ML19326B765
| ML19326B765 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Oconee, Mcguire, Saint Lucie, Point Beach, Arkansas Nuclear, Brunswick, Turkey Point, Crystal River, Farley, Robinson, McGuire  |
| Issue date: | 01/03/1974 |
| From: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| IEB-74-01, IEB-74-1, NUDOCS 8004170597 | |
| Download: ML19326B765 (3) | |
Text
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UNITED STATES
o ATOMIC ENERGY COMMISSIC o
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DIRECTORATE OF REGULATORY OPERATIONS 1
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REGION ll - SulT E 818
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230 P E ACHT R EE ST R E ET. NORT MwEST 4fE5 o%
AT L. ANT A. G EoRGi A 30303 7 n,,,,,,,,,,,,,,,,,,,,,,
In Reply Refer To:
January 3, 1974 RO:II:NCM 4
THIS DOCUMENT CONTAINS 1
.2 POOR QUALITY PAGES Gentlemen:
The enclosed Directorate of Regulatcry Operations Bulletin No. 74-1, involving two valve problems is sent to you to provide you with infor-mation we recently received from the Philadelphia Electric Con:pany and the Wisconsin Electric Power Company. Tha problems involved def3,:iencies identified at the Peach Bottom, Units 2 a td 3 and the Point Beach reactors. This information mar relate to the performance of certain equipment at your facilities. The Bulletin also requests certain action on your part in this matter.
Very truly yours, 2 O gu Norman C. Moseley Director
Enclosure:
RD Bulletin No. 74-1 Dated January 3, 1974 O_
8 004170f 7 q
J Address list of a111 ties receiving bulletin for completion of requested action. Reply required within 30 days.
.l Directorace of Regulatory Operations Bulletin 74-1, January 3, 1974 l
Addresses In Reference To 1.
Alabama Power Company 50-348 Farley 1 1
ATTN:
Mr.
A.-R. Barton 50-364 Farley 2 Senior Vice President 600 N. 18th Street
. Birmingham, Alabama 35302 2.
Arkansas Power and Light Company
-313 'ANO, Unit M ATTN:
Mr. J. D. Phillips 50-368 ANO, Unit. '
Senior Vice President Sixth and Pine Streets Pine Bluff, Arkansas 71601 3.
Carolina Power and Light Company 50-261 Robinson 2 ATTN:
Mr. J. A. Jones 50-325 Brunswick 1 Executive Vice President 50-324 Brunswick 2 Engineering, Construction and Operation O.s 336 Fayetteville Street Raleigh, North Carolina 27602 4.
Duke Power Company 50-169 Oconee 1 ATTN:
Mr. A. C. Thies 50-270 Oconee 2 Senior Vice President 50-287 Oconee 3 Production and Transmission 50-369 McGuire 1 Power Building 50-370 McGuire 2 422 South Church Street Charlotte, North Carc, lina 28201 5.
Flcrida Power & Light Company 50-250 Turkey Point 3 ATTN:
Dr. R. E. Uhrig 50-251 Turkey Point 4 Director of Nuclear Affaire 50-335 St. Lucie 1 4200 Flagler Street P. O. Box 3100 Miami, Florida 33101 6.
Florida Power Corporation 50-302 Crystal River 3 ATTN:
Mr. J. T. Rodgers i
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Assistant Vice President l
Generation Engineering
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320134th Street, South
.P. O. Box 14042 St. Petersburg, Florida.
33733 0
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Georgia Power Company 50-321 Hatch 1 ATTN:
Mr. R. W. Scherer 50-366 Hatch 2 Execoitive Vice President 270 Peachtree* Street, N. W.
Atlanta, Georgia 30303
-8.
South Carolina Electric and Gas Company 50-395 Summer 1 ATTN:
Mr. E. H. Crews, Jr.
Vice President Construction and Engireering P. O. Box 764 Columbia, South Carolina 29202 e
9.
