ML20234F137
| ML20234F137 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/01/1987 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Robert Williams PUBLIC SERVICE CO. OF COLORADO |
| References | |
| REF-PT21-87-141-000 PT21-87-141, PT21-87-141-000, NUDOCS 8707080116 | |
| Download: ML20234F137 (2) | |
Text
,F. JUL 1- 1987 In Reply Refer To:
Docket: 50-267 Public Service Company of Colorado ATTN: Robert 0. Williams, Jr.
Vice President, Nuclear Operations P. O. Box 840 Denver, Colorado 80201-0840 Gentlemen:
This forwards, for your information, reports recently received by the Commission under the reporting requirements of 10 CFR Part 21. The attachments 1 through 5 were inadvertently omitted from our letter of June 10, 1987.
Although no response is required to this letter, we shall be pleased to answer any questions which you may have regarding this matter.
Sincerely, c:w ma 3 - w., a J. P. Jnulen 1
' J. E. Gagliardo, Chief Reactor Projects Branch -
Attachments:
- 1. Virginia Electric and Power Company letter dated January 28, 1987
- 2. The Foxboro Company letter dated February 17, 1987
- 3. SMUD letter dated February 10, 1987
- 4. Morrison-Knudsen Company, Inc. letter dated January 13, 1987
- 5. ISOMEDIX letter dated March 30, 1987
- 6. SOR, Inc letter dated April 27, 1987 cc w/ attachments:
Manager, Nuclear Production Division Fort St. Vrain Nuclear Station 16805 WCR 19)
Platteville, Colorado 80651 P. Tomlinson, Manager, Quality e7070B0116 070701 Assurance Division PDR ADocK0500g7 (same address) S Colorado Radiation Control Program Director Colorado Public Uti .ies Commission k
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of Colorado bcc to DMB (IE19) bec distrib. by RIV:
RPB DRSP RRI R. D. Martin, RA l SectionChief(RPB/A) RSB )
Section Chief (RSB/ES) Project Inspector, RPB RPSB D. Weiss, RM/ALF MIS System R. Hall ;
RSTS Operator NRR Project Manager j RIV File I l
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Attachment 1
't YINGINIA ELecrusc AND POWER COMI%NY H arHMOND,VINGIN1A 202 61 W.L.SrsWART * *g ' ,2 P3 i1 -
i v.c. rn. inn wiconi on mon January 28, 1987- I Dr J. Nelson Grace Serial No. 86-753A Regional Administrator N0/RCB:dmk Region Il Docket Nos. 50-338 U. S. Nuclear Regulatory Commission 50-339 i Suite 2900 License Nos. NPF-4 101 Marietta Street, N.W. NPF-7 ,
Atlanta, GA 30323
Dear Dr. Grace:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AFs 2 NEW SERVICE WATER SPRAY SUPPORT SYSTEM FOLLOW UP REPORT On November 12, 1986 Virginia Electric and Power Company reported a potential defect involving a substantial safety hazard at North Anna Power Station Units 1 and 2 in accordance with 10 CFR 21 (Serial No.86-753). In that report, we committed to ultrasonic testing of suspect materials and development of a
. repair / replacement plan.
Ultrasonic testing of the suspect materials has been completed, and the results have been documented in a Non-Conformance Report. Twenty-one steel columns supplied by Rockwell Engineering Company were found to have laminations in the web. Eight of the defective columns were never installed and will not be used
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in the spray array support structure. An action plan for replacing the remaining thirteen defective columns has been developed and is summarized below:
Defective columns will be replaced one at a time by removing the column and the attached footing, temporarily supporting connecting members and piping, installing replacement column and footing, and reattaching ,
connecting ambers and piping. l i
The' replacement plan for each defective column will be reviewed to ensure that injurious stresses are not imparted to adjacent components ;
during the repair process. '
Current plans are to repl' ace defeccive columns prior to placing the new spray array system into operation.
. - a n-w W pj)h"4DDCis 0500g3 3 S
Should you require further information, please contact me.
