ML20024C827
| ML20024C827 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Crane  |
| Issue date: | 02/03/1978 |
| From: | Cobb W BABCOCK & WILCOX CO. |
| To: | Cobb W, Herbein J, James Smith BABCOCK & WILCOX CO., DUKE POWER CO., METROPOLITAN EDISON CO. |
| References | |
| TASK-*, TASK-11, TASK-GB B&W-1001, NUDOCS 8307130380 | |
| Download: ML20024C827 (32) | |
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t February 3, 1978 To: S&W User's Group Distribution
- Attached is a copy of the minutes of our User's Group meeting on November 15 and 16, 1977 Very truly yours, Nk W. A. Cobb B&W Representative S&W User's Group WAC:dmd Attachments
- Per attached distribution list.
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0 DISTRIBUTION LIST ScW USER'S CROUP
'.' J. G. Herbein (Jack).
Mr. R. J. Rodriguez (Ron)
Manager, Nuclear Operations le,o President, Generation Sacramento Municipal Utility District stropolitan Edison Company Rancho Seco Nuclear Generating Station L
- 0. Box 542 I
P.0. Box 550
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sading, Pennsylvania 13603-Herald, California 95638 (215) S2P3601 (203) 748'-2751
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Mr. G. P. Beatty, Jr.
(Guy)
- r. W. A. Cobb (A1)
Nuclear Plant Superintendent anager, Generic Projects Florida Power Corporation sbcocli & Wilcox Company -
P.G. Box 1228
- r. J. Ed Smith (Ed)
Mr. J. G. Evans (Jack)
Assistant to VP, Energy Supply tStlon Manager Toledo Edison Company
- enee Nuclear Station
,~300 Madison Avenue 7
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Box 1175 aneca, South Carelina 2S678 To,1edo, 0hto,,43652,,
(803) 882-1039. '
(41S) 259-5690 Mr. G. P. Miller (Gary)
- r. J. P. O'Hanlon (Jim)
Station Superintendent nit i Superintendent Three,Mlle Island Nuclear Station a
bree Mile Island Nuclear Station,
Metropolitan Edison Company ctr,opolitan Edison company P.O. Box 480
.0 Box 480 Middletown, Pennsylvania 17057 iddletown, Pennsylvania 17057 (717) 944-4041 (717) 344-4041
- r. J. W. Anderson (dohn)'.
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,Mr.'R. V. Montross (Bob)
Plant Superintendent lant Superintendent Consumers Powr Company rLansas Nuclear One 1945 Parnall Road
.0. Box 608 Jackson, Michigan 49201 ussellville, Arkansas 72801 (517) 788-2242 l
(501) 968-2513-O-
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Ol5TRIBUT10N LIST (C0!!T'D) 8t,W USER'S GROUP Mr. Paul F. Ahern Mr. A. M. Qualis Principal Nuclear coerations Suoervisor Plant Superintendent Power Authority of the State of New York Bellefonte Nuclear Plant 10 Columbus Circle P.O. Box 2000 New York, New York 10019 Hollywood, Alabama (212) 337-2336 (205) 259-0420 Mr. H. Ray Caldwell (Ray)
Mr. John h1ada's
Nuclear Operations Engineer
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Station Manager Ohio Edison Company North Anna Power Station 76 South Main Streer P.O. Box 402 Akron, ohto 44308 Mineral, Virginia 23117
.(216) 384-5778
,,703) 894-5151
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Mr. L. L. Lawyer (Sandy)
Ar. T. L. Baucom Manager, Generation Operations Station Superintendent Hatropolitan Edison company Surry Power Station P.O. Box 542 P.O. Box 315 Reading, Pennsylvania 19603 Surry, Virginia 23883 (215). 929-3601
" (703) 683-0900 (Bruce)
Mr. Paul Yundt (Paul)
Mr. 8. E. McLeod Plant Superintendent Plant Superintendent Portland General Electric Company Vashington Public Power Supply System 121 5.V. Salmon Street 3000 George Washi,ngton Way Portland, Oregon
$7204 P.O. Box 368 Richland,, Wash'ington S9352
.(503)~226-8388 (509) 946-1611 Mr. T. D. Murray (Terry)
Station Superintendent Teledo Edison. Company Davis-8 esse Nuclear Power Station 5501 North State Route 2 Oak Harbor, Chlo 434,49 e
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s MINUTES OF MEETING - B&W USER'S GROUP NOVEMBER 15 s 16, 1977 G ENERAl.
i The 8sW User's Group met on November 15th s 16th at the Twin Bridges Marriott Hotel in Washington. 0.C.