Tennessee Valley Authority 50-259 Browns Ferry 1 ATTN:
Mr. J. E. Watson 50-260 Browns Ferry 2 Manager of Power 50-296 Browns Ferry 3 818 Power Building 50-327 Sequoyah 1 Chattanooga, Tennessee 37401 50-328 Sequoyah 2 S0-390 Watts Bar 1 50-391 Watts Bar 2
- 10. Virginia Electric and Power Company 50-280 Surry 1 ATTN:
Mr. Stanley Ragone 50-281 Surry 2 Senior Vice President 50-338 North Anna 1 P. O. Box 26666 50-339 North Anna 2 Richmond, Virginia 23261 i
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. January 3, 1974 Directorate of Regulatory Operations Bulletin 74-1 4
VALVE DEFICIENCIES Information was recently received from the Philadelphia Electric Company and the Wisconsin Electric Power Company concerning two types
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of deficiencies relating to valves.
The deficiency identified by the Philadelphia Electric Company at the Peach Bottom, Units 2 and 3 facilities related to weld failures between the valve yoke and the motor operator mounting plate in valves supplied l
by the Walworth Company. A full description of the deficiency is I
provided in Attachment A.
The second deficiency, identified by the Wisconsin Electric Power Company at the Point Beach plant, involved a backseating disc mislocation problem on two inch Darling valves.
Full details are prosided in attachmen: B.
In light of the above information, you are requested to determine whether similar valves are installed or scheduled to be installed in your DUPLICATE LOCUMENT
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Entire document previously f
ad/2946M entered into system under:
Id lMhbhb ANO N o. of pages:
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facilities and inform this offf.ce in writing within 30 days of the date of this letter regarding the results of your determination.
Also please send a copy of your report to B. H. Grier, Assistant Director for Construction and Operation, Directorate of Regulatory Operations, USAEC, Washington, D. C.
20545.
In the event such valves are identified, you are requested to determine whether those identified valves have the deficiencies described and if 1
so, to inform us in your letter of the corrective action planned and the date of scheduled completion of tiiat corrective action.
Attachments:
A.
Philadelphia Electric Company Letter, dated October 1,1973 to Dr. Knuth 1
B.
Wisconsin Electric Power Company Letter, 1
dated October 29, 1973 to J. F. O' Leary t
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tiLADELPHIA ELECTRIC ~ 7MPANY i
G 2301 MARKET STREET PHILA DELPHI A.- PA.19101 V. S. DOYER vier-enessoant October 1, 1973 Dr. D. F. Knuth, Director Directorate of Regulatory Operations United States Atomic Energy Commission c
Washington, D.C.
20545
Subject:
Significant Deficiency Report -
High Pressure Service Water Valve Weld Failure Peach Botton Atomic Power Station - Units 2 & 3 AEC Construction Permit Nos. CPPR-37 and CPPR-38 File: OUAI,2-10-2 SDR No. 5
Dear Dr. Knuth:
V In compliance with 100FR50 55, paragraph (e) attached is the Significant Deficiency Report concerning the weld failure on the High Pressure Service Water valve in Unit No. 2.
This item was reported to AEC DRO I by telecon on June 1, 1973 We trust that this satisfactorily resolves this item.
If further infor=ation is required, please do not hesitate to contact us.
We appreciate your extending the time for our response to October 1, 1973 as agreed Ly telecon on September 14, 1973 between our Mr. G. R. Hutt and Mr. R. Heischennn, USAEC DRO I.
Sincerely, 1
4
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lI.N.t im Copy to:
J. P. O'Reilly, USAEC O)
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Attachment A Page 1 of 2 t
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jIO"IFICANT DFFICIENCY REPORT - SDP ").
5 (3
HIGt 2 ESSURE SERVICE MATER VALVE E., FAILURE k_l PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 & 3 AEC CONSTRUCTION PERMIT NOS. CPPR-37 AND CPPR-38 t
Description of Deficiency During a routine walk-thru of Unit' No. 2 plant by the licensees operating personnel, a 12 inch - 300 pound motor operated globe valve in the High Pressure Service Water line on the discharge side of one Residual Heat Removal heat exchanger was discovered to have experienced a weld failure.
The failure occurred between the valve yoke and the motor operator mounting plate.
The reason for the failure has been identified as insufficient fillet veld throat dimension caused by the installation of unauthori::ed shims between the yoke legs and the mounting plate, which reduced the effective size of the weld.
