ML20198H252
| ML20198H252 | |
| Person / Time | |
|---|---|
| Issue date: | 03/24/1986 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2385, NUDOCS 8605300229 | |
| Download: ML20198H252 (30) | |
Text
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"?Wihpg0I&L.c Poe esta94 CERTIFIED MINUTES DATE ISSUED: March 24, 1986 MINUTES ACRS SUBCOMMITTEE MEETING ON REACTOR OPERATIONS JANUARY 7, 1986
- WASHINGTON, D. C.
A meeting was held by the ACRS Subcommittee on Reactor Operations.
Notice of the meeting was published in the Federal Register on December 16, 1985 (Attachment A). The schedule of items covered in the meeting is in Attachment B. The list of attendees is in Attachment C. A list of the meeting handouts is in Attachment D. The handouts are filed with the office copy. H. Alderman was the Designated ACRS Staff Member. The meeting was convened at 8:30 a.m.
s Principal Attendees ACRS NRC U . Ebersole, Subcommittee Chairman C Rossi C. Michelson R. Hernan D. Moeller B. Gallo G. Reed V. Panicera D. Ward E. Greemon C. Wylie S. Miner H. Silver V. Thomas D. Lynch J. Giitter T. Johnson S. Long )
8605300229 860324 M. Campagnone PDR ACRS R. Singh 2385 PDR G. Rivenbark ,
B. Clayton l g; B. Neighbors '
', K. Cook gIi' a u . DESICNATED ORIGINAL CQ1e1 sy '
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SUMMARY
/ REACTOR OPERATIONS 2 l January 7,~1986 Subcommittee Mtg.
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Opening Statement - J. Ebersole, Subcommittee Chairman i i Mr. Ebersole noted the purpose of the meeting was to discuss recent plant operating experiences. He noted that the Offices of Inspection and Enforcement and Nuclear Reactor Regulation-have identified a number
! of current events for discussion with the Subcommittee. He also noted j that the Subcommittee had received a report from Mr. Michael Childers of Northeast Utilities on the effects of Hurricane " Gloria" on the 1
i Millstone Nuclear Power Station Units 1 and 2.
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l He requested each member to rate each event as a candidate for full
! committee presentation.
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S. Miner, NRR, Rancho Seco - October 2, 1985 i !,
, The reactor tripped from 15 percent power due to high primary system i 1
i pressure caused by a trip of both main feedwater pumps. Later they had 3 f uncontrolled cooldown of over 110 F. in 15 minutes, f
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i i The primary cause of the cooldown was the lifting of the steam relief l valve in one of the feedwater heaters, i i l The "A" main feed pump was tripped by a defective high pressure trip !
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l switch. When the "A" pump tripped, the operator tried to increase the
. speed of the "B" pump, but could.n't get it increased fast enough. He i
i i tripped the pump which initiated the auxiliary feedwater system.
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SUMMARY
/ REACTOR OPERATIONS 3 January 7, 1986 Subcommitte2 Mtg.
At that particular time, the auxiliary feedwater pumps were started off of low pressure on the discharge side of the main feedwater pumps, but the control valves were opened by a separate signal that was taken off the turbine on the main feed pumps. When the "A" pump tripped and the "B" pump was at minimum speed, the auxiliary feedwater pumps were operating, but the valves weren't opened. The operator knew that if he tripped the "B" pump he could open the valves and get auxiliary feedwater into the steam generator. Following this incident the high pressure switch was replaced. Trip monitoring equipment was installed on the feed water pumps to be able to diagnose any future trips. The auxiliary feedwater instrumentation system has been modified so that the same parameter would start the pump and open the valves so there is actually low discharge pressure on the main feed pump.
Rancho Seco - Auxiliary Feedwater Pump Failure The thrust bearing on a auxiliary feedwater pump failed because a 1
slinger ring was installed improperly. The bearing was repaired and the slinger ring was checked to make sure it was in place and then the pump was endurance tested. All the rest of the safety grade pumps were checked to make sure the same thing didn't occur.
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SUMMARY
/ REACTOR OPERATIONS 4 January 7, 1986 Subcommitte2 Mtg.
- Rancho Seco, December 10, 1985, Reactor Trip Main feed control was in the process of being transferred from manual control to automatic. The reactor was at 91 percent power. During the transfer process the main feedwater flow increased. The operator in looking at the flow meters returned the control of the main feed flow to manual, and in looking at the meters, the "A" meter responded and the "B" meter hung up. The operator didn't recognize that the "B" meter was hung up and he thought the flow hadn't reduced. He then reduced the flow further and got a high pressure scram.
The safety valve on the 4th paint feedwater opened which was due to a 20 percent overshoot in the contro11er. The problem was diagnosed right away and the safety valve was shut before overcooling occurred., The ,
controller was reset to a. lower level. -
Rancho Seco, Power Failure in the Integrated Control System The ICS failed at 76 percent power, the reactor tripped, and an over- :
cooling event occurred of about 180 F. in about 24 minutes. This event resulted in an Incident Investigation Team being set up. Mr. Rossi noted that the ACRS will be briefed following the conclusion of this investigation.
A committee member inquired to what extent does the absence of main steam isolation valves in essence degrade the turbine driven pumps since
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SUMMARY
/ REACTOR OPERATIONS 5 January 7, 1986 Subcommittce Mtg.
you don't have any steam pressure to drive them? The response was they wouldn't degrade at all because they are upstream of the main feed and the turbine stop valves are upstream. Mr. S. Miner added there is a valve on the linie and they just go and shut the valve. He noted the valve is on the main header.
Mr. Rossi pointed out that the situation on this plant without MSIV's is that they have to go in and do individual valve isolations depending on where the problem is, and there is no question that this increases the
- probability of having some sort.of failure.
l H. Silver, NRR, Crystal River Unit 3, November 22, 1985 Mr. Silver pointed out that Crystal River is a Babcock & Wilcox plant, and it has the Emergency Feedwaters Initiation and Control (EFIC) system and has the capacity to feed and bleed through the safety valve and has PORV's.
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A committee member questioned as to whether feed and bleed can take place through the PORV's. The response was yes. The committee member
,1 i commented that the PORV's are questionable in view of the fact that they 1
have unqualified electrical apparatus.
Mr. Silver commented that the event he was going to discuss involved a partial failure of main feed flow, an auxiliary feed actuation, and a
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j reactor trip.
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SUMMARY
/ REACTOR OPERATIONS 6 January 7, 1986 Subcommittee Mtg.
He noted the significance of the event is that questions have been raised regarding procedures and training of operators, post trip review, operability of some auxiliary feed components, and unnecessary auxiliary feed challenges.
