisory Committee on Reactor L 96-83 and Pub. L 96-191) provides,in tctivities associated with submitting Safeguarda; Subcommittee on Reactor part. b following-update FSAR. Operations; Rescheduling of Meeting ne NRC staff considered safety Sectica 4. As used in this Act-{41the term repects of the requested exemption froim The Federal Register published on "singfe system of Government-wide p " ' ^ ' the update FSAosubmitta! date. The Friday, August 16,1985 (50 FR 33135) proposed axemption affects only the contamed notice of a meeting of the issued and maintained joint!> by$a Go m ent p m the General required date for updating the FSAR and. ACRS Subcommittee on Reactof Services Administration, the Department of does not affect the risk of facility Operations to be held on September 9 Defense, and the National Aemnautics and cecidents.ms, the granting of the 1985 has been changed to 7uesday. Space Administration....and (B) agency requested exemption will have no September 10.19s5,1:00p.m Room acquisition regulations implementing and signibant impact on plant safety. JoddL 1717HStreet. NW, Washington, supplementing the Government. wide e. DC. All other items mmain the same as procurement regulation.... previously published. Section e(s).The Administrator shall I3

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%e public interest will b5 served by Further information regarding topics provide overall direction of procurement ting the exemption since the to be discussed. whether the meeting policy and leadersh;p in the development of neee used its nnel to complete has been cancelled or rescheduled. the p unt systems d the axacuuve '8 other work of er safety significana Chairman's ruling on requests for the S ction e(d).no functions of the sooner than would be the case if opportunity to present oral statements Administrator shall include-(t) providing personnel were diverted to updats the and the time allotted thenfor can be leaderehlp and enrains action by the FSAF @ p4*L

.0.

. obtained by a prepaid telephone call to - executive sgancies in the estabh=at. ' s m.e *, O e g', em t l

g .er w M Y .J _.~ G.9;s.p$. Fed;r:1 Regist:r / Vcl. 50 No.150 / Friday. August 18,,1985 /=Natisse 'a' Un-J AK ~ R ~'~ - -- IV bcEwsts's cosaMmerrs om suPPLERO(r 1 Org] g{a&gpggg ggyj pgemm%.amOy ' Accordingly, pursuant 1o Sections 103, To NUREG-0737-Continued members of the av.b!M arish concursemoe 1611,1610, and 182 of the Atomic Energy ,g g g g g,, sm Act of1954, as amended, and the Tm. 4.wa. ore ,, g.;r Mh b Commith. W ' W s wGl k m de Commission's regulations in to CFR .um=4 2.20s and to CFR Part 50,it is hereby ed @ W % ~ Wons of ms % when add-ordered. effective lmmediately that a.u,,,o a,sf 2 m u ,,,,,,,i, facility operating license No. DPR-34 is SW NRC transcriptis be kept.and 43esseises modified to provide that thc licensee _ ggy g. g gmsngey, gg. y . o,,,,pe.

• Subcommittee,its maaltans= godSta!!.

shall: Implement the specific items

====ry e.oort sores Q'S ' Persons desW to ade eral a.- described in the Attachment to this order m the manner desenbed in PSC's statements shoal,!potify the ACRS staff =.e members as farin advance as submitfals noted in Section Ill herein no 88**",,"a' practicable so that appropriats later than the dates in the Attachment. ,p,,,

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- am se. m as o= v Extensions of time for completing "J'"7, . E,*,1, arrangements can be made... /n 3{. _ana During the initial portion of the these iterns may be granted by the em-s.,cv Director, Division of Licensing. NRR, for g g'a= e=,"' any ofits consultants who may be meeting, the Subcommittee, along with good cause shown. samcaern present, may avt hany prelhninary - V Yee m t views mgarding snatkrs to be j su niem,e an em s.ame,' considered during the balanrw of the The licensee or any other person with e a' meeting. j an adversely affected interest may D ne Subcosamittee wSI then bear ~ request a hearing on this Order within auw.= aa sene.