I i
Corrective Action l
The failed valve is one of a series of eight valves (four in Unit 2 and four in Unit 3).
These eight valves were visually inspected
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and a second valve uns found to have cracks in the yoke to motor operator mounting plate weld.1 All eight valves were returned to the vendor for rework.
The rework involved elimination of the shina in the failed valve and the rewelding of the mounting plates,to the yoke legs with full pene-tration velds on all eight valves.
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An investigation of similar valves'(supplied by the same vendor) elsewhere in the plant, was undertaken.
A total of 108 valves were iden-tified by the vendor to have yoke to motor operator mounting plate con-struction similar to that of the failed valve.
Fifty-eight (including the above mentioned eight) of these valves are nuclear valves classified as Group II-as defined by Figure A.2.1 of Appendix A of the Peach Bottom Atomic Power Station FSAR.
balance of plant velves.
The renining valves are GroupIII non-nuclear i
The Vendor's veld stress analysis ' calculations were reviewed and a table of acceptable veld sizes prepared.
a 1
This valve was originally reported in tne interim report to have shims.
The valve was only visually inspected at that time and the cracks were interpreted to indicate the presence of shims.
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Attachment A Page 2 of 2
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Wisconsin Electric eonacournur gh 231 WEST MICHIGAfi, MILWAUKEE,WISC0fiSiti 53201 7
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October 29, 1973 l
l Mr. John F. O' Leary, Director Directorate of Licensing j
U. S. Atomic Energy Cc:mnission Washington, D. C.
20545
Dear Mr. O' Leary:
DOCKET NOS. 50-266 AND 50-301 FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 POINT BEACH NUCLEAR PLANT BACKSEATING DISC MISLOCATION PROBLEM ON 2" DARLING VALVES In accordance with Section 15.6.6.A.3.b of the Technical Specifications for Point Beach Nuclear Plant (Facility Operating License Nos. DPR-24 and DPR-27), this report describes p) a possible generic problem with a category of 2" gate valves in-(V stalled at Point Beach Nuclear Plant.
The valves in question are 2", No. S-350 W;D welding end, outside screw and yoke, double disc gate valves with lip seals, and are manufactured by the Darling Valve and Manufacturing Company.
The valves used at Point Beach Nuclear Plant are safety class I, ASA series 1500 lb. valves.
An investigation of excess letdown line leakage on September 15, 1973, lead to an inspection and subsequent repair of valve 1MOV-1299 on Unit 1 (excess letdown system root valvc) on September 26, 1973.
Inspection of the valve disclosed that its dcwnstream seat protruded from the valve body such that if the. valve disc was fully withdrawn from the guides, as allowed by its backseating ring, the disc could catch the " lip" of the seat ring when reinserting.
Four marks on the lip of the down-1 stream seat ring indicated that the disc had caught there during previous valve closings.- Internal damage to the valve consisted of a fine vertical crack at the 12 o' clock position in the upper -i portion of the downstream seat ring.
Two locating pins between
.l the upstream and downstream discs of the split duc valve were found to be slightly bent also and some facial scratches to the down stream disc were evident.
There was no metal loss involved lo in the damage.
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i Attachment B j
Page 1 of 3 w
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Mr. John F. O'L' ry October 29, 1973 N
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Repair of the valva involved rounding the lip of the seat ring to prevent luture hangups of tha disc.
The thin ver-tical crack 'n the downstream seat could not be fully lapped out during the repair.
Accordingly, a manual valve was added to the system downstregm of 1MOV-1299 to back up the root valve.
Valve IMOV-1299 thereby remains effective and operable as a remotely controlled root shutoff valve, but is considered not totally capable of effecting completely tight shutoff without some through-leakage.
At the time, measurements indicated that the location of the backseating ring on the valve stem was too low but this could not be assuredly determined.
If such was the case, this would allow the split discs to fully clear the seat rings when the valve was fully open and backseated.
The tendency for inter-ference to occur between the downstream disc and seat during valve closing could be expected to increase if there was flow through the valve, creating a differential pressure-which could swing the loose hanging disc onto the lip of the seat.