In this plant the feed control is on pump speed control down to about 50 percent power. Below 50 percent power the main feed line is locked closed and there are two bypasses around a block valve. One is a 10 inch valve and the other is a 6 inch bypass.
The normal procedure is to use the two bypass valves to bring the plant down to about 20 percent power, at which time the 10 inch bypass valve is secured and the plant is brought a full shutdown using the 6 inch valve.
During this event, the shutdown was proceding normally down to 20 percent power, when the operator remembered that the 6 inch valve had exhibited erratic control characteristics on a previous shutdown. He decided to switch back to the 10 irich control valve. l l
l The 10 inch control valve exhibited sluggish behavior and could not open fast enough to maintain level in the "A" steam generator. The EFIC system initiated auxiliary feed. The operators quickly secured the EFIC system because of fear of excessive cooldown.
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SUMMARY
/RFACTOR OPERATIONS 7 January 7, 1986 Subcommittee Mtg.
The operators observed the high pressure trip coming and attempted to open the PORV to avoid the trip. The PORV didn't open. The operators then closed the bicek valve.
w Following the event, the PORV was examined and a couple of contacts on the PORV were found to be burned out. .
In this event, it is believed that the auxiliary feed and EFIC system would have controlled this event automatically had the operators had not interfered.
H. Silver, Crystal River Mr. Silver very briefly noted an event at Crystal River which was an !
apparent separation of a reactor coolant pump impeller from a shaft and a resultaat trip on flux flow mismatch. The plant is now down and the pump is in the process of being removed and there is no indication yet as to the specific cause. .
V. Thomas, I&E, Reactor Trip Breakers Failure, D. C. Cook Plant, October 29, 1985 ,
On October 29t.h..one of the reactor trfp breakdrs on Unit 2 failed to automatically open upon the receipt of a scram trip signal. However, .
the scram function itself was accomplished because its redundant breaker
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. had opened.
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SUMMARY
/ REACTOR OPERATIONS 8 January 7, 1986 Subcommittee Mtg.
On November 3, 1985, while testing the remaining breaker in Unit 2, motor failure was experienced with one of the reactor trip breakers.
This was one of the breakers that had worked properly during the October 29th event.
In-plant testing showed the problems to be loss of force in Undervoltage TripAttachment(UVTA).
Bulletin 85-02 issued November 5, 1985 required special tests for currently operating plants without auto shunt trip. Two test failures were experienced at Kewaunee, others were successful.
Failure analysis testing started at Westinghouse which include visual inspections, force measurements, electrical tests and cyclic performance tests. The results not in yet.
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Fermi Unit 2, Emergency Diesel Generator Bearing Failures - M. Lynch, NRR Fermi has exhibited continuing diesel failures from January 1985 to December 1985 which cast doubt on the reliability of on-site power.
Failures include:
Diesel March 1985 November 1985 11 Bearing failure repaired Bearing failure, repaired 12 Bearing failure, repaired Bearing failure, repaired
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SUMMARY
/ REACTOR OPERATIONS 9 January 7, 1986 Subcommittee Mtg.
13 Inspection, accepted Bearing failure, repaired 14 Inspection, accepted Bearing failure, repaired
" Followup actions o Review teams currently investigating o Franklin Institute examining bearings o Apparent cause may be due to inadequate lubrication and method of " break in"
, o Licensee Test Program on EDG 13 scheduled o Repairs to be completed by the end of the year o 50.54(F) letter being issued requesting additional information M. Lynch, NRR, North Anna Unit 1, Emergency Diesel Generator Defective Parts, December 12, 1985 The problem encountered in this event is that the nuts that secure the bearing cap to connecting rod are not " square".
This has the potential of common mode failure of emergency diesel generators with generic application to Colt /Fairbanks Morse engines.
This case involved thread-pitch not perpendicular to nut focus inducing stresses beyond design limits and potential nut failure. This was discovered by a factory assembler on new engines. It is believed to be a bstch problem involving a sub-vendor.
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HINUTES/SU'MMARY / REACTOR OPERATIONS 10 January 7,1986 Subcommitte? Mtg.
A 10 CFR 21 letter was sent out concerning spare parts to Calve ~rt Cliffs, North Anna, Limerick and Fermi. Follow up actions include:
o Inspection of EDG "Id" at Worth Anna found defective nuts prior to refueling restart of plant o Affected licensees are being advised by vendor o IE/ Vendor Program Branch following up M. Lynch, NRR, Catawba Unit 2, TOI Emergency Dieset Generator Main Bearing Failures, November 20 and December 5, 1985 The unit was in preoperational testing. During October 1985, EDG 28 had an engine tear-down inspection. 6 out of 10 bearings were inspected, f7 was not inspected. On November 20th, bearing #7 failed after 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of operation. In postulated cause was an inadequately supported bearirg.
Following the failure, 7 out of 10 bearings were inspected. #1, 2 and 4 were not inspected. 5 out of 7 bearings were replaced although only lighth scored. On December 5 #7 bearing failed. The test was stopped after 4 minutes. The failure mode was similar for both incidents. The d
bearing had a crack at the minimum wall thickness.
Followup actions include:
o Detailed failure analysis and dimensional check is in progress o Licensee consulting with TDI o Cause of failure has not yet been identified o Possible delay in Catawba 2 fuel load date m v e
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. RINUTES/5UMMARY/ REACTOR OPERATIONS 11 January 7,1986 Sub:omitt02 Mtg3 o The Staff men.itoring licensees" effort J. Glit_er, .I.E. ; McGuf reAi_ts 1 and 2. - Oual Unit Trip on toss of InstrumentAirt.Jovember2,13 4
A section of bf.afdad flexible pipe *on the discharge 'of the "B" instru-meht air ecmpre.ssor rupturgd at a weided 'secm causing the instrument air system to depressurize. The air system. is commch to b6th units, Both units tripped from 100 perce0t pcw6r />n LO LO to $tesh generator level caused by closure cf the tain fee 6weter flow control v61ves on loss of air power. The auxiliary feed flow control valves go open c~ n loss of aif resulting in an exdesh AFW flow. The air was restored in about eight minutes.
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' Unit I depressuriied t9 the safety 1,njection initiation point. In-4 jetilon want on for about 10 titrutes. ,
l Ita Unit 2 operators recognited the Unit A problem und tripped two reactor cociant pumps to slow cooldown caused by pressurizer spray valve leskage. No safety injection occurred.
All other plant systems performed as expected for this transient.
The s3fety significance of this event Na,s that a non-safety grade system failure resulted in a challssnge to safety systans. Two units were affected by a siegie failure. 1 8
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SUMMARY
/ REACTOR OPERATIONS 12 January 7, 1986 Subcommittee Mtg.