4. omen si.

presentations by and hold <har=..lons 20 days of the date of publication of this with representatives of the NRC Staff, Order in the Federal Register. Any Proose ens.o. m

• its consultants, and other interested N,,,,,,,,,',e request for a hearing should be w mas,7 persons regarding this nylew.

addressed to the Regional ,.m see. Further information regarding topics Administrator. Region IV, U.S. Nuclear 5 L"=S"ev Q=' 'd

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to be discusaed.whether the meeting Regulatory Commission. 611 Ryan Plaza ., m, r.c., Drive Suite 1000. Arlington, Texas has been cancelled or rancharhdod, the 7tiO11. A copy should also be sent to the s eq,,- uh,M ". Chairman's ruling on requests for the ' ,,u. opportunity to oral statements Executive Legal Director, U.S. Nuclear j ', 4 'sc Enwy.ncy ' sc. cepe. as and the time tied therefor can be Regulatory Commission. Washington, 7 j' '* *- <btained by a prepaid telephone call to DC 20555. A request for hearing sha!! the cotmfrant ACRS staff member,Mr. not stay the immediate effectiveness of ' g,q,,g;gy,l",7,,,,,,,,,,,, Elpidio Igne (telephone 302/634/1414] this order. .e,.=w a If a hearing is to be held, the g.4ssa ner between 8:15 a.m. and 5fl0 p.m. Persons Commission willissue an Order plannInf to attend this meeting are designating the time and place of any [FR Doc. 85-19622 Mled 8-15-45,8 43 am) urged to contact the above named aumsocome - , individual one of two days before ihe such hearing. If a hearing !s held concerning this scheduled meeting to be dvised of any changes in schedule,etc,which may Order. the issue to be considered at the Advisory Committee on Reector' have occurred. hearing shall be whether the licensee Safeguards Subcommittee on Metal should comply with the requirements set Componenta; Meeting Datd August u te85. forth in Section IV of this Order. nsartoe W.ubarkin. This Order is effective upon issuance. The ACRS Subcommittee on Metal Assistant Executive DirectorjbrPrayect Components will hold a meeting on u. Review. Dated at Bethesda, Maryland, this 2nd day September 4 and 5,1985 Room 1048, [FR Doc. 85-29825 Filed 8-15-48; ties am) of August.1985. 1717 H Street NW Washington DC. ausso coor veme ei.as For the Nuclear Regulato:y Commission. To the extent practical the meeting will be open to public attendance. mPson,j" Director. Division officersing Ofice of However, portions of the meeting may dylaory Committee on Reactor Nuc/corReactorRegulation. be closed to dicass GeneralElectric Safeguards Subcommittee on Reactor proprietary information. Operations; Meeting Octusers CouurrMENTs oN SUPPLEMEMr 1 agenda for subject meeting shall e ACRS Subcommittee on Reactor.

• • {

To NUREG-0737 Wednesday, September 4.1985-8;$0 . Operations will hold a meeting on ax.n a.m. until the conclusion of business September 9,1985, Room 1048,1717 H re, nowrem. s ,",,,"5,",'*", nursday, September 5,1985-8:30 a.m. Street NW., Washington, DC. l aaw until the conc!cslon of businese %e entire meeting will be open to The Subcommittee will review public attandance. ,,e,,,,,,,, P> ,.wr is m Regulatory Guide 1.99, Revision 2, and %e agenda for the subject aseeting l other related concerns, and discuss the shall be as follows: I o m,sy.==

• • w' I

,,I,7 gun'c. status of the NDT of piping program and Monday, September A 125--not7p.m. to seos wr ik awahno ' the HSST program.The Subcommittee . untiliaeconclusianofbusmass j 1 L"'"* ** will also review steam genaretor girth ne Subcommittee will discusa recen ver.a weld cracks. 1 operating occurrences,. s

r-33135 Feeleral Regioene / Vol 58 No.159 / Fridey, August 1g.1985 / Notices Oral stetemend esey be preseefed by

• Ar.ib.,

fish'section-Hydro - Northwest Electric Power and members of the pobhc with the-Assessament Studpr concurrenceof theSubcosmeittee '"

• Discussion ofIssue Papers..

