ML20141E950
| ML20141E950 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Dresden, Nine Mile Point, Catawba, Brunswick, North Anna, Turkey Point, River Bend, Cook, Maine Yankee, Rancho Seco, 05000000 |
| Issue date: | 11/18/1985 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2370, NUDOCS 8601080437 | |
| Download: ML20141E950 (11) | |
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W ISSUED:
NOV. 18, 1985 COMBINED
SUMMARY
/ MINUTES OF THE NOVEMBER 4, 1985 MEETING 0F THE ACRS SUBCOMMITTEE ON REACTPR OPERATIONS WASHINGTON, D.C.
The ACRS Subcommittee on Reactor Operations met on November 4,1985 in Room 1046 at 1717 H Street, N.W., Washington, D.C.
The purpose of this meeting was to discuss recent plant operating experience.
The Offices of Inspection and Enforcement and Nuclear Reactor Regulation, as well as the Subcommittee, identified a number of current operational events for discussion.
Following the Subcommittee's review of these events a limited number were selected for presentation to the full ACRS during the November 1985 full Committee meeting (November 7-9,1985). Notice of the meeting was published in the Federal Register on Tuesday, October 22, 1985 (Attachment A). A copy of the schedule of discussion is Attachment B.
A copy of the slides used during the meeting is kept with the office copy of these minutes.
The entire meeting was open to public attendance.
No written or oral statements were received from members of the public.
Richard Major was the assigned staff engineer. The meeting began at 1:00 p.m.
Attendees ACRS NRC Staff J. Ebersole, Chairman E. Rossi C. Michelson, Member E. Weiss C. Wylie, Member D. Powell P. Balmain R. Major, Staff D. Mcdonald R. Hernan G. Polahan S. Minor Others J. Trotter, NUS Corp.
J. Slider, self J. Herring, Bechtel L. Conner, DSA C. Wethy, Fla. Power and Light Co. (FPL)
D. Chaney, FPL D. Hoffman, Ace-Federal t
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REACT 0P OPERATIONS 2
November 4, 1985 E. Nichols, U.C. Berkeley J. Nurmi, QATEL H. Fontetilla, Va. Power K. Khianey, Bechtel J. Kerdiles, Framatome Failure of Magnesium Rotor on Limitorque Valve Operators During EQ Testing - J. Stewart, IE This was not an operating event, but a failure that was discovered during environmental qualification testing. GE was running tests at Wylie Labs, for River Bend and Nine Mile Point 2.
Motor (Reliance-manufacturer) failures were discovered at 7,15 and 43 days into the 100-day LOCA test. Magnesium rotor corrosion due to the steam L
environment caused the motor failure.
Similar motors had previously passed LOCA testing at lower temperatures. GE has issued a service information letter recommending BWR plant review and possible mitigating actions (such as placing these valves in a safe condition following a LOCA but prior to magnesium rotor failure). An IE information notice is being prepared.
Catawba Unit 1 - Partial Loss of AC Power During Diesel Generator Operability Test, August 15, 1985 - D. Powell, IE Unit I was operating at 95% power.
Unit 2 was in preoperational test-ing. The Unit 1 operator made a switching error while attempting to parallel a diesel to a bus. The electrical load was shed from the bus and the automatic response to a blackout signal began. Containment pressure increased because of the loss of power which caused containment chillers to trip. The Unit 2 NCO helped the Unit 1 NCOs by depressuriz-ing the Unit I containment. While the Unit 2 NC0 was away from the Unit 2 panels, the Unit 2 volume control tank (VCT) filled to 100% and ap-proximately 80 psig.
It appears Unit I was supplying power to the Unit-2 panel board that controls the VCT outlet valve. The outlet valve shut on loss of power, but VCT letdown was not isolated. A three-way divert valve control switch was in the VCT position.
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j REACTOR OPERATIONS 3
November 4, 1985 Follow-up actions include reminding operators of Duke's shift manning policy.
It is to obtain the shift supervisor's approval before leaving i
your unit to help the other units' operators.