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Followup actions included:
o The flexible pipe on the instrument air compressors was replaced o The use of the braided flexible pipe on the instrument air system will be reviewed to determine if other replacements or modifications are necessary to increase reliability o Check valves will be installed on the discharge of the three i
reciprocating instrument air compressors o Flexible pipe applications in other plant systems and at all Duke Power Nuclear Stations will be reviewed.
S. Long I.E, St. Lucie Unit 1, Upper Guide Structure (UGS) Lifting Rig Failure, November 6, 1985 While removing the UGS, 1 of 3 bolts connecting the UGS to the lifting rig failed with the UGS still over the core. The 50 ton load could have fallen back into the reactor vessel possibly damaging fuel and resulting in the release of radioactive gases to the containment. The lift was stopped when the rig was seen to tilt after it was raised 8 feet. The rig was canted about 6" up and the UGS was cant'ed about 6" down.
An attempt was made to lower the UGS to the installed position, but the load cells indicated binding. ;
1 The licensee declared an unusual event, enhanced containment integrity and implemented procedures to monitor load stability. A secondary
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SUMMARY
/ REACTOR OPERATIONS 13 January 7, 1986 Subcommittes Mtg.
lifting rig was designed, tested and installed. The assembly was jacked I
level and then moved to its normal parking position in the refueling pool.
An inspection revealed that the failed bolt was only inserted about i turn and stripped during the lift. Combustion engineering procedures for rig attachment had included verification of thread engagerient. This was omitted from the licensees latest procedure.
Followup actions include:
o Licens ee returned UGS to the installed position using long attachment bolts with heads that bear on rig surfaces above water level.
o Licensee is reviewing other lift procedures to ensure proper verification of bolt thread engagement o I&E is preparing an information notice M. Campagnone, NRR, Susquehanna Units 1 and 2, Loss of Till Transformer, December 2, 1985
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The Till transformer was tripped. The loads were automatically trans-ferred to the T211 transformer. The momentary interruption of AC power to the control and instrument panels causes the F.W. controllers to lock-up causing the three variable speed, 33 percent capacity FW pumps in each plant to fail "as is".
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SUMMARY
/ REACTOR OPERATIONS 14 January 7, 1986 Subcommittee Mtg. !
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On Unit 1, the operators failed to reset switches which would allow th'e i
manual control of the F.W. controller. This resulted in a steam-feed ,
mismatch which caused the reactor water level to increase to +54" tripping the unit on high reactor water levej. '
On Unit 2, the operators reset switches to gain manual control of the ,
feedwater controllers. The "A" FW pump coritrol logic had an error which upon resetting switches caused the "A" FW oump to wind down to zero flow. The operators tried to make up the ficw with the "B" and *C" F.W.
pumps but the level had already dropped to +13" causing a reactor scram or low reactor water level. The level decreased to -31.5". The RCIC auto initiated at -30". The 'MSIV's closed. HPCI was manually initi-ated.
The significance of this event was that a single loss of power caused a FW transient in both units and caused each unit to scram. ,
Follow up Actions Include:
I o The licensee das modified the load line up so that F.W.
control instrumentation will be powered from vital AC pcrer.
This provides on uninterrupted seurce of power.
o The licensee as been requested to identify other instrumenta-tion on I and C panels and to investigate similar scenarios.
R. Singh, I&E Indian Point Unit 2, Lose of Of fsite _ Power, _ December 12, ;
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SUMMARY
/ REACTOR OPERATIONS 15 January 7,1985 Subconoittes Mtg.
This event occurred while the unit was in hot shutdown following a reactor trip approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> earlier on a loss of flow signal.
During the process of relay checking someone bumped into a relay panel in the control room. Relay chatter caused both 6.9 KV breakers to open and loss of offsite power occurred. The emergency diesel generators started and picked up the loads. The reactor coolant pumps were lost and the plant entered natural circulation. Offsite power was restored in 20 minutes.
d R Singh, IAE, Waterford 3 Loss of Offsite Power, December 12, 1985 Unit 3 was in cold shutdown. Lightning struck the B Phase of the Waterford - Little Gypsy I line. The fault was cleared by normal relay action and breaker operation (bieakers 3212,3215,7102,and7106). At the same time, Unit 1 main transformer went off line due to a problem with the sudden pressure relay. About 30 seconds later, breakers 3212 ar.d 7102 automatically closed. A few minutes later the dispatcher tried to close breaker 7106 which faulted due to a failed breaking. ,
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The feult was cle6 red to normal relay action and breaker operation.
This fault resulted in the opening of the Waterford 3B line breakers due to phase comparison relaying.
1 30 seconds later, breaker 3212 automatically closed and faulted breaker i 7106. Steaker 7112 opened to clear the fault.
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SUMMARY
/ REACTOR OPERATIONS 16 January 7, 1986 Subcommittte Mtg.
This fault also caused opening of the Waterford 3A line breakers due to phase comparison relaying. Total loss of offsite power occurred.
A few minutes later the dispatcher closed breakers 7102 and 7112 which energized the 7106 faulted pushing.
Misoperation of relaying caused the Raceland line to the switchyard to be lost. The Raceland line was restored.
During the restoration breaker, 7112 was closed again which resulted in the loss of the 500 KV line to the switchyard for five minutes.
Following the loss of offsite power, both EDG's started and picked up the load.
Shutdown cooling was lost for five minutes.
Offsite power to the startup transformers was restored in about 40 minutes.
The feeder breakers to start-up transformers had opened due to phase comparison relays being set too low for plant conditions.
The relay settings were changed to correct the problem.
R. Singh, I&E, River Bend, Loss of Offsite Power, January 1,1986
.. MINUTES /SU$ MARY /REACTOROPERATIONS 17 January 7, 1986 Subcommittee Mtg.
l The reactor was in hot shutdown, when all offsite power was lost. All the emergency diesel generators started and picked up the load. The offsite power was restored after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 15 minutes.
An investigation revealed that the feeder breakers to both startup transformers opened as a result of a radio blitz. A security guard used his radio inside a building with a fiber optic tone system.
The tone system which is used for separating offsite power control cables picked up the blitz and caused the loss of one startup transformer.
I The feeder breakers can only be locally reset and were not reset.
The guard went to the same building again and this time the remaining startup transformer was lost.
G. Rivenbark, NRR, Hatch Unit 1, Flooding of Safety Related Areas, December 21, 1985 At the time of the event the unit was totally defueled. Maintenance was being performed on the isolation valve in the RHR torus suction line.
This single air-operated valve was relied upon for isolation of the torus. Electric power for actuating the solenoid was lost due to diesel testing. The isolation valve opened resulting in water flowing by gravity through the valve. The RHR room was flooded to 14 feet deep.
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SUMMARY
/ REACTOR OPERATIONS 18 January 7, 1986 Subcommittee Mtg.