Cameervation Planning N=ril 1> (Northwest Power P!anning f'?=df). ( Chairmerc written statements wfB be-

• FERCupdate Actos: Notice of meeting tobe held eccepted and inade eveileble to the
• Other. '

pursuant to the Federal Advisory Commktee. Recordings wit! be peemitted'

• Publiccomment Committee Act. 5 USC AppenEx L 1-only during these portmns of the Status:Open

4. ActMties wulinclude:

. meceing when a transcript is being kept. - cnd questions may be asked only by suneesAsty:The Northwest Power

• Deash dn sidd na members of the Sebcommittee. Its Planning Council hereby zenounces a substitutions issue consultants, and Staff. Peesons desiring forthcoming meeting ofits Hydropower e Disdn @

WW to make oral statements sheekf notify Assessment Steering Counmittee. g, the ACRS staff member named below as DATic August 13,1985.1090 a.m. d @h inn far in advance as is practicable so tiret g,,, ann. & meeting willbe heldin . Reedent fish productivity test aree cppropriate arreir.4 can be meds the Council's Meeting Room,850 8.W. report During the trntial portion of the Broadway. Suite 1100. Portland. Oregon.

• Other
• "8 I

b Pon PunTHan esponenATsoss CONTACT:

• Publiccomment present. =say exchange gethminary Peter Paquet. 503-m81.

Status: Open. views regardirts matters to be Edward Sheets. suesesastv:m Northwest Power considered dwing the bolsace of the. ^==awDunsor Planning Council hereby annoucas a meeting. [FR Doc. 86-1953 Phd 8-15-4R tes am) The Wttee win them home forthcoming meetira of its Resident Fish - -. co*E ""** presentauens by and held disc===I,== Substituticas Advisory Committee. i with representatives ei the NRC Staff. DATu-August 20,1986. 9:30 a.m. its co==1*==*= and otherlaterested Production Planning Adiveery - Aconsse:& meeting wul be held at persons regarding this rwiew. Cosmanittes;Nottoe the Ramada Inn. Room 200, Spokane d Further informados regardlag topass. s International Akport.Spakane, ta be discussed,whetime the meseurg Aanscv:ProductionPtameng Advisory . haa beencanceled or r# Mi the - Committee of the Pecific Northwest Washington. m enronnafiorsconTAcvt Chairman't rulias on revisas for the, ] Marty Montgomery. 206434-2s43. n 3 opportuasty to present arel stala=== cnd the time allotted therefor saa he p;anning CoM. Edward Sheets, cb4 aimed by a prepaid telephone cau to, AcTisse Notice of meeting to be held E'rde Dh. I the cogniamat ACRS samff mammher her. . pursuant to the Federal 4dvisory. Richard hisjor (telephone 202/634-1414} ' Committee Act. 5 U.S.C. Agtpendix 1,1-

• L *
• C088 8"S *
• betwees 835 a.mi. and 5:00 p.m. Pereces

4. ActMties wiu fnchide:

-plannlag to asetand this meeting are... 4 Discussion of ym-y artalysis urged to <=asmee the aben named '. . Issue paper SECURITIES AND EXC$4ANGE 4 Individual one or two days befare the :

• Discussion of production investment COMMLSSION

. schedaled meeting to be advised of any policies issue paper ~ hangesis schedale, air wiuch may

• Discuarton of resident f!sh c

[ Release No. lC-14870; File No. 812-4147) l have occurred. subsHrnemna insaa papes .t Dad Angut 12, M . Othes The Ufo insurance Company of Marnom W. Liberkan.

• Public commet Virginis et aig Emnptfre AppsceGon E

.~ Assismas r==, *'m Duurserfar Proyecs Status: Open. August s.tasa Review. suesmaart.h Northwest Power Notice le hereby given that The Life [FR Des. air. astm PGod 6-as-eas k46 ami Planning Psmant H beeeby=====a== a insurance Company of Vttgmia (the

=== com ionee .. forthcorning nosetag of its Fredactuus " Company"), Life of Virginia Separate Planmsey c-h Account I( Account ), and Life of Virginia Security Sales, Ltd. (" Security O ^*N88 4* 888' "3"' PACIFIC HORTHWEST ELECTRIC ' Sales"), referred to collectively hertia es POWER AND COteSERVATIOle..>r; , Aconesse& muting wff! be bekila " Applicants",6610 West Broad Street. the CouncTs meeting room. 850 5.W. Richmond. Virginia 23230, fued an PLANNING COUNCs.1*., s ~, Broadway Suite 1100, Portland, Oregon application on July 1,1985, for an order