A copy of the list of attendees is attached as.
In general, the meeting followed the previously prepared agenda, a copy of which is attached to these minutes as Enclosure 2.
Mr. W. A. Cobb of SsW chaired the meeting in the absence of Mr. J. G. Evans, User's Group Ch'a i rman.
4 MEETING OF NOVEMBER 15, 1977 (FIRST DAY OF MEETING)
OCONEE OTSC TUBE PROBLEM C. V. Pryor of S&W mode a presentation on the OTSG tube problem. Mr. Pryor described the eddy current inspection program which.had been conducted at Oconee as well as Three Mlle Island and SMUD. Tubes inspected by eddy current were Identified as to location within the steam generators along with those tubes in which Indications of greater than 20% of wall thickness had been Identified'and those having indications of greater than 40% of well thickness. Mr. Pryor also identified those tubes which had been plugged as well as those which have been stabilized (strengthened by insertion of a solid rod within the tuba).. 8sW's recommended _ standard tube _ pattern for eddy current inspection was also presented.
Mr. Pryor indicated tMt most edfy current indTH elons were Tound in the proxi-mity of the open tube lane which was provided for inspection on the earlier 177 units.
Indications were primarily along this open tube Inspection lane in the area between the upper tube support plate and the upper. tube sheet. Most Indi-cations were immediately adjacent either to the tube support plate or the tube sheet. Mr. Pryor also described the. vibration test program which had been-con-ducted at Oconee and the test program which is planned on TMI-2.
It was further pointed cut by Mr. Pryor that B&W had previously conducted meetings to describe i
the problem in comprehensive fashion to all of the operating plant owners and that later presentations were planned for 205 plant owners.
Following this presentation, Mr. R. J. Saker of SsW Nuclear Service Department, described fleid operations relating to the OTSG tube problem. Mr. Baker's presenta-l tion covered methods of plugging tubes sstabilizing tubes along with the field l
problems encountered in this work. He also described cube removal operations where tubes are removed intact for examination of cause of defect. The presentation covered operations at Ocones, Three Mile Island, and SMUO. Of particular Interest was the, problem with radiation sevel in the SMUD generators.
l REFUEL.ING EXPERIENCE Jim Phinney of 85W described the refueling experience on B&W units during the last year. Refueling work was reported to require thirty-tnree (33) days If no addi-tional work was required. However, an average of thirty-one (31) days extension was required for additional unck either on 80P ltams or N53 Items. The major Items causing outage extensions were the following: high reactor building activity, l -,-.,,_, -, - - _ - _ -....,, _, - - _ ' - _. _ - - _
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extended eddy current Inspection, OT5G tube repairs, fuel element bow and twist damage, fuel handling equipment failures, RC pump seals, turbine problems, seal plate leakage problems, stator problems, and polar crane problems.
8sW's program to improve reliability was described. Major steps In the action plan include collection of operating data on reliability, an actiori plan for availability improvement, equipment upgrading as indicated by field reliability data Improved services to customers, and a new BsW 5 pare Parts Center to better address the utilities' needs. Mr. Phinney also reported on specific reliability items as follows:
(1) Seals - SsW's 875-s-3 seat for 177 units is expected to complete testing in mid-1978 and subsequently be available for use on operating plants. This seal is expected to provide significantly improved reliability.
(2) Fuel Handling Equipment - BsV is incorporating Into new fuel han-dling equipment a continuous control rod guide brazement in the control rod handling anst.
(3) BsW has tested and is offering for replacement use a Target Rock spray valve. This valve Is a sealed valve which has been tested for many. cycles of operation.
(4) Graham Letdown Cooler - B&W has conducted wrk on explosive plug-ging of tubes and on sleeving. A final report is expected in December.
If development is expected to be required B&W will make a proposal to those utilities utilizing Graham coolers.
(5) ICs - asW has visited a number of plants to assess " hunting" move-ment of the CRD's due to the ICS systems. A universal fix is very exclusive. There are some Indications that different ICS settings at the various plants may cause a different response to the same fix. As a result, 8sW will send block schematics to all of the
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to erating utilities and asli for all.)CS settings. The Information t' Ten,be'usecT tci'try to.lete'r.mine a common fix.