Subsequent draining of the RDHR room resulted in water being introduced to other safety equipment room.
Follow up Actions Included o Region 2 sent a group to the site to review the operational, maintenance and equipment restoration aspects.
o The licensee is developing maintenance and test clearance procedures and related operator training.
o The licensee is evaluating each equipment item that was wetted for restoration or replacement.
The meeting was adjourned at 1:45 p.m.
NOTE: Additional meeting details can be obtained from a transcript of this meeting available in the NRC Public Document Room, 1717 H Street, NW., Washington, D. C., or can be purchased from ACE-Federal Reporters, 444 North Capitol Street, Washington, D. C. 10001, (202) 347-3700.
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]8 ,},y conm:ction of nu;!.*ar power plaats.
Safwerds; Subcommittee on Reac, tor
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dis;:a i!. 3.CRS preceJures and ,
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.[n' .Ir t ebI. n 5[a a prac' ices nd defMilion of a standard The ACRS Subcommittee on Reactor l
t N3 nf11 !icent:6 ind :r.dnt pl..n t. Operatio is will hold a meeting on
- e. sac anr?.' oT m .u; x: nl ccritols. *l. TV.-l Oryoni.c' ion and Janua y 7.1986. Room 1046.1717 H j
Scrcm Systems H2do:i*y. D te to be bloneseme et ofN::clearPower Street. NW. Washington. DC.
determinrel. Washmtc n. DC. The Activiths-The members will hear and The entire meeting will be open to Sub<:on:mii's wdl diece terar.i discuss a Wi;ng by reprewntative of' public attendance.
hres Lar r(i thil t,. fer 3.'.'! ..ni CE the NaC S vf regd.!rg chengesin The agenda for the subject meeting pbm an.! .atin e ti rs.: ve of Oe stru:!.re 23J ;:::ennel proposed to shall be as follows:
ATW'S Ra,.n impir n::r.L inn gifort. strenrlhe.: i VA rreclear activities.
R:::iabi .. and 'ec.:otr::st:c Tuesday, January 7.1986-9 00 a.m.
Ass.w+ :yDat on.llocat on to be *l. Semi:y of Nuclear Facilities-Th e g]ntil the Cone.lusion of Bustaess detenirt ! The S :k.ir tri;te null memNrs will hear and discuss reports review 'he probabihst.c mk asscosmer.1 b3 its ik..mmittee and by The Subcommittee will hear an I ' M #"' 1 representatises of the NRC Staff update on the new LER system and will Er.eq vry Cere Cec! vg Sntems. recriing proposed changes in the review recent operating experience.
D.; e . I;e determ;ned. u ashington. DC. iriangements for plant security at Oral statem=nts may be presented by
- n. c!aar power stations. members of the public with the e '
.. r so ti t ft 'K. Nuclear Reac!ctPressure Vessel contecence of the Sabcommittee h)dro'i;n.emic loads issue for D?.'R Thermo/ShocA-The members willhear Chairmaa. written statements will be contair n:i s. and discuss reports by an ACRS accepteil and made available to the ACRS Full Comm.ttee i Meet:.-ng consultant and an ACRS Fellow Committee. Recordings will be permitted regarding actions taken/being taken to only dt. ring those portions of the .
January 9-11.1986. Iterns are preclude pressurized thermal shock in meeting when a transcript is bemg kept.
tentet/t e/y scheduled. reactor pressure vessels. and questions may be asked only by
' A. Denis Besse Nuclear Cenerating members of the Subcomrmtree.its Representatives of the regulatory staff Srotiop-Bnefing re;nding plant restart consultants, and Staff. Perw.s desiring fulhm;t a lost of fe<:dwater incident. will participate as appropriate.
.I Use of the Chech0perator to me w! s'atements should nut;fy
- B Recent Ote:'m Gerts-Rcport the Ar> Mf m.A.r nm. I b:.la as -
of ACRS subecmm!:;ce and Concept in Requal.fication ofNuclear representatise of the NRC Staff PowerPlant Operators-The members far in .sance as in practical!e so tliat will hear a report and discuss the appropriate arrangements can be made. a regarding recent operating events and occurrences at nuclear power plant comments of an mvited expert regarding During the initial portion of the stations. applicat(on of the check. operator meeting. the Sulemmittee may
- C. Afeeling with Director. NRR- concept m requalification of nuclear . exchange preliminary veiws regarding Briefing regarding activities of the Office power plant operators. matters to be considered during the of Nuclear Reactor Regulation. *M. AnticipatedCommittee balance of the meeting.The
- D.NRC Outoge Inspecoon Subcommittee will then hear Activities-The members will discuss presentations by and hold discussions Progrom-Briefing by representatives of anticipated ACRS subcommittee the NRC Staff regarding the with representatives of the NRC Staff activities.
implementation of an NRC outa e and other interested persons regarding
, 8- - *N. Preparation ofA CRS Reports to this review.
- the NRC-The Committee will discuss clear eactor ressure s1 Further information regarding topice Integrity-The members will hear and proposed reports to the NRC reguding to be discussed, wnether the meetir.g discuss reports from its consultants and matters considered during this meeting.
in addition, proposed ACRS committees has been cancelled or rescheduled. the staff regardin transients and sam ing Chairman's ruling on requests for the
- .hniques re ted to the potential r on additional topics considered at '
opportunity to present oral statements seactor pressure vessel thermal shock. previous meetings including top,cs i such and the time allotted therefor can be F. Regulatory Research as the state of nuclear power plant obtained by a prepaid telephone call to Program-The mem ers will discuss safety, operation of the Palo Verde the cognizant ACRS staff member.Mr.
proposed ACRS comments regarding the Nuclear Power Station, and the Indian Herman Alderman (telephone 202/634-proposed NRC Safety Research Program Point Nuclear Station probability of core 1414) between 8:15 a.m. and 5:00 p.m.
and Budget for FY 1987 melt will be discussed. Persons planning to attend this meeting
- *C. Quontitative Safety Goofs February 13-15.1986-Agenda to be are urged to contact the above named (lentatireJ-The members will hear and announced. Individual one or two days before the discuss the report ofits subcommittee March 13-15.1986-Agenda to be scheduled meeting to be advised of any regarding the evaluation of proposed announced.
NRC safety goals. changes in schedule, etc., which may have occurred.
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l ndzral Reclsl;r / Vd. 50. N2. 241/ Monday. D;cember 16, 1985 / NItic:s J 51315 dad. Deurnber to.1985. Dollars ($25,000) within thirty days of Morion W. tJLarkin, containment Ice cohde'nser system.He -
the date of this Order, by check, draft, or Commission issued a Notice of *
A ssis tant En ecutire Directorfor Project money order payable to the Treasurer Review. Consideration ofIssuance of the ....
of the United States and mailed to the Amendments in the Federal Register en .