",1 - ; _ ; a a======* Steertny ~

Post FunTHER WIPonetAT90st CosITAcTt of the Commission, pursuant to secbone Committee;temethus s ? Roa Eggers,503-222-5181..,. ,g'gy ,g _ -_ g .w Edwami Sliesen, ". 11(a) and 11(c) of the Act. approving the .- e terms of certain offers of evchange la SteeringrW=mittee of the Pacific Erecutiw Duessna connection with certain flexible M NortBwest Electric Pbwer and.*,.* (,, [FR Dos.as4ee54 Fund MHs;ases seg Caservatin Planning Ctamd!'. ~; same cons menea,,, . referred to the application on file with (Nh Power PlurmfngW Actione Notice of needng to be held "s the Commission for a statement of ( Resident Flatim W Applicant's representatfons, which are PommesN the Pederal ComadRoe Act,5DAC E CommRtes %. summarized below, and are referred to the Act and the rules thereunder for a 1-4.Astsvities weliumindse .+.*. Aoency: Resident Fish Substitut>omo statement of the relevant statutory (River maman==motsesdy.H.9 p.,5 Advisory Committee of the Paafts provisions. ~ ' ~ . n.M.;yar;& pre.W ..+. . m ,..y a.. .e r. ' %.q;Jg. g,M.4.* - f J l ~w l

e a PROPOSED SCHEDULE ACRS REACTOR OPERATIONS SUBCOMMITTEE MEETING SEPTEMBER 10, 1985 WASHINGTON, D.C. 1:00 PM 1. Chairman's Introduction - J. Ebersole (10 min) 1:10 PM 2. Discuss Recent Plant Operating (3 hrs,35 min) Experience (SEEATTACHEDLIST) BREAK (10 min) 3:00 PM 4:45 PM 3. Select items to be presented to the (15 min) full Committee on Thursday, September 12,-1985 from 8:45 to 10:45 A.M. 5:00 PM 4. Adjourn

Attachment:

List of Recent Significant Events s 9 .,y

As of September 5, 1985 ~ Tentative Agenda for ACRS Subcommittse Meeting on September 10, 1985 -1:00 p.m. Room 1046, H Street RECENT SIGNIFICANT EVENTS Presenter /Officee Date Plant Event telephone 12/84 Seabrook Main Steam Safety Valve Flow Deficiency G. Hammer, NRR 492-8963 7/2/85 Fermi 2 Inadvertent Criticality D. Lynch,idtR 492-7050 8/8/85 Turkey Pt. 3 Post Trip Loss of Auxiliary Feedwater J. Henderson, IE 492-9654 9/4/85 Hope Creek Inadvertent Actuation of Fire J. Henderson, IE I Suppression System 492-9654 7/23/85 Turkey Pt. 3 MSIV Problem V. Hodge, IE 492-7275 4-8/85 Turkey Pt. 3 Recent Inverter Failures H. Bailey, IE ~ ' 492-9006 7/25/85 Point Beach 1 Loss of Offsite Power H. Bailey, IE 492-9006 7/23/8S Point Beach Safety Injection Recirculation Line T. Colburn, NRR Deficiency 492-4709 8/7/85 Maine Yankee. Common Mode Problem with Steam Generator P. Sears, NRR Pressure Indication 492-7458 8/16/85 Dresden 2 Loss of Offsite Power R. Gilbert, NRR 492-7128 8/19/85 Browns Ferry Seismic Design of Cable Trays E. Weiss, IE 492-9005 8/20/85 Callaway 1 Electric Power Transient T. Alexion, NRR 492-8929 6-8/85 Waterford Startup Experience Comparison Wm. Jones, IE Wolf Creek 492-7613 Callaway Catawba Byron 8/28/85 Peach Bottom Pipe Cracks G. Gears, NRR 492-8362

6 ATTACHMENT C ACRS REACTOR OPERATIONS SUBCOMMITTEE MEETING SEPTEMBER 10, 1985 WASHINGTON, D. C. Meeting Slides 1. A package of 38 slides was used in the various presentations. The slides are kept with the original copy of the minutes on file at the ACRS Office. i j I a ATTACHMENT C .}}