Very truly yours, l
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, ou~ .
a W. L. Stewart O
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Attachment 2 4
Fo20to, MA, U.S.A. 02035 The Foxboro Comoanv, r
- *"75o Telex 927 002 17 February 1987 United States Nuclear Regulatory Commission Office of Inspection and Enforcement ,
Washington, DC 20555 Attention: Director, Office cf Inspection and Enforcement
Dear Sir:
Subject:
Potential Defect SPEC 200 Current-to-Voltage Cards 2AI-12V and 2Al-13V
~
Please refer to the attached letter sent to nuclear users.
i We do not believe printed wiring assentlies are stored in, unusual,above 1' specification, high humidity conditions in.the nuclear plant. If the off-normal storage condition exists, corrective action has been identified in 'the attached notification. ,
Very truly yours, THE FOXBORO COMPANY Al]. TM Michael J. Berberian, D100/N04-2B \
l Manager, Corporate Quality Assurance pjb I i
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@^^150 PDR PT21 CZr_
ENVF(iXB d 87 PDR l E*
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4 High Moisture Effects on Spec 200 Current-to-Voltage Cards 17 February 1987 Page 2 If these conditions exist, it is recommended that these capacitors. be replaced with Part Number H0110BN.
If additional assistance is rsquired, please contact either of the following individuals:
James T. Kaiper, D872/B52-2K, at (617) 549-6332 or Dana A. Hambleton, D137/N04-2B, at (617) 549-3889 at The Foxboro Company -
Foxboro, MA 02035 Very truly yours, THE FOKBORO COMPANY
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Michael J. Berberian, D100/N04-25 Manager, Corporate Quality Assurance ~
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17 February 1987 Attention:
Dear :
Enference:
Subject:
High Moisture Effects on Spec 200 Current-to-voltage Cards, 2AI-I2V and 2AI-I3V, During long-Tern Storage This letter is to provide advisory notification of an off-normal condition of Spec 200 cards stored in an environment of high moisture without power applied. We believe this kind of environment for storage (in excess of 400C and 95% EE or condensing moisture) would be very unusual in your nuclear plant.-
The above current-to-voltage cards as unpowered shelf sparea can exhibit erratic output operation and insufficient span adjustment when put into
- service.
The high moisture allows excessive leakage in a monolithic ceramic capacitor manufactured by AVI and these were used in the Spec 200 current-to-voltage cards up to August 1983.
The capacitors are easily identified. Their location is shown in Spec 200 MI 2AI-140 Page 10 and 11, and are identified as C1, C3, C6, and C7. The suspect capacitor manufactured by AVE has a bright blue case and the letter A or AYX marked in black.
The conditions for tais erratic operation are:
- 1. Unusual high humidity in storage area
- 2. Date code prior to August 1983 *
- 3. Bright blue, capacitors marked with AVI identifier I
L . .
Attachment 3 Osuun "4" i SACRAMENTO MUNICIPAL UTIUTY DISTRICT C P(#'R Sox 15530. Sacramento CA 95852 1830,(916) 452-3211 AN E(tCh tp f SfSTEM SERVING THE HEART OF CALIFORNIA February 10, 1987 d l0: j'g JEW 87-119 !!V/4:
m J. B. Martin, Regional Administrator Region V Office of Inspection and Enforcement Attn: Document Control Desk i
U. S. Nuclear Regulatory Connission ~
l i 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596 <
l DOCKET NO. 50-312 Rancho Seco Nuclear Generating Station Unit #1 License No. DPR-54 10 CFR 21 REPORT, LIMITORQUE GEARED LIMIT SWITCH ROTORS WARPED
~
Dear Mr. Martin:
In accordance with 10 CFR 21.21(b)(2), the Sacramento Municipal Utility District hereby submits a written report documenting the notification made by '
- Mr. C. Stephenson of the District to Mr, L. Miller of Region V Nuclear Regulatory Commission (NRC) on February 5, 1987 concerning warped geared limit
. switch rotors supplied by Limitorque Corp., Lynchburg, Virginia.
During the motor operated valve (MOV) refurbishment program initiated by IE Bulletin 85-03, seven (7) out of a group of fifty (50) Fibrite (brown color) geared limit switch rotors were discovered to be warped sufficiently to prevent limit switch adjustments. The warped F1brite geared limit switch rotor was detected on January 16, 1987 during the replacement of a rotor on the limit switch gear box. Electrical maintenance personnel installed a new Fibrite rotor onto a limit switch gear box and proceeded to rotate the limit switch rotor with a drill motor during bench testing to ensure engagement of the gears. They observed that the rotor was not making contact with the
" fingers' due to an axial bend in the rotor.