[FR Dx. a~s-341 Filed 12-13-85. 8 45 am] Direetor. Office ofInspection and August 5,1985 (50 FR 31661). By lettae ;
artuus coos ruoei-as Enforcement. USNRC. Washington. DC dated October 31,1985, the licensee '
20555. requested, pursuant to 10 Cm 2.107 ne licensee may, within thirty days i
(Docket No. 50-454.Ucense No. NPF-37 permission to withdraw its application EA 85-521 -
of the date of this Order, request a fer the proposed amendments.ne basta hearing. A request for a hearing shall be - for withdrawal of the amendment ,
- Commonwealth Edison Co.:(Byron addressed tp the Director. Office of request was that the licensee
lant. Unit 1); Order imposing Civil Inspection and Enforcement, USNRC.
determined that an error existed in the one ary Penalty Washington. DC 20555. A copy of the input assumptions to the computer* code, hearing request shall also be sent to the used to provide the technical i Executive ! egal Director. USNRC.
justification for the proposed Commonwealth Edison Company (the Washinkton, DC 20555 and to the amendments.%e Commission haa
,, licensee )is the holder of Operating Regiona Administrator. Region 111,799 considered'the IIcensee's October 31 License No. NPF-37 (the license ,) Roosevelt Road. Clen Ellyn. Illinois 1985, request and has determined that 60137. lf a hearing is requested. the permission to withdraw the April 5.
m .i i n (t e Co r fsfon ne mrniss n H issue an Order 1985, apphcaHon for amendmuts M license authorizes the licensee to designating the time and place of be granted. -
operate the E3 ron Plant. Unit 1. In hearing. lf the licensee falls to request a ,
anng within thirty days of the date of For further details with respect to,thld accordance with the conditions action, see (1) the application for specified therein. The license was issued this Order, the, provisions of this Order amendments dated April 5.1985 (2)the on October 31.1984. shah be effective without further proceedings and. If payrnent has not licensce's letter dated October 31.1985.
Il been made by that time, the matter may withdrawing the application for A specialinspection of the licensee's be referred to the Attorney Cencralfor ament' nents. (3) McGuire Licensee COU'CN O"*
Event Report (LER) 85-29. dated October actisities was conducted on March 11. 31.1985, and (4) our letter dated 1pn T!.i rn .its c ! - r r tien in the n ent Qq licenree requesis a Decm' 10.19".5. A!! of the above ind entud that tb 6 .a "I.E r. ct m c7 pr.urd r. bate, t're fesue; m dered at such heari g shall be; dc s .cnt: cr* a.s2.l'e for public conducted its act"..% in fell inspition at the Commb stor/s Public complian:e with Cor.-65:cn requisements. A wr;::cn Nctice of be .(a)Mcons lhether :r.e license viciation f ne Cc.mmission s Documtnt e 3 as Roum. in7 H inStreet. NW..
Washington, DC. and at the Atkins Violation and Proposed I'rposition of ngpen.ents as set forth in the Notice Library. University of North Carolina.
Civil Penalty was sen cd upon the f \iolation end Proposed Imposition of Charlottee (UNCC Station), North licensec by }ct:ct dated Jene 6.1W5 The Civu Penahy rcfmnced in SecHon U Carolina 28223.
Notice ip.tes the netare cf the violatien, abo e and the ep; .; cme p evisions of the g g, = , Order should be of December 1935. ;
i .t .
e nt of c .i! penalty 8 N(L For the Nuclear Regulatory Commlasion.
pit. "i! f:r the sichfien:.The lice .sce D.o J c. 15da l.far) land, this 9th day B ] Youngblood. .'
te , n;:i.. J to ths ::ofin :.! Vih don n:zd D C' d ' Ab- D;recrur. PtVR Troject Directorare No. 4.
3*; ops,tJ Snper.it:en of C. il Ptnalty I' ' O de.kar Re;ulatory Conunission. Djiisjon ofplyn Licensing-A.
wit'. L !< er da td bly 12 191;5. IN', f.t.1 o> tor.
[FR Doc. 85-29:38 Filed 12-13-85; 8 45 mm) m .Tre. m . OT &l. specN n and E-'. w:e nen:.
owns ecog yn>as es Up.m c. m!&: .: or. ' de 1: nsec'.
irR Dec cv w.ri!ed 1M3-es. e 45 am) rc%:.se A .d Se : .it :7.t r.4 :i f act. rs.ti s cc .1 resses.u
' nri..r.stien. a ...' g e aat. fm ._
(Docket No. 50-3211 n.it:;.. tion c rt;.:: fri J :;. :P Of Dir. ver. O.*f ce r i::. . .c.fi'n .:'d o acWo- m aN S370 Environments! Ascecsment cnd Final Dfcrt.cmt nt. he r Jcte air d 4:. set Finding of No Significant impact re Nuefcar Regarding Proposed Amendment to
'c:ta in, the At pcr;% in :)'s Ordn dat c.h g.7;;;n, hva pn3 r Co.;3 gMcCu.,.
p; lithe'rev.at ofFacility Operating Ucense; Georg!a
- hr : .. .t.r i c,et.16,r . e t :' sn.' d .: A ppSc;t!:c. for / nendments to Power Co. Et al.
. .h. ; , s. p m.... e < : t1 - . A tmn 8 e.e ';'y " 377.;".) Liecnses
- a: -tcd ir d.c .*:."rc of / cla:ien The U.S. Nuclet.r Regulatory i :rc. ': . ed i , c ::is r f Cml
' The Un:td steter. Nuclear Regulatory Commission (the Commission)is P.:n. .
. ld b.:1 px ed.
Cstr :.iscien !!! r Ccmm!:sion) has considering the issuance of an
prted it r. ". cst of Dake Power amendment to Pacilit) Operating
('ctr en:. ('Mirenste) to withdraw its License No. DPP.-57 issued to Georgia Ir. .- ie r .
- th * .rv '..;. c. 3 pa. -
Apr.) 5 W app!icatis , of the. :.f;Cuire Pcv.er Corr.rany. Ogfr thorpe Power u er .. A o' O.e /.teaic Encr;-!.:t Nurh <: W.:sr. Ur.fis 1 end 2, located d ,m e :. ..t r diJ. .a U.: C. :::d. F b. Cc:poration. f.funicipal Electric In ? : 1.14e 1.2 Cour.ty. North Care!ina. Authcrity of Georgia, and the City of L r:-2! . ; nd n' Cl R : 'W. .: ir ha'.y Thr r rp i amend ner.ts would have Dr.iton Ccorgia. (the licensees) for )
'4*':s d d .t d.:.nt;-d T :hnical Specification 3.6.5.1 cperction of the Edwin 1. Hatch Nuclear s
t c ; : eie * -
- i.s 'r. :' ~ to r": c;2rction seith a reduced Plant. Unit No.1 (the facility) leca ted in l
.. .ce:,.Tr. Tl v .nd :n!-
.r- . :;ht of:ce in the Ap;lir.g County Georgia.
l .