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will Jim also reported on the ERDA refueling outage availability program being conducted by 8sW. Phase 1 covering the N55 has been completed with 11 to 12 critical path days saved. Phase 2 of this program to develop prototype implementation at Oconee is planned.
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Mr. Phinney listed the following services as being available from 88W:
1 (1) Special tools l
(2) Procedure improvements (3) Special recovery teams (OT5G, RC pump seals, CROM inspection and repair)
(4) Special services (video equipment, ' noise / vibration detection)
(5) outage staff augmentation (6) Hands-on work packages.
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3 Finally, Jim made the following sunnary recommendations:
(1) Use B&W's refueling experience (2) Use the recommendations from the ERDA study i
(3) Utilize contingency planning (4) Utilize outage critiques and outage reports (5) Plan for good in-plant communications (6) Provide standard health physics and security (7) Make early commitment to contracted work (8) Have decontamination facilities available.
RC COOLANT PUMP SEALS Bill Spangler reported on RC pump seals and on the recent problem with RC pump It was reported that the. endurance test on the long-stack 875 seal gaskets.
had completed 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> with excellent results (the 875 short-stack which will be used as replacement seal for 177 FA size Bingham pumps is scheduled to go on test in early December). The results from the 875 long-stack seal Indicate a possible lifetime of 3 to 5 cycles without maintenance.
Bill also reported on the test experience for the 950 seats which will be used ~
on the 205 plants with singham pumps. Approximately 5.000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of testing has been completed on this seal with very successful results. John Anderson of Arkansas P&L Inquired about tests being conducted on B-J seat s.
8III responded that we haven't had as many problems with 8-J seals and hence have no further development work underway. Mr. Anderson further reported a 200 to 300 psi cycling on the B-J seals. Mr. Bradham of Duke reported that the 875 seats installed in Oconee had only 1/3 to 1/2 the maintenance time of the previously installed seals.
Bill ~ also reported on gasket leakage with Singham pumps.
It was reported that the problem was caused by insufficient gasket rebound for the flange motions caused by pressure and temperature gradients. The following fixes will be incorpo-rated:
(a) Revised Installation procedures (b) Higher gasket dens'ity to improve resiliency (c) Incorporation of a hard nose on the gasket (d) New gasket filler material (e) Higher bolt lead (pre-load)
NUCLEAR PART5 CENTER Mr. L. R. Weissert described the newly organized B&W Nuclear Parts Center. Lou described in some detall the organizational setup of the new center to serve the needs,of the operating utilities.
He set the following goals for this organi-zation:
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(a) To be on call and on time (b) To provide fast response 3
(c) To provide updated parts manuals (d) To assist in spare parts Inventory planning and in planning for parts needed for outages l
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(e)' To define Interchangability of supplied parts (f) To provide a parts locator service.
Mr. Weissert also expressed a desire to meet with utility representatives to discuss their inventory policy and develop a spare part plan with them. The Owners were asked.for a contact within their organization for this function.
Mr. Rodriguez of SMUD requested that 85W develop a policy on 88W Inventory of spare parts and to report this policy to the. utilities with particular regard
-q to the Inventory of spare RC pumps or RC pump Internals.
lNCORE DETECTORS Mr. E. 5. Patterson of 8&W described the design of the B&W Incore detectors and a possible failure mechanism for the failures which have been encountered. The presumed mechanism postulates a defect in the outer sheath of the detector with RC water then causing stress corrosion cracking of the individual detector sheaths.
He pointed out that while the mechanism explains the failure of the detector after water entry it does not explain the presence of initial defects in the detector l
sheath. He Indicated the following steps which B&W has taken to improve the equipment for later applications:
(a) Better material control (b) Increased inspection in fabricatl' n o
(c) Improved heat treatment of the ladividual detectors and of the final detector assembly (d) Improved non-destructive testing during fabrication (e) Closer follow of performance at Individual operating plants.
Pat Indicated a failure rate of approximately 1% at most operating plants, but approximately 5% of the oconee units, which used earlier manufactured detectors.
He further Indicated that planning for supply of replacement detectors was important.
Mr. Anderson of Arkansas Psl Indicated a 15 month lead time for pre-vlously ordered detectors. Pht_nney of _BsV,1,rt cated.that Instructions on, check-di Inc the resistance of notentially, failed detectog,woQbe fo_rwarded to utilities in the near future.