The entire shipment of fifty (50) F1brite limit switch rotors was checked for warpage. Seven (7) of the fifty (50) were warped severely enough to prevent limit switch adjustments. The shipment was purchased under Purchase Order No. RS 90625.
An internal Occurrence Description Report was initiated on January 16, 1987 1 requesting the Plant Review Committee (PRC) to review the warped rotors for i possible 10 CFR 21 deportability. On February 3,1987 the PRC reconnended that ,a 10 CFR 21 Report be submitted to the NRC pursuant to 10 CFR 21.4(d)(1).
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RANCHO SECO NUCLEAR GENERATING STATION C 14440 Twin Cities Road, Herald, CA 95638 9799;(209) 333 2935
_________--__________i___.__.__~ --
.- 3 Mr. Martin February 10, 1987 I
1 l
District maintenance procedures were in place, prior to the discovery of the -
warped rotors, that prevented the installation of a defective component into l
an operating system.
The District considers Limitorque Corporation to be better qualified *to provide the NRC an itemization of those facilities which may be affected by l
this defect.
l If there are any questions concerning this report, please contact Mr. Ron W. Colombo at Rancho Seco Nuclear Generating Station.
Sincerely, ,
I
(
Jo n E. Ward Deputy General Manager, Nuclear cc: Director I&E
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s Attachment 4
. ' CONTRACTORS ENGtNEERS DEVELOPERS hMORRISON KNUDSEN COMPANY,INC.
= = = . '
2?%TafL8'afen*
January 13, 1987 Mr. James Taylor !
USNRC 1717 H Street Washington, D.C. 20555
Dear Mr. Taylor:
Enclosed is supporting documentation concerning a reportable 10CFR, Part 21, condition from our subsidiary, Power Systems Division in Rocky Mount, North -
, , Carolina.
We will forward further information as it becomes available. You may call me at (208) 386-5365 if you desire any further infonnation concerning this subject.
Very truly yours,
.b. b R. D. Kulchak Manager-Quality Assurance RDK/gs Encl.
cc: H. Falter (w/attachs.) i F. Jones l K. Sowder 1
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PDR PT2 EECliORRK I B7 Pop
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\ CMATORS OF ELECTRICAL EC W
\)N POWER SUPPLY SYSTEMS URGENT SENT:
'3 PDWER SYSTEM.S a - - uuosanoivmo PT,.EAS5 Mp3?O IMMEDIATELY REC'D.: I
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==,wsererr.= hN \ L DATE: i
@/.gJ,'/.'$%* d ""'" TIME-f l
g January 12, 1987 TELECOPY .
DATE:
Morrison-Knudsen Company, Inc.-
COMPANY: !
(
)
ADDRESS:
CITY & STATE:
Ron Kulchak (Quality)
ATTENTION:
REFERENCE:
Reportable Defect Report 10CFR21-0033 i TELECOPY NO.:
MESSAGE Please refer to attached memo and report concernina Square D Relays.
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pgoy; Harry W. Falter, Principal Enginmar -
PowtR sysnus A MORRISON KhuD$EN DMSION PAGES, INCLUDING THE COVIR SHEET.
TRANSMITTED HEREWITH ARE _ FBI '
IF YOU DO NOT RECEIVE ALL PAGES LISTED, PLEASE CALL (919) 077 2720, *
- I,$XTENSION NOS. 210 OR 212 FOR VERIFICATION.7 N .LW A>OM N33CnNWOSIMMOW 6E:9T 46, 2T WI A.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ ____A
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S/N M-E-0-0004 MORRISON-KNUDSEN COMPANY, INC.
INTER. OFFICE CORRESPONDENCE
- " January 12,1987 Ron Kulchak " " Harry W. Falter
- ^"'*
Boise *"f5I)-Rocky Moun't, NC C-2726 MK/PSD Memo S/N M-E-0001 (1/5/87)
Reportable Defect Report 10CFR21-0033 I have reviewed the Square D Company report attached to MK/PSD Report 10CFR21-0033, and I conclude that the defect is reportable.