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o- -
. .m . . _ . _ . _
<W*7~d j
. TENTATIVE SCHEDULE REVISION 2 - 1/03/86 ACRS SUBCOMMITTEE MEETING ON
- i REACTOR OPERATIONS, JANUARY 7, 1986 i
ROOM 1046, WASHINGTON, D. C. '
8:30 a.m. Introductory Remarks - Subconnittee Chairman RECENT SIGNJFICANT EVENTS Presenter /
Office Date Plant .. Event Telephone 8:35 a.m. TE/2 Rancho Seco* Reactor Trip & Excessive 5. Miner, NRR ,
10/7 (ACRS Request) (Update); AFW Pump Bearing 492-8352 !
Failure !
9:00 a.m.10/29 D.C. Cook 2 Reactor Trip Breaker J.T. Beard, NRR l
9:15 a.m.11/13 Fermi 2 Recent Emergency Diesel J.T. Beard, NRR 11/12 North Anna 1 Generator Failure Events 492-7465 12/5 Catawba 2 10:00 a.m. ****** ******
BREAK 10:15 a.m.11/2 McGuirE 1&2 Dual Unit Trip on Loss of G. Lanik. IE Instrument Air 492-4196 10:30 a.m.11/2 Peach Botton 3 Residual Heat Removal Pump J. Zudans IE Rings & Motor Bearing 492-7205 Failures 10:45 a.m.11/6 St. Lucie 1 Vessel Internals Lifting S. Long. IE ,
Rig Failure 492-7159 '
11:00 a.m.11/22 Crystal River MFW Failure /AFW Actuation H. Silver, NRR 3 Reactor Trip 492-7900 11:15 a.m.12/2 Susquehanna Partial Loss of Offsite M.J.Campagnone 1&2 Power: Control Systems 492-8474 Malfunction, Dual Unit Trip 11:30 a.m. ****** BREAK ******
11:45 p.m.12/12 Indian Point Recent Loss of Offsite R. Singh, IE 2 Power (492-8985 Waterford 3 and others i
12:15 p.m. Discussion of Other Events l 1:00 p.m. Subcommittee Discussion l l
1:45 p.m. ADJOURN 1
~
ACR5 5USCOM.MITTEE MEETING ON . REACTOR OPERATIONS. _ _
N.' ALDERMAN
". LO.LAT,ID:1: Room 1046,1717 H St. NW., Washington, D. C.
DATE: January 7,1986
'. ATTENDANCE LIST PLEASE PRINT:
NAME BADGE NO. AFFILIATION -
lH [i,t..~. r:. - i o o 4eo Ft.d .
P K 6.cm; F ._ 1 6 L p (2 c_.
T 1 r t e r i e t c._ tr- cA 72 rd u G -
R. T. $bs E - 09ES FPL
%K.A$1%s E-0930 F*iPL--
lA.b'lL4/2/) foff? it~/t.'
51)e / A/vit n1 i E'093 ) $A 1 CL.-
Y.!.w % -u c'oiuc, mtc >
'(k(%c)>..A ~.v:.::, , 751 W ;
1 E f~ 6 cum G.-cris9 L P4 L. '
PP ^/c./fr c' 09(5 L f L -.
V'vJs (b E. - 0 /4 9 LPYL-M c C ir ies.Lrs socioi bsA f))b c' Vn c. !~ ;?
- ) H ; '
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h . ,l.' G., k d.31#/6 V (22
%vru c.o<n $ .3 T- (, tL' J
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1
AC Rh SUbLtr*.Ma l i tt Mt E.1 I nu Vi1 ELAllOR OPERATIOfiS .
H. ALDERMAN
. LOCAT.10:1: Room 1046,1717 H St. NW., Washington, D. C.
.' DATE. January 7,1986
- ATTENDANCE LIST PLEASE PRINT:
NAME BADGE ii0. AFFILIATION -
& . E. /20 tse' ZE TF
- 5. L e., ->
/U/ ? c.- u :: c c i c t Jr
,b o M D .S $$
V. w 'iS , c, m,n I t= % cu E
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'=. ,', : -: : . . ..
E c Gm, en >c ac < nn
matvs reptd;ng q.mlity centrol and
&!St. Nin. .D.'e :c L de:rmin2d qud'. m rc.g ? in the design and (Febmr> /'.!crch). ren Lor.;r. ion:. CO.
dviscry Committee on Reactor concruction of nu:; lear power plants. Sarc guards; Subcommittee on Reactor xpb c . . Ie '
- radixctn a waste mar,agement and Oper:tions: Meating daring t.aa vcent exteac. : d ou%;e. and dispml. ACRS procedures and ciscuss m r.agemer t ch angar, made as a p ' ices, and defmilion of a standard The ACRS Subcommittee on Reactor result of the !icenr2 is indeNndent E n!- Operations will hold a meeting on i nssessrner.t of moaa;cm"nt controls. l;I. TVA Otyani/ofion and January 7.1986. Room 10LI6.171711 Scram Systems Reliabili!y, Date to be MancSemert ofNuclearPower Sl('el' NW, Wa shington, DC.
- determined. Washmson. DC. The Acritilles-The members will hear and The entire meeting will be open to Subcommit'2e will disem scrara discuss a hriefing by representative of public attendance.
break 2r r@bility for DNW nd CE the N9C S Pf regeding changes in The agenda for the sub[ect meeting plano and untinue its rsCew of'he strut! re and ;,;r:onnel proposed to shall be as follows:
ATWS R ip implementation effort. strengthen TVA nuclear activities.
Reliabn.y and.robabu:stic Tuesday, January 7,198b9:00 a.m.
Ass-sure.Y Date and lucation to be *1. Security of Nuclear Facilities-Th e Until the Conclusion of Business memNrs will hear and discuss reports determired The Sabcar mi: tee will review the probabi!ist;c nsk assessment by its subcommittee and by The Subcommittee will hear an
. r W;ne 3. representatives of the NRC Staff update on the new LER systern and will Ere;"ncy Core Cooling Sprems. regaHing proposed changes in the review recent operating experience.