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NI Call 8 RATION Mr. J. R. Smotrel of B&W made~ a presentation on NI calibration. The overhead slides used by Mr. Smotral are attached as Enclosure 3 His presentation addressed the following major points:
(1) The need to maintain Mi calibration (2) The causes of changes to NI calibration (3) Past events In discussion of this subject with the operating users (4) B&W's current reconnendetIons (5) Further 8sW program on Ni calibration.
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$1TE PR08LEM REPORTS AND FIELD CHANGES
'E. Wascher' of BsW described the systems which BsW has in place for assess-Mr. Rc Ing the applicability of a site problem found at one site to all of the other Bsw units. The system regul.res that an assessment be made and* documented on each If the documented assessment Indicates that the problem problem which arises.
is applicable to a given plant, the problem is added as an outstanding problem to computerized reports which Indicate the total number of problems outstanding I
against a given plant. The problems are thus maintained visible to management and can be expedited vigorously. The system likewise provides for generic handling of field changes.
RATCHET TRIP The Mr. A. W. Brown of B&W made the presentation on the ratchet trip problem.
overhead slides used by Mr. Brown are attached as Enclosure 4.
Art Indicated that a number of proposals have been made through operating plant customers for mini-mizing the possibility of vacchet trip. The last of these proposals ws in pro-cess and should in the customers' hands launinently. The final quotation is for a systen which detects the Imminency of a ratchet trip and provides a conventiona.1 i
The trip on such a signal to prevent damage to the lead. screw and segment arms.
new system would cause the rods to drop only if they were commanded to move dur-Ing the time that a fault existed which could cause a ratchet trip to occur.
ICS Mr. R. W. Winks had been scheduled to make a presentation on the Improvements to preclude hunting in the Integrated control system. However, at the last minute Mr. Winks had been called to the Duke site on an urgent problem and was unable tc, attend. However, Mr. Phinney had earlier presented the essence of Mr. Wink's (see report on refueling experience in these minutes).
report MEETING 0F NOVEMBER 16,19N The meeting consumed one-half day and was devoted exclusively to plant experience reports by the station superintendents. Resumes of their reports are presented below:
(
CPERATIONS AT OCONEE I
Mr. O. 5. Bradham of Duke Power Company gave the report on Oconee (Mr. Bradham's report was actually given on November 15, IS77 to Parmit his return to oconee).
(1) Tube leaker on OT5G - Oconee !!
(a) Leak determined through air ejector readings; scrne disagressent with steam line monitors.
(b) Leak apparently only I gpm; may be only gas.)
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6-g Radia-(c) Turbine building sumps and releases not based on I gpm.
tion seeping into concrete in sumps causing higher background.
A reconsnendation was made that tube leaks should be considered in the design of the turbine building.
(d) Problems encountered were the following:
(1) Training people who do not normally work in radiation.
(2) No change rooms in area of turbine building.
(3) Problems with radiation monitoring and control of releases.
(2) Stator Problems (a) The problem of valve leakage running down into the control rod drive stators was described. The problem was complicated by the fact that this is cromated water.
(b) The difficulties of changing CRDM stators when the drives were at approximately 120' to 130*F were described.
(3) RC pump seals - Ollie described problems with particles from welding processes which were not properly flushed from the system' prior to operation.
(4)
Mr. Bradham described-the sources of reactor building radioactivity.
(a) AC system leaks (b) Leaking fuel (c) Velan valves (d) Bingham RC pump gaskets leaking (5) Duke is planning to change out all valves to utilize packless valves.
OPERATIONS AT THREE MILE ISI.AND l
Mr. G. P. Miller, Superintendent of Three Mlle Island Station led off the report t
by announcing the appointment of Mr. J. P. O'Hanlon as Superintendent for Three Mile Island Unit 1.
Mr. Miller then reported on progress at Three Mile Island l
Unit 2.
The following items were reported:
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f (1) Fuel load is expected somewhat af ter the beginning of the year.
(2) The following was the chronology of events for 1977:
(a) ACR$ hsarings - early 1977 (b) RCS system filled - May 1977 (c) Public hearing - July 1977 (d) Hot functional test - finished October 1977 l
Mr. Miller reported that the biggest reamining problem involves the main steam line break analysJ s.
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(3) Licensing examinations were passed by 12 CRO's; 2 SR0's must retake the examinations.
(4) There were two fires in Unit 2.
(5) Standardized tech specs must be used on Unit 2 causing a probable backfit on Unit I for uniformity.
(6) 450 people. are employed in operations at the site, not count-Ing security or training (50 to 80 guards are employed)
Mr. J. P. O'Hanlon repor"tod on Three Mile Island Unit 1 as follows:
(1) Capacity factor has been approximately 75%.