Review my report and if you agree, notify the NRC within the required time period in accordance with the QAM. -
Pleas,e acknowledge receipt of this transmittal and advise I
your action. ,
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.MO.RRISON-KNUD8EN nm= - COMPANY, INC0
! l REPORT 10CFR21-0033
. I January 12, 1987 j 1
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Reportable 10CFR-21 l
_ COMPONENT : Square D Company General Purpose Relay Class 8501 Type KPD-13 130 VDC service 1 APPLICATION: Control circuits for diesel generators used as emergene power supplies for Nuclear Power
- Plants furn shed by Bruce GM Diesel, Inc. or Power Systems Division of Morrison-Knudsen j Company, Inc.
DEFECT: In an application, the 130 VDC relay was energized for a long period of time. This ~
period is estimated to be approximately 10 years. When the relay was de-energized, it failed to drop out and remained in its energized state.
CAUSE Square D Company conducted tests which iden- !
tified residual magnetism to be the cause.
The probable cause of the residual magnetism was probably due to the DC device being 4 constantly energized for such a long period.
DISCUSSION: Bruce GM Diesel and Power Systems Division ,
used normally energized relays to monitor individual fuses in the control system.
Should a fuse fail, its relay would drop out and activate an alarm.
There were a few instances where the emer-gency start relay was contractually speci-find to be in its normally energized state where the relay would complete the amergency start signal when it dropped out.
If a fuse blew in a critical circuit, a relay held in by residual magnetish would fail to send the signal to the alarm which was meant to alert an operator of the-fuse failure with the result that the circuit would not func-tion when called upon. Likewise, if the relay in the start circuit were to hang up due to residual magnetism, the start signal would not be. transmitted to the circuitry.
E*d 'D'N IW A>OM M35CnN>t-NOSIdWOW 07:9T 48. 21 WI
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'MO.RRISO.N-KNUDSEN
. m ww mee. CCMPANY, INC.
REPORT 10CFR21-0033 January 12, 1987 .
Page Two .
\
CORRECTIVE ACTION:
There is no specific test documentation to p j
provide the exact length of time beforeIt is residual magnetism becomes a factor.
j recommended that the normally energized f relays be inspected or replaced during overy I fuel outage. Inspection should be documented 2 and maintained to determine the length of time residual magnetism becomes a factor. , g i
5
, l Replacement with the Square D Class 8501, I type XUD does not appaar feasible because of physical differences that require consider- ;
able redesign. :
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CONCLUSION:
The defect is determined to be reportable on the basis that if a blown fuse is not slammed, the operator would not be alerted and criticalAlso, control in thecircuit couldwhere few cases be the isolated.
relay is normally energized for the emergency start signal, it would not transmit the start signal if residual magnetism kept the relay energized. The diesel generator, therefore, would f ail to perform its safety function.
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- / __ U_ _ _m E N33 Harry W. Falter, P.E.
IN
- N.C. License No. - 7022 LLIA ne.asion',
ATTACHMENTS:
Square D Letter January 7, 1987 Square D Letter September December 19, 1986 31, 1986 TVA Letter Relay Comparison
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INDUSTRIAL CONTROL RELAYS ,600 VOLT TYPE X , C1.h*M / 8501 / ' ~
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UTIUTY AU11UARY RELAY For special 1kadons in the electrie udfiry industry, the 7)pe X " Relay is evtilable. This special was4on offers the aw e Utility Aux! ""g* 88'8 h aame features as the standard de opersted eclay plus:
- 1. 4, 8 ami 12 pole, versions, wkh up to 12 poles normally open or pese closed, s.n. a.c. ine
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fueled titi plant appikadons where reliable performance, a pure 63 power p . and up to 12 usable poles an required. . See xuoo.isoo .