Datn ~ be determmed. Washmgton. DC. arrangements for plant security at Oral statements may be presented by
'l he S ibcommittes will contmue its nuclear power stations. members of the public with the review of resolution of the *K. Nuclear Reactor Pressure Vessel concurrence of the Subcommittee hy drodmamic loads issue for BWR Thermo/ShocA-The members will hear Chairman, wntten statements will be contair nents. and discuss reports by an ACRS accepted and made available to the consultant and an ACRS Fellow Committee. Recordings will be permitted ACRS Full Committee Meeting regarding actions taken/being taken to only during those portions of the January 9-11.1986: Items are preclude pressurized thermal shock in meeting when a transcript is being kept.
tentatively scheduled. reactor pressure vessels. and questions may be asked only by
- A. Doris.Besse Nuclear Generatird Representatives of the regulatory staff members of the Subcommittee,its Statiop-Briefing regarding plant restart consultants. and Staff. persons desinng following a lost of feedwater incident. will participate as appropriate.
to mab c o! statements should nutify
- B. Recent Owi.+; Erents-Report .I" Use of the heypemtor the ACM ataff memher named below us of ACRS subcoInmit:ee and Concepun Requalification ofNuclear Power Plant Operators-The membera far in adsance as is practicable so that representative of the NRC Staff will hear a report and discuss the appropriate arrangements can be made.
- regarding recent operating events and cccurrences at nuclear power plant comments of an mvited expert regarding During the initial portion of the strtions. applicat,on i of the check. operator meeting, the Subcommittee may
- C. Meeting with Director. NRR- concept m, requalification of nuclear exchange preliminary veiws regarding Briefing regardin8 activities of the Office power plant operators. matters to be considered during the cf Nuclear Reactor Regulation. *M. AnticipatedCommittee balance of the meeting.The
- D. NRC Outage Inspection Subcommittee will then hear Activities-The members will discuss presentations by and hold discussions Progmm-Briefing by representatives of anticipated ACRS subcommittee the NRC Staff regarding the with representatives of the NRC Staff activities.
implementation of an NRC outage and other interested persons regarding
, .N. Preparotion ofACRS Reports to this review.
ins,pection program for nuclear facilities- the NRC-The Committee will discuss Furtherinformation regarding topics Integr e me er wift earan proposed reports to the NRC regardin8 to be discussed whether the meeting discuss reports from its consultants and matters considered during this meeting.
, has been cancelled or rescheduled, the In addition, proposed ACRS committees l stiff regarding transients and sampling , Chairman's ruling on requests for the tichniques related to the potential for n additional topics considered at -
opportunity to present oral statements I reictor pressure vessel thermal shock. previous meetings including topics such and the time allotted therefor can be F. Regulatory Safety Reseamh as the state of nuclear power plant obtained by a prepaid telephone call to '
i Program-The members will discuss safety, operation of the Palo Verde the cognizant ACRS staff member,Mr.
proposed ACRS comments regarding the Nuclear power Station, and the Indian Herman Alderman (telephone 202/6W przposed NRC Safety Research Program point Nuclear Station probability of core 1414) between 8:15 a.m. and 5:00 p.m.
cnd Budget for FY 1987. melt will be discussed. Persons planning to attend this meeting
'G. Quantitative Safety Cools February 13-15,1986--Agenda to be are urged to contact the above named (tentativeh--The members will hear and announced. Individual one or two days before the discuss the report ofits subcommittee March 13-15,1986-Agenda to be scheduled meeting to be advised of any regarding the evaluation of proposed announced, NRC safety goals. changes in schedule, etc., which may have occurred.
l
- i. t r
F;d:r:1 R: gist;r / V:1. 50, N . 241 [ Mond;y, D:ctmb1r to,1985 / Notices -
51315 D5ted:December 10,1985. Dollars ($25,000) within thirty days of Morton W. Ubarkin, -
containment Ice cohde'nser system.%e -
the date of this Order, by check, draft, or Commission issued a Notice of
- Assistont Erecutire Directorfor Project money order, payable to the Treasurer Consideration ofIssuance of the .,.
Review. . ..
of the United States and mailed to the Amendments in the Federal Register on (FR Doc. 85-29741 Filed 12-13-85: 8.45 sm] Director Office ofInspection and August 5,1985 (50 FR 31601). By letter ;
artuno coot rsoo.es-as Enforcement, USNRC, Washington, DC dated October 31,1985, the licensee 20555. requested, pursuant to 10 CFR 2.107
[ Docket No. 50-454, Ucense No. NPF-37 He licensee may, within thirty days permission to withdraw its application of the date of this Order, request a for the proposed amendments.ne basis .
EA 85-52) .
hearing. A request for a hearing shall be
- addressed to the Director, Office of for withdrawal of the amendment" .
Commonwealth Edison Co.:(Byron request was that the licensee Plant, Unit 1); Order imposing Civil Inspection and Enforcement, USNRC, determined that an error existed in the Monetary Penalty Washington, DC 20555. A copy of the inpt'itassumptions to the computer code' hearing request shall also be sent to the used to provide the technical i Executive Legal Director, USNRC, justification for the proposed Washington, DC 20555 and to the amendments. ne Commission has
,h, Commonwealth Edison Company (the Regional Administrator, Region 111,799 considered'the licensee's October 31, censee,)is the holder of Operating Roosevelt Road. Glen Ellyn. Illinois 1935, request and has determined that License No.NPF-37(the license ] 60137. lf a hearing is requested, the th permission to withdraw the April 5.
- n *
[
license authorizes the licensee to ion,b Commission willissue an Order designating the time and place of 1985, application for amendments should be granted. . ,,-
operate the Byron Plant. Unit 1. In ""U"8 .the licensee fails to request a For further details with respect to,this accordance with the conditions heanng within thirty days of the date of action. see (1) the application for specified therein. The license was issued this Order, the provisions of this Order amendm on October 31,1984. shall be effective without further licensee.ents datedOctober s letter dated April 5,1985,(2) 31.1985, the proceedings and,if payment has not 11 withdrawing the application for been made by that time, the matter may amend nents,(3) McGuire Licensee A specialinspection of the hcensee's be refe,rred to the Attorney General for Event Report (LER) 85-29, dated October
.* collection.
activities was conducted on March 11, 31,1985, and (4) our letter dated 1985. The results of ni:: inspection I" the event the licensee requests a Dectrcht 10,1955. All of the above indicated that the linnsee had not hean.r;; as prc.med above, tne ttsucs to be considered at such hearing shall be:
dor.ce nt: cre as siM 5 for public conducted its activities in full inspection at the Commissiorls Public compliance with Commission .(a) Whether the licensee was in Document Room.1717 H Street, NW.,
requirements. A written Notice of n lation of tne Commission s Washington.DC, and at the Atkins Violation and Proposed Imposition of requirements as set forth in the Notice i Vi lation and Proposed Imposition of Library. University of North Carolina, Civil Penalty was served upon the Charlottee (UNCC Station), North licensee by letter dated June 0,1985. The Civil Penalty referenced in Section II Carolina 28223.