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(2) The following chronology of events was given:
February 1977 - Change to monthly turbine stop valve test at 50%.
March 1977 - Refueling and fuel shuffle required 8 weeks.
Snubbers and CTSG eddy current tests lengthened the re-fueling.
July 1977 - Deluge system operated. There was a problem in maintaining vacuum due to shrimp Intake into the condenser.
September 1977 - Valve failure caused acid breakthrough to OTSG. Ph was 2 or 3 Also, a high resistance connection
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to the AC pumps caused arcing and ultimate vaporization of the connector and a cable length. A generator ground fault also caused the unit to trip during this month.
October 1977 - The unit tripped due to an ICS signal convertor failure.
(3) Three Mlle Island I will convert to standardized tech specs at the refueling outage in 1979 The increased surveillance testing Identified by these specs would probably double the present required testing.
(4) On the OTSG's, 9 tubes were plugged. Only one or two required plug-ging, and the remainder were plugged for conservatism. GPU feels that the OTSG tube problem may not be generic and that the problem may be to differing layups of the generators and different operation of the emergency feed nozzles.
(5) TMI plans monthly vibration testing on the DH pump to assure that the problem which occured at Florida Power Corporation does not cause failure of the TMI pu ap.
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. f CRYSTAL RIVER lli - FLORIDA POWER CORPORATION
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Mr. G. P. Beatty reported on operations at ' Crystal River ill.2s follows:
(1) Licensed Decen6er 1976 based on standardized tech ' specs (338' j
surveillance procedures are required by STS)..
(2) The following chronology of events was reported:
I January 1977 - Initial criticality March 1977 - 100% power May 1977 - Problem with governor valves on Westinghouse tur-bine. Ten day outage - borrowed replacement. 'Also during this month there was a salt water leak into the condensers causing four additional days outage.
June 1977 - Operated at 70-75% capacity factor. Experienced stator failures; replaced hot at approximately 130*F.
July 1977 - Experienced one or two additional stator failures.
All stators were changed out from epoxy to varnish type.
No subsequent stator problems occured. An expansion joint disintegrated on the turbine.
1002 load rejection with no reactor trip was experienced.
(3) FPC lestituted its own fix on the ICS to correct excessive control p~
J roJ motion. This reduced rod motion per once every 4 or 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Handout on the_ fix was distributed (F. R. Fahland of S&W has a P
~ copy).
(4) A total of 350 modifications (MAR's) have been issued on Crystal Alvor 3
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(5) A management consultant has reconenended 34 more positions on the operating staff. This will bring the staff to jlg, people not counting security or system maintenance.
7 (6) FPC allows the use of furmanite on the secondary side of the plant without engineering approval. One furmanite joint has leaked.
d ANO #1, ARKANSAS Pst Mr. J. W. Anderson reported on operations at ANO-I as follows:
(1) Two rows of blades were cut out during refueling. Two high pres-
' sure heaters were out of service with tube leaks on the secWary side.
(2) It now appears that refueling on Unit 2 and Unit I will be coinci-dent.
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9 (3) The reactor protection system on Unit 2 will have a calculating module..
(4) During the problem with the surveillance holder tube,all of the fuel had to be' removed to remove the pieces of the surveillance A total of 609 polnds of original weight (all but holder tube.
two pounds of the surveillance holder tube components) were retrieved.
(5) A total of 31 operating days have been lost, a total overall caps-city factor of 70%.
(6) One ratchet trip has occured since the last meeting of the User's This was apparently a fault in the transfer switch.
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(7) AND has its own equipment for installing furmanite.
(8) John reported a problem of Asian clams clogging the condenser.
The screens won't take out the larva. Clorine must be used during a very narrow time window in order to destroy the larva.
BsW was (3) The' computer was changed out during the last refueling.
very helpful. APsL is very happy with the computer supplied by Systems Engineering Laboratory.
(10) Mr. Anderson is pleased with the sodlum recorders which he is using.
4
_ (11) John reported a bonnet-to-body leak'In the Velan shutoff valve
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immediately ahead of the spray valve.
(12) AN0-1 is operating with approximately 33% efficiency with the leaks in the condenser being the biggest efficiency loss usually.
(13) A reactor building cooling fan is out of service with a bearing failure (Joy axial flow fans).
(14) 327 men are employed in operations including all security and custodial l
fo rces.