(The control rooms are combined and the operator was licensed on both units.) The plant's electrical interactions are being reviewed by the licensee.
i Maine Yankee - Rosemont Transmitter Improper Installation, October 10,
~1985 - P. M. Sears, NRR The plant was in a refueling outage.
It was discovered that pressurizer pressure, pressurizer level, and steam generator level transmitters had not been installed in complete agreement with the EQ test configuration.
Errors included covers not being tightened as tightly as the test configuration and the absence of drain holes in the bottom of junction boxes. The installation was complete'd in 1982 and the tests were completed later. A steam leak could have compromised the above systems.
i At Maine Yankee a check has been made for similar problems with other qualified equipment; none has been found.
Earlier this' year it was l
found that steam generator pressure instrumentation was compromised.
These two events, taken together, are being considered by NRR as candidates for an abnormal coreurrence.
j Dresden 3 - Scram Solenoid Froblem Induced RCS Leakage, September 19, 1985 - Eric Weiss, IE~
The plant was operating at 80% power. A turbine control valve fast closure was caused by an instrumers technician error. A pressure spike caused a scram.
The o'erators attempt to reset the scram but only p
channel A reset [ resetting channel A causes scram discharge volume (SDV) vent and drain valves to open]. Leaking solenoid valves cause low air t
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pressure resulting in partially open scram outlet valve and SDV vent and j
drain valves. Steam escaped into the reactor building and radiation i
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REACTOR OPERATIONS 4
November 4, 1985 alarms were activated. Operators manually closed SDV vent and drain valves.- Three individuals were contaminated during the event. The leak lasted for 23 minutes.
North Anna Emergency Diesel Generators (EDG) - Leon Engle, NRR The emergency diesel generators at North Anna were manufactured by Fairbanks Morse, Inc.
Fast starts and fast loads during tech, spec, testing have been reduced. This tech, spec. relief was given when Va.
Power committed to continue an enhanced-EDG maintenance program and to continue looking for root causes of diesel failures. The enhanced maintenance program includes:
the routine analysis of engine lube oil; establishing the trending of critical engine operating parameters; improved maintenance practices with recommendations from diesel consultants and the vendor; increased inspection of engine components; increased hands-on training for mechanics, foreman, and maintenance engineers at vendor's facilities; and planned diesel overhauls during refueling outages.
1 Recently several failures occurred at the North Anna diesels.
Apparently, wrist pin bushings failed by extrusion. The extruded bushings resulted in bushing contact with piston internal bosses.
Contact with piston bosses deform the piston (ovality). Deformation of the piston results in contact with the cylinder liner and localized overheating. The result is then temperature-induced fatigue failure of piston, cylinder, or both.
It is now believed excessive mechanical force on the wrist pin bushings
-begins the failure. The cause is excessive firing pressure which can result from fast start, fast loads, and--the most recent postulation--
unequal cylinder firing pressures due to timing misadjustment.
REACTOR OPERATIONS 5
November 4, 1985 il Rancho Seco Event Follow-Up - H. Baily, IE 1.
Reactor Trip and Excessive Cooldown October 2, 1985 The Rancho Seco cooldown event is significant because it is an apparent violation of cooldown. technical specifications, represents multiple equipment failures, and questions the adequacy of plant maintenance.
The incident began with the plant at 15% of full power conducting a turbine overspeed test.
Due to low condenser vacuum, the steam bypass valves trip and feedwater heater relief valves lift. The A main feedwater pump trips. Both auxiliary feedwater pumps start on low main feedwater discharge pressure. The reactor tripped on high pressure; the 8 main feedwater pump also tripped. During the cooldown transient pressurizer level dropped.
High pressure injection started and supplied water to the primary system. Pressurizer level was restored and high pressure injection was secured. The reactor cooling system overcooling was stopped. The reactor cooling system cooldown was between 100*-110 F in twenty minutes. Tech. Specs allow a limit of 100 F cooldown in a i
one-hour period. Main feedwater was restored and auxiliary feedwater was secured.
2.