Notice otates the nature of the violation, abo e, a t e epr.ljceble provisions of the g,,,,,n ,:.is Order should be '
of December 1985. -
.a d be 8U5tained-o nt of c il penalty For the Nuclear Regulatory Commission. -
prce d for the vio!ctions. The licensee Dr.ted a: bthrsda. Maryland, this 9th day B1 Youngblood, e rt.,omk.1 to the Notice of Violation and c nenn! n ms.
Director, Pim Project Directorote No. 4.
PropJ5cd Imposition of Ci"il Penalty Fcr the No tear Replatory CommissiorL pirision ofpim Licensing-A.
Wilh 6 It 'ter dated July 18 1985. Imes M. Taylor.
[FR Doc. 85-29:38 Filed 12-13-85: 8.45 am]
gg Direcor. Ol fire c!?rspectica and e, tuna cong ps,wa,.m E=fmement.
Upon censider.:t'on of theli: nsee's (FR Dac. 85-nry, Filed 12-13-85,8.45 am]
resp nse And the L.tcmonis of fact. c;.tma cons ns>esu expi.-natten, and ary:AnL for - ! Docket No.50-321]
raiti;; .ticn contair.ed tha e:n. the Dirs ctor, Office of r.r.;ection cnd 10 ct:c* N :. D-009 and 50-370] Environmental Assecsment end Final Enfcreement, har dete mird as set Finding of No Significant impact fo:th in the Apper dix to this Order that Duke Four Co.; McGuire Nuclear llegarding Proposed Amendment to Station, Units 1 and 2; Withdrawal of Faci!ity Operating License; GeorE,la -
- 'he; w tlc no!atin ocemcd h.* pro,m: ed ,c rc:th-rtate:' an/ tint f,pp ;c;;;;,r. for A nendments to
'claletion Power Co. et al FacCl;y"""2trti.o Liecnses i '
- c:tsi: .4tc.d in the Noccc of V.clation %c U.S. Nuclear Regulatory j er.c i r~ ad Jr., cGir cf Cisil
~ The Un: led states Nuclear Regulatory Cornmission (the Commission)is Pen: 'y shrld be !. p2:ed. Com :.issien (the Comrr.ission) has considering the issuance of an
,y
- g: nted ic recucst cf Dake Power amendment to Facility Operating Connny (t:u licenste) to withdraw its License No. DPR-57 issued to Georgia In viev. ef the .1,rcio .g. cr 3 purur. April 5. E application cithe McGuire Pcwer Company. Oglethorpe Power to sede. 34 of the Ato:aic Energy /.ct Nuclur 5-1 :;:on. Units 1 and 2, located Corporation. Municipal Electric '
of 1054. s.: eraerded. 42 U.e C. 2K. P b. in W ckLn '.<2:g County North Carolina. Authority of Georgia, and the City of
, L n-203. end 10 CFR r N5, .:is hort! y The rrr o . d amend nents would have Dalton. Georgia. (the licensees) for ordt a d that: chan; .d T, :hnical Specification 3.6.5.1 operction of the Edwin 1. Hatch Nuclear
" s lia <ee rar e civi! m by in il a to r!!m cparction with a reduced Plant, Unit No.1 (the facility) located in
. w iTmMy Du il s- .nd mini;.:=
- ight ofice in the Appling County, Georgia.
t _
W Wb TENTATIVE SCHEDULE REVISION 2 - 1/03/86 ACRS SUBCOMMITTEE MEETING ON REACTOR OPERATIONS, JANUARY 7, 1986 ROOM 1046, WASHINGTON, D. C.
8:30 a.m. Introductory Remarks - Subcommittee Chairman RECENT SIGNIFICANT EVENTS Presenter /
Office Date Plant Event Telephone 8:35a.m.TD77 Rancho Seco' Reactor Trip & Excessive 5. Miner, NRR 10/7 (ACRS Request) (Update); AFW Pump Bearing 492-8352 Failure 9:00 a.m.10/29 D.C. Cook 2 Reactor Trip Breaker J.T. Beard, NRR 9:15 a.m.11/13 Fermi 2 Recent Emergency Diesel J.T. Beard, NRR 11/12 North Anna 1 Generator Failure Events 492-7465 12/5 Catawba 2 10:00 a.m. ****** BREAK ******
10:15 a.m.11/2 McGuire 182 Dual Unit Trip on Loss of G. Lanik IE l Instrument Air 492-4196 10:30 a.m.11/2 Peach Botton 3 Residual Heat Removal Pump J. Zudans, IE Rings & Motor Bearing 492-7205 Failures 10:45 a.m.11/6 St. Lucie 1 Vessel Internals Lifting S. Long, IE Rig Failure 492-7159 11:00 a.m.11/22 Crystal River MFW Failure /AFW Actuation H. Silver, NRR 3 Reactor Trip 492-7900 11:15 a.m.12/2 Susquehanna Partial Loss of Offsite M.J. Campagnone 1&2 Power: Control Systems 492-8474 Malfunction, Dual Unit Trip 11:30 a.m. ****** BREAK ******
11:45 p.m.12/12 Indian Point Recent Loss of Offsite R. Singh, IE 2 Power (492-8985 Waterford 3 and others 12:15 p.m. Discussion of Other Events 1:00 p.m. Subcommittee Discussion 1:45 p.m. ADJ0 URN
, ,..,.._m.: , , . - , , _. , - -
ACRS SUBCOMMZTTEE MEETING ON REACTOR OPERATIONS H. ALDERMAN Room 1046,1717 H St. NW., Washington, D. C.
{ LOCATIO:1:
DATE:
January 7,1986 ATTENDANCE LIST l
PLEASE PRINT: ,
NAME BADGE N0. AFFILIATION .
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ACRS SUBCOMMITTEE MEETING ON _ REACTOR OPERATIQNS_ H. ALDERMAN '
l 1
L0 CAT,10:l: Room 1046,1717 H St. NW., Washington. D. C.
DATE: January 7,1986 ,
ATTENDANCE LIST PLEASE PRINT:
NAME BADGE NO. AFFILIATION -
sea omss ze
&. E /20cse' ZE TE 5 . L c-, -,
,4 h/ 9xu:gict 15 l . $ fb O Ms .s SS V. t v L ,c , ,= a n Ie 'T?scucu r sjI , [ . YT , ., f'.;
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s ATTACHMENT D HANDOUTS AT THE REACTOR OPERATIONS MEETING JANUARY 7, 1986
- 1. NRC Staff presentation to the ACRS.
- 2. Millstone Units 1 and 2, Loss of Offsiite Power as a Result of Hurricane Gloria.
- 3. Procedure for Augmented Investigation Team (AIT) Response to Operational Events.
- 4. Special Safety Inspection - Donald C. Cook Nuclear Power Plant.
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