RANCHO SEC0 - SMUD Mr. R. J. Rodriguez reported on operations at Rancho Seco as follows:
(1) Chronology of events:
January 1977 - Unit trip during instrument check (went out F,v.fe turbine) on high vibration on a.s w January 1977 - Main feedwater p' ump trip. This was apparently a governor problem.
January 1977 - 100% load rejection test without reactor trip O
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April 1977 - CR0 stator problems Spray valve malfunctions. Forty (40) hours required to fix bypass valve.
July 1977 - CRD transformer shorted to ground. CAD group #6 dropped causing crud burst.
(2) The Rancho Seco capacity factor has been 962 through the first 7 1/2 months of 1977
. (3) Ranc'ho Seco has a program to shock the system.with lithium hydroxide (L10H) to prevent plate-out of crud on fuel assemblies.
(4) A total of 340 man rem of irradiat'lon dosage was Incurr'ed durl'ng re-fueling.
(5) A total of 52 Velan valves in the 1" to 1 1/2" range were replaced with potest diaphragm, valves during refueling.
.:.wsa (6) During QT5G inspection. Iron oxide was noted in the lower tube sheet crevice.
(7) RC pump seats did not fit well during installation. Machining was required. One leaked and a chip was found between the seal rings.
This es corrected, and the seals are now operating well.
(8) A tear-down of the Westinghouse turbine was accomplished during re-fueling good and clean. Governor valve seat was broker. and all were replaced. The generator was in good shape. Cracking was detected in the turning vanes in the piping. Baffles were lost in the MSA and 12% of the tubes in tne reheater high pressure coil were plugged.
(3) A problem in drawing control ws reported, particularly the updating of drawings to reflect changes. As a case in point, it u s indicated that the drawings in the CRD Control Manual CR0 System Manual do not agree with the drawings which were submitted for approval originally M,
$8%Ind_icated_ that the manual _ drawings wege.agorryt).
(10) The problem of corrosion was reported on unprotected carbon steel pipes in the reactor building due to humidity.
(11) CAD group 6 was reported as being hard to latch due to chips caused by previous ratchet trips.
Davis-5E55E TOLEDO EDISON COMPANY Mr. T. D. Murray, Superintendent of D-B reported on operations as follows:
(1) The following chronology of events was reported:
3/22/77 - All transmission lines out of service. One diesel also out of service. Fuel loading went very smoothly.
Some problem with fuel handling equipment..
7/03/77 - Entered mode 4.
Experienced some vibration problems with main feedwater pumps due to pipe loads on pump.,
- II -
7/16/77 - Entered mode 3 Experienced problems with check
.l valves In DH system sticking open.
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8/12/77 - Initial criticality. Some problems were experienced ll with the reactimeter.
l 8/28/77 - Feed pump tripped due to surge capacitor failure.
3/14/77 - CRDM stator failure Rupture disc 3/24/77 - Electromatic relief valve stuck open.
ruptured.
10/23/77 - SCRF5 trip Impeller failure on. main feed pump (DeLaval) 10/28/77 -
11/15/77 - Some protlem with water hammer due to steam traps at 403 power.
(2) Mr. Murray announced that Mr. J. G. Evans, Chairman of the 84W User's Group, had been promoted to Assistant to Vice-President, Energy Supply.
The meeting adjourned shortly after noon on November 16,1977 It was agreed by all that the meeting had been useful and beneficial.
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o ENCLOSURE I ATTENDEES BsW USER'S GROUP MEETING NOVEMBER 15. 1977 I
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Company Name WPPSS W. C. Bibb (Bill)
WPPSS J. R. Holder (Joe) i Duke
- 0. 5. Bradham (0111a)
Consumers R. W. Montross (Bob)
SMUD R. J. Rodriguez (Ron)
Toledo Edison
. T. D. Murray (Terry)
Ohio Edison
. W. Junctlla (John)
Ohio Edison
. Ray Caldwell (Ray)
Arkansas Power & Light
. W. Anderson (John)
Florida Power
.j R. Westafer Florida Power G. P. Beatty (Guy)
Portland General Electric J. C. Perry (Jay)
Metropolitan Edison - TMI G. P. Miller- (Gary)
Metropolitan Edison - TMI-l J. P. O'Hanlon (Jim)
TVA i
A. M. Qualls (Allan) l PASNY P. F. Ahern (Paul) 84W W. A. Cobb (A1) l B&W J. P. Phinney (Jim) 8sW W. H. Spangler (8111)
S&W l
C. W. Pryor (Chart le) 88W J. R. Smocral (Jim)
'EsW A. W. Brown (Art)
BsW R. E. Wascher (Bob) 8&W E. 5. Patterson (Pat)
L. R. Weissert (Lou) 8&W 8&W F. R. Fahlsnd (Frank)
BsW R. J. Baker (Bob)
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ENCLOSURE 2 AGENDA B&W USERS GROUP HEETING
, NOVEMBER 15 s 16,1377 TWIN BRIDGES MARRIOTT MOTEL WASHINGTON, D.C.