There are six similar 2" Darling valves in each unit at Point Beach Nuclear Plant.
In addition to the above mentioned 1299 valve, valves 270A & B (normally open) are installed er. the reactor coolant pump seal return line.
These valves are, rarely operated in the life of the plant.
Also, valves 598 and 599 on the reactor coolant system drain line are of this type.
These valves are never operated during normal pressurized and pcuer operation.
The sixth,similar valve on each unit is MOV-427 on the normal letdown line.
The function of valve 427 is to close in the event of low pressurizer level and, in closing, cause the closure of the containment isolation valves 200 A, B and C, via an interlock.
None of the Darling valves d'escribed in this re-port are containment isolation valves.
Valve.1MOV-427 was investigated during a Unit 1 shut-down on October 13, 1973, after it was reported that' it would not
,ful.ly close remotely.
Manual manipulation of the valve on Septem -
ber 28, 1973,'had shown that at approximately one-half shut and again just prior to closing, the valve operation became sticky.
Tests were conducted at that time to verify that IMOV-427 was capable of performing its primary function of initiating an iso-lation signal for the letdown line.
The slightest movement of the' valve off its backseat was found to be sufficient to activate the -
-interlocks.and~close the AOV-200 letdown isolation valves.
Measurements indicated that the discs of IMOV-427 when Attachment B Page 2 of 3
Mr. John F. O' Leary October 29, 197;!
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backseated cleared the seat rings and left the valve open to sim(
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lar problems as experienced in 1MOV-1299.
Inspsetion showed no damagetovalveIMOV-427otherthanaslightmarkingoftheuppek i
edge of the seat ring, similar to that found in 1MOV-1299.
closing up the valve, Befos guiding the discs down between the seats.the seat ring edges were roun The " valve open" limig switch was then set for 2-1/4", 5/16" less than the maximum backe seating position of 2-9/16".
ducted satisfactorily.
Valve cycling tmsts were then con-During the same shutdown, valve IMOV-270B was cycled manually with no evidence of stickiness or disc hangup.
completion of repair of 1MOV-427, on October At the 13, 1973, it was concluded from measurements taken, operating experience and teleo phone discussions with the valve manufacturer, that, dimension error could exist with respect to backseat locationsindeed, a I
on the stem.
With these confirmations, it was concluded that all; twelve valves of this type would require investigation on a sche I dule commensurate with the plant operating schedules.
Valves IMOV-1299, electrically limited similarly to IMOV-427.2MOV-1299 and 2MOV-427 will be Valve IMOV-1299 will be completely changed out during a convenient shutdown fol-lowing the receipt of a new valve.
New valve stems with back-seats located so that full opening of the valve will not permit and wil' be fitted in the remaining valves at convenien downs.
The service of the 598, 599 and 270A & B valves is such that Jt is not considered necessary to change the stems of these valves until the next refueling shutdown of each unit.
The nuclear steam supply system supplier has been in-formed about the problems encountered with these valves.
Very truly yours, L-
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o Sol Burstein Senior Vice President cc:
itc. James G. Keppler
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Regional Director Directorate of Regulatory Operations, O,
Region III j
U Attachment B Page 3 of 3
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j Directorate of Regulatory Operations Bulletin 74-1
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dated January 3, 1974 s
Distribution:
Chief, Field Support and Enforcement Branch Deputy Director, RO Assistant Director for Construction and Operation, R0 (3)
Assistant Director for Radiological, Environmental, and Materials Protection, RO Director, Office of Operations Evaluation, RO Assistant for Plans and Programs, RS Director, DL Deputy birector, DL q
Deputy Director for Technical Review, DL Assistant Director for BWR's, DL (3) l Assistant Director for PWR's, DL (3)
Assistant. Director for Operating Reactors, DL (3)
Assistant Director for Environmental Projects, DL (3)
R. F. Fraley, ACRS p_
y Files 1)R Central Files cc: 1.etter addressed to Licensee w/ enc 1 l
N w/o distribution and address list NSIC R. L. Shannon, DTIE (TIC)
Chief, Regulatory News Branch, IS PDR Local PDR e
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