Auxiliary Feedwater Pump Bearing Failure October 7,1985 The second Rancho Seco event involved an auxiliary feedwater pump bearing failure. The safety significance is a partial loss of decay heat removal capability. The reactor was in hot shutdown when the main feedwater pumps tripped. Motor driven AFWPs were used to supply feedwater.
Smoke was observed from the "A" AFWP. A bearing had failed.
The causes were a mispositioned oil slinger ring which likely occurred in 1978; and a change made to the oil feeder level control made in 1982 which resulted in high oil level.
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REACTOR OPERATIONS 6
November 4, 1985 Hatch 1 - Crack in the Drywell Inerting and Purge Line - December 15, 1984 - Henry Baily, IE A linear through-wall crack 2-3/4 inches was discovered in the drywell inerting and purge line. The concern is over loss of containment integrity. The unit was in a refueling outage when the crack was discovered during ultrasonic inservice inspection. The crack was in a weld in this 18-inch line.
The licensee repaired the weld and submitted an LER on January 7,1985. The licensee is being cited by the Region for not immediately reporting the event per 50.72.
IE is considering additional actions on this issue.
Both the vendor (GE) and NRC had sent information notices outlining concerns for this system's integrity nearly a year before the' defect was discovered. When responding to the information provided, magnetic particle inspection was used, rather than the recommended ultrasonic (UT) examination techniques due to a lack of baseline data for the UT test.
Brunswick, Unit 2 - MSIVs Failure to Close - Vern Hodge, IE On September 27, 1985, three out of eight MSIVs failed to close in a test. The cause of the failure is a potential generic problem. The
. unit was shut down at the time. -The problem was traced to ethylene propylene disc degradation in the air-operated solenoid valve.
The four solenoid valves were sent to the Harris Energy Center for study. New solenoid valves containing viton parts have replaced the old valves. The reactor is now operating.
Turkey Pt. 3 - Problems with Aur.Iliary Feedwater, Following Reactor Trip July 22, 1985 (Follow-Up) - Robert Baer, IE and Daniel Mcdonald, NRR Unit 3 tripped from full power on July 22, 1985. High steam generator level caused MFW pumps to trip. All thred steam-driven AFW pumps started and ran. One pump had problems with an air-operated AFW control
REACTOR OPERATIONS 7
November 4, 1985 valve. MFW pumps were restarted. AFW pumps were shut off. AFW pump turbine governors were reset locally.
Steam supply valves to one turbine were placed in an off-normal configuration to facilitate trouble-shooting of the flow control valve. High steam generator level occurred again with MFW flow. AFW pumps were restarted. Two tripped on overspeed. The AFW pump with the off-normal steam valve configuration ran, but flow oscillated. The basic cause of the event:
governor oil was not drained properly when AFW turbines were reset locally.
Procedures outlining reset were not sufficiently explicit.
Currently the Staff is obtaining more detailed information from Terry Turbine and plans to prepare an information notice.
The Staff noted they had responded to ACRS comments (made on September 20,1985)ina letter dated October 28, 1985.
D. C. Cook, Unit 2 - Failure of Scram Breaker Undervoltage Trip Attachment - E. Rossi. IE Mr. Rossi gave a brief statement concerning a failure of one of the undervoltage trip attachments on one of the two scram breakers at D. C.
Cook. The event occurred on October 29, 1985. The plant was tripped from 80% power when the failure occurred.
During a subsequent bench test, the breaker that worked (Westinghouse plants use only two scram breakers) failed to operate. This test was only for the automatic trip; manual trip was not tested. The automatic shunt trip has not been installed at D. C. Cook 2, but it will be before operation is again allowed.
(Cook, Unit I had already added the shunt trip.)
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Conclusion:==
Mr. Ebersole explained the full Committee session would be from 3:00 -
4:00 p.m. on Thursday, November 7, 1985.
Items picked for presentation
{
to the full ACRS include: The Rosemont Transmitter Improper j
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4 REACTOR OPERATIONS 8
November 4, 1985 4
Installation, the Dresden 3 scram solenoid problem, and the Turkey Point 3 Auxiliary Feedwater problem follow-up.