NOVEMBER 15. 1977 0800 - 0810 C0FFEE 0810 - 0820 OPENING REMARKS W. A.'C088 '(AL) 0820 - 0915 OCONEE OT5G TUBE PR08LEM C. W. PRYOR (CNARLIE) 0915 - 1015 REFUELING EXPERIENCE J. D. PHINNEY (JIM) 1015 - 1030 C0FFEE BREAK 1030 - 1200 B&W BRIEFINGS
(%20 MINUTES EACH)
(1) KC PUMP SEALS W. N. SPANGLER (BILL)-
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(2). N'.' CLEAR PARTS CENTER L. R. WEI53ERT (LOU)
(3) INCORE DETECTORS E. 5. PATTERSON (PAT)
(4) NI CAllBRATION J. R. SMOTREL (JIM)
(5) SITE PR08LEM REPORTS s R. E. WRSCHER (50 8)
FIELD CHANGES (6) RATCHET TRIP A. W. BROWN (ART)
(7) ICS R. W. WINKS (808)
IN-R00M BUFFET SERVICE 1200 - 1300 LUNCH 1300 - 1400 B&W BRIEFINGS (CONTINUED) 1400 - 1630
,5UPERINTENDENTS QUESTION PERICO (1) GCONEE (8) TVA (2) TMI (3) VEPCO (3) CR #3 (10) WPP55 (4) ANO #1 (11) PGE (5) RANCNC SECO (12) PASNY (6) DAVIS-BESSE (13) OHIO EDISON (7) CONSUMERS NOVEMBER 16. 1977 0800 - 0810 C0FFEE 0810 - 1100 PLANT EXPERIENCE REPORTS
($25 MINUTE 5_EACH)
OCONEE ANO #1 TMI RANCHO SECO CR #3 DAVIS-8 ESSE 1100 - 1200 USERS GROUP SUSINESS e
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ENCLOSURE 3 NI CALIBRATION
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NEED TO MAINTAIN-NI CALIBRATION II.
CAUSES OF CHANGES TO NI CALIBRATION III.
PAST SEQUENCE OF EVENTS IV.
B&W RECOMMENDATIONS V.
CURRENT PROGRAM O
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NE5D TO MAINTAIN *NI CALIBRATION A.
Core power as derived from NI's feeds Reactor Protection System (RPS), therefore, NI calibration must be maintained so plant protection is not compromised.
B.
Total flux signal uses in RPS:
RPS-I RPS-II S,T High Flux T
High Flux Flux / Imbalance / Flow - S,T Flux / Flow T
S,T Flux Pump Monitor T
Low DNBR Flux / Offset S
Flux / Delta T T
T required for transient protection 5 required for steady state protection C.
Safety Analysis assumptions 1.
Tech Specs and FSAR are based on SA assumptions 2.
Total NI calibration error of 4%FP to heat balance a.
Normal calibration error limit
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CAUSEsorCHANdETONICALIBRATION II.
NI detectors infer core power from core leakage flux Factors that affect core power to leakage flux relation-ship at NI detectors:
1)
Changes in neutron transport medium Hydrogen density in downcomer (T
changes) e Boron concentration in downcomer 2)
Changes in radial flux profile Rod movement Xe distribution Depletion (slow effect) 4 p
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PAST SEQUENCE OF EVENTS l
I,etter sent to 177 FA plant customers
- August 1976 recosamending more frequent NI calibration checks.
I,etter sent to.177FA plant., customers
- March 1977 reinforcing previous recommendations and providing more detailed surveillance suggestions.
Information meeting held in I,ynchburg
- April 1977 with 177FA plant customers to discuss March letter and obtain customer feedback.
I.etter sent to'177FA plant customers
- May 1977 containing proposed revision to Baw Standard Tech Specs on NI calibration 3
for comment.