The meeting was adjourned at 4:40 p.m.
i NOTE: A complete transcript of the meeting is on file at the NRC Public Document Rocm at 1717 H St., N.W., Washington, D.C. or can be obtained at cost from Ace Federal Reporters, Inc., 444 North Capitol St.,
Washington, D.C. _20001 [ Telephone (202) 347-3700]
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i 42810 Fed:ral Regi:ter / Vol. 50,' Nr. 204 / Tu:sdiy, October 22, 1985 / Notices pirsent, may exchange preliminary
, the ACRS staff merober named below as far in advance as is practicable so that siews regarding matters to be far in advance as is practicable so that appropriate arrangements can be made, considered during the balance of the appropdate arrangements can be made.
During the initial portion of the meeting.
During the initial portion of the meeting, the Subcommittee may The Subcommittee will then hear meeting. the Subcommittee, along with exchange preliminary views regarding presentations by and hold discussions any of its consultants who may be matters to be considered during the with representatives of the Duquesne present, may exchange preliminary balance of the meeting.The Light Company, NRC Staff, their views regarding matters to be Subcommittee will then hear consultants, and other interested considered during the balance of the presentations by and hold discussions persons regarding this reviews.
meeting.
with representatives of the NRC Staff Further information regarding topics ne Subcommittee will then hear and other interested persons regarding to be discussed, whether the meeting presentations by and hold discussions this review.
his been cancelled or rescheduled, the with representatives of the NRC Staff, Further information regarding topics Chairman's ruling on requests for the its consultants, and other interested to be discussed, whether the meeting opportunity to present oral statements persons regarding this review.
has been cancelled or rescheduled, the and the time allotted therefor can be Further information regarding topics Chairman's ruling on requests for the obtamed by a prepaid telephone call to to be discussed, whether the meeting opportunity to present oral statements the cognizant ACRS staff member, Mr.
has been cancelled or rescheduled, the and the time allotted therefor can be Herman Alderman (telephone 202/634-Chairman's ruling on requests for the obtained by a prepaid telephone call to 1414) between 8:15 a.m. and 5,:00 p.m.
opportunity to present oral statements. the cognizant ACRS staff member, Mr.
Persons planning to attend this meeting and the time allotted therefor can be Richard Major (telephone 202/634-1414) c.re urged to contact the above named obtained by a prepaid telephone call t between 8.15 a.m. and 5.00 p m. Pedons individual one or two days before the the cognizant ACRS staff member, Mr.
I I"8 to attend this meeting are schedule Anthony Cappucci(telephone 202/634-
,g c changes m,d meeting to be advised of any 3267) between 8:15 a.m. and 5,:00 p.m.
Individual one or two days before the schedule, etc., which may
, have occurred.
Persons planning to attend this meeting scheduled meeting to be advised of any are urged to contact the aboved named changes in schedule, etc., which may Dated: October 18.1985.
Individual one or two days before the have occurred' Morton W. tibarkin.
h'b*l'0 i"E'*b'*0't0*f "Y
Dated: Octoyer 18.1985 Assistant Ex ecutive Dimctorfor Project changes in schedule, etc., which may Review.
ss stan ecut DimctarforPwject Date r18,1985.
coog
- c. 65-25186 Filed 10-21-45: 8.45 aml As s n Exe u DimctorforPmfect suma coot ruo.ei-u Advisory Committee on Reactor Review.
Safeguards, Subcommittee on
[nt noc. as.25185 Fded 10-21-85. 8.45 aml Regulatory Policies and Practices; suma caos ruo-m IDockets Nos. 50-269,50-270 and 50-2871 Meeting Duke Power Co.; Consideration of He ACRS Subcommittee on dvisory Committee on Reactor issuance of Amendments to FaclHty Regulatory Policies and Practices will Safeguards, Subcommittee on Reactor Operating Licenses and Opportunity hold a meeting on November 1,1985.
Operations; Meeting for Prior Hearing Room 1N6.1717 H Street, NW.,
Wa shington, D.C.
He ACRS Subcommittee on Reactor The United Stales Nuclear Regulatory ne entire meeting will be open to Operations will hold a meeting on Comm,ssion (the Commission) is i
public attendance.