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- October 1977 - Letter sent to 177FA plant customers containing recommended changes to Tech Specs and Operating Procedures.
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1.
NI Power range calibration to heat balance should be checked a alnimum of once per shift.
j 2.
A re-calibration is required 'whenever a c'alibration check shows that the heat balance power exceeds the NI indicated power by 2tRTP or more.
[ Note:
The safety analyses for this plant was performed assuming a maximum calibration error of 4%RTP (beat balance > NI indicated power) in the RPS setpoint.]
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i Recommended Chances To Operatine Procedures A.
During startups 1.
Check NI power range calibration at power levels of approximately 15-30, 70, 90 and.100 percent of Rated.
Thermal Power (RTP).
2.
A NI power range calibration should be performed if:
r a)
Beat Balance (EB) minus NI indicated powerp> 2% RTP at h- 0% RTP 15-30, and 60% RTP calibration checks.
b)
EB minus NI indicated power [> 2% RTP at 90 and 100%
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[ <-2% RTP RTP calibration checks.
i B.
Steady state operation (Power level maintained within 5%RTP band and no changes in rod index.> 15% since last calibration check).
1.
Check NI power range calibration once per shift and recalibrate, if necessary, in accordance with Tech.
Spec. limits.
C.
Power changes > 5% RTP and/or changes in Rod Index >'15% since last cslibration check.
1.
Chec4 NI power range calibration after reaching desired power level and re-calibrate, if necessary, in accordance with Tech. Spec. limits.
2.
In addition to first check, a minimum of two additional checks should be performed at 2 to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> intervals to confirm that the calibration has stabilized, i.e. calibration is still with-in Tech. Spec. limits.
This additional checking should con-tinue until two consecutive checks show that further recali-bration is not required.
D.
NI Power Range Calibration Without the Computer If the computer is not available for heat balance calculations, Tech. Spec. calibration limits should be adjusted in accordance with the accuracy of the hand heat balance calculatio.nal method used, i.e. a NI calibration should be performed if the calibration check shows l
l (Band Calc. BB minus NI indicated power) > (4%RTP minus IB Calc.
Accuracy
- l',%RTP])
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- A value less than 2%RTP cannot be used without prior NRC approval.
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t V.
CURRENT PROGRAM Calculational code is being developed to investigate A.
the combined effects of power distribution and downcomer property changes on out-of-core detector resporise.
Results will be used to determine magnitude of calibration problem on feed-and-bleed type plants.
B.. Conceptual designs for auto calibrator (AT) and remote manual calibration devices have been developed for operating plants.
Decision to continue work on these items will be based on the extent of problem following implementation of new Tech Specs and Operating Procedures.
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O ENCLOSURE 4 RATCliET TRIP THE CONDITION THAT OCCURS WHEN A CRDM STATOR IS MOMENTARILY DE-ENERGIZED AND QUICKLY RE-ENERGIZED AGAIN BEFORE THE'CRDM LEADSCREW TRAVEL IS COMPLETE.
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A SUPPLY GROUP BUS n
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B SUPPLY ia COIL GATE CONTROL DRIVE
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RATCHET TRIP PREVENTION PLAN OBJECTIVE -
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1.
MINIMIZE THE POSSIBILITY OF FAILURES
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2.
MINIMIZE THE CONSEQUENCE WHEN FAILURES OCCUR O
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1 IF A STATOR PHASE FAILS TO BE ENERGIZED OR FAILS TO BE DE-ENERGIZED DURING ROD MOVEMENT, ROD WILL BE TRIPPED.
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- s AREAS ~OF ItiPROVEliENT IMPROVED GATE DRIVE A'SSEMBLY TRANSFER Sw!TCH FAILURE DETECTION power SUPPLY SEQUENCE VERIFICATION IMPROVED IRANSFER Sw!TCH IMPROVED SEQUENCE PROGRAMMER i
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i TRAlll.' F ER CVilTCH AG'l !' i' I
n NEW COMPONENT ANALYSIS AND TESTING 1.
A MATHEMATICAL ANALYSIS OF THE DESIGN IS CONDUCTED USING WORST CASE CONDITION.
2.
A LAB TEST IS CONDUCTED'TO VERIFY.
THIS ANALYSIS.
3.
A PROTOTYPE IS TESTED UNDER
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ACTUAL CONDITIONS IN THE CRDM ACdEPTANCEPROGRAM.
4.
AN ACCELERATED LIFE TEST IS CONDUCTED.
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