Monday. November 4,1985, Room 1M6, considering issuance of amendments to The agenda for the subject meeting 1717 H Street, NW., Washington, DC.
shall be as follows:
ne entire meeting will be open to Facility Operating IJcenses Nos. DPR -
- 38. DpR-47 and DpR-55, issued to Duke public attendanIthe subject meeting Power Company (the licensee), for hiday, hemben, Imx m The agenda fo operation of the Oconee Nuclear Until5:00p.m.
shall be as follows:
%e Subcommittee will discuss SECY-Station, Units 1,2 and 3, located in 85-208 (Incident Investigation Program) 2nday. NovembeN,1985--r:00p.m.
Oconee County, South Carolina.
UntiltAe Conclusma ofBusmess De amendments would revise and recommendations made by ASI.BP S nent of The Subcommittee will review recent Technical Specifications (TSs) of the and ope related to the establi u en Incident Investigation Organization.
operating experience.
. operating licenses to establish a Oral statements may be presented by degraded mode of operation if a core
.within NRC members of the public with the flood tank boron concentration Oral statements may be presented by concurrence of the Subcommittee decreases below the current members of the pubhc wi:h the - e concurrence of tne Subcommittee Chairman: written statements will be requirement of 1835 ppm. Presently, the Chairman; written staterrents will be accepted and made available to the Oconee Nuclear Station, Units 1,2 and accepted and made available to the Committee. Recordings will be permitted 3.TSs require plant shutdown in 12 Committee. Recordings will be permitted only during those portions of the.
hours if the boron concentration in each
-only during those portions of the meeting when a transcript is being kept,'
core flood tank falls below 1635 ppm L
l rueeting when a transcript is being kept, and questions may be asked only by boren. De change proposed by the
' and questions may be asked only by members of the Subcommittee,its licensee would allow the boron-members of the Subcommittee,its consultants, and Staff. Persons desiring concentration in one core flood tank to consultants, and Staff. Persons desiring to make oral statements should notify decrease below the current minimum of l
to make oral statements should notify the ACRS staff member named below as 1835 ppm for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> while the ATTACH"ENT A dh
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PROPOSED SCHEDULE ACRS REACTOR OPERATIONS SUBCOMMITTEE MEETING NOVEMBER 4, 1985 WASHINGTON, D.C.
R00!i1046 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) 3:00 PM BREAK (10 min) 4:45 PM 3.
Select items to be presented to the (15 min) full Committee on Thursday, November 7, 1985 from 3:00 to 4:00 P.M.
5:00 PM 4.
Adjourn
Attachment:
List of Recent Significant Events O
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ATTACHMENT B i
As of'Octobe'r 28, 1985 t
Tentative Agenda for ACRS Subcommittee Meeting on November 4, 1985 1:00 p.m.
- Room 1046, H Street RECENT SIGNIFICANT EVENTS Presenter / Office Date Plant Event telephone 8/15/85 Catawba Partial Loss _of AC Power D. Powell, IE During DG Operability Test (492-8373) 10/10/85 Maine Yankee Rosemont Transmitter Improper P. Sears, NRR Installation (492-7458) 09/19/85 Dresden 3 Scram Solenoid Problem Induced E. Weiss, IE RCS Leakage (492-9005) 09/18/85 North Anna 1/2 EDG Engine' Failures L. Engle, NRR (492-7094) 10/02/85 Rancho Seco Reactor Trip and Excessive H. Sailey, IE 10/07/85 Cooldown (492-9006)
AFW Pump Bearing Failure 12/15/84 Hatch 1 Crack in Drywell Inerting and H. Bailey, IE Purge Line (492-9006) 09/27/85 Brunswick 2 MSIVs Failure to Close M. Grotenhuis, NRR (492-7367) 8/8/85 Turkey Pt. 3 Post Trip Loss of Auxiliary NRR/IE Feedwater (Followup)
Failure of Magnesium Rotors J. Stewart, IE on Limitorque Valve Operators (492-9061)
During EQ Testing Note:
Other recent events at Palo Verde will be discussed with another ACPS subcommittee on November 5, 1985.
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