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Attachment 5 E..- ' V.o' p
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isommoix g i l March 30, 1987 ', I Mr. Gary G. Zech, Chief Vendor Program Branch Office of Inspection and Enforcement ' U.S. Nuclear Regulatory Connission-Washington, D.C. 20555
Dear Mr. Zech:
As you may know, Isomedix provides gamma radiation services related to the { qualification of nuclear reactor safety-related equipment. During the past I few months, the nuclear equipment qualification program af Isomedix has been i under close review by both our customers (equipment manufacturers and test , labs) and utility end users. The scope of this review has included our past and present operating procedures and controls as well as current'and 4 historical test records. Based upon our review and the recommendations of our I customers, we have instituted some changes to operating procedures and documentation methods. One item which was noted concerns the measurement tolerance associated with the dose and dose rate values certified by Isomedix on our test reports. Dur-ing a period of the late 1970's, a value of i 3% was stated as the Eccuracy of the dose measurement. This- value was based upon literature published regard-ing the Harwell Red 4034 Perspex dosimeter, the system primarily used to moni-tor these irradiations. However, the reporting of this tolerance value ceased by the early 1980's, and from that time until recently our test reports have not stated a value for the measurement tolerance associated with reported dose
, or dose rate values.
More recently, our Technical Department studied the Harwell Red 4034 dosimetry system and estimated the tolerance associated with this system to be 8% (4% precision, 4% bias) at the 95% confidence level. This value has been stated in our Standard Dosimetry Procedures since 1984, and is currently being quoted to customers when we are requested to bid on a job as well as listed on cur-rent test reports. However, the magnitude of this value has become a cause of concern to one of our customers and is the reason that this report is written. Our survey of previous test records included the test files of the Automatic Switch Company of Florham Park, NJ. This customer has used our radiation ser-vices for three equipment qualification testing programs involving solenoid valves and three involving pressure / temperature switches. Our evaluation of test data for these programs was reported to ASCO, and they have requested that we report our findings to your. agency under 10CFR21. Their concerns are O I( as follows: _ T21
" ( 7 veni oiusaOENVIh ISOMEDIX INC.
)O a CORPORATE OfflCE$
- 11 APOLLO DRIVE WHIPPANY, NEW JERSEY 07981 * (201) 887-4700
- FAX 8871476 . TELEX 317361
[ Mr. Gary G. Zech March 30, 1987 2
- 1) That the minimum doses stated in the test reports for ASCO tests cannot be assured due to the negative measurement tolerance associated wit 5 each dose measurement. '. ;
- 2) That the maximum dose rates stated in the test reports cannot'be assured due to the positive measurement tolerance associated with each measurement.
Note: ASCO also voiced concerns regarding dose rate uniformity, test sample temperature, and test records. These subjects were listed by Mr. Steve Alexander of your staff during his April,1985 inspection, and were addressed in our response dated June 26, 1985. The tests in question were performed ' between 1978 and 1984, and as such do not reflect the program revisions which were instituted in response to the 1985 E.Q. inspection. . With respect to the question of tolerance for dose and dose rate measurements, our report to ASCO listed a value of i 2% for the associated time measure-ments, based strictly upon the test tolerance for calibration of timers. Fol-lowing the issuance of this report, a review of calibration records for the l past 5 years was performed for the timers in question. These records show that, in fact, the % error associated with these timer measurements has aver-aged less than 0.7%. Based upon this result, the total tolerance associated with Isomedix dose rate measurements (dose / time) is estimated to be i 8.6%, while the tolerance associated with total dose measurements (dose rate x time) is estimated to be i 9.6%.
~
During the time of the April 1985 E.Q. inspection, the" subject of test tolerance was discussed with Mr. Alexander. Based upon our conversations at that time, it was our understanding that the 10% margins applied to test doses, as prescribed by IEEE 323, were designed to compensate for errors asso-ciated with the measurement process. As the inspection report shows, this subject was not listed as a deficiency or even a connent by the inspector. For this reason we had not taken action with regard to specifying measurement tolerances in our reports. Since our estimate of total dose tolerance is within 10%, it is our belief that the ' test requirements for minimum dose have been met. In the case of the dose rate measurements, the tolerance must be considered in regard to dose rate limitations imposed by the purchase order. The ASCO tests were typically performed at dose rates well below the purchase order limita-tions, so that a potential increase of s 10% will not cause a deviation. In > one case, however, test records show a dose rate of 3.97 Mrads/ hour, whereas the P.O. states the rate.to be below 4 Mrads/ hour. There most certainly have been other instances where the test dose rate was within 10% of the specified maximum value, and in these cases the potential exists for deviations from specifications. The degree of deviation would not exceed 10%, however, so the effect of this upon a qualification test is Itkely not significant. As stated i above, this report is sent at the request of our customer, due to their con-cerns over the qualification status of their products. While we do not feel that the situation is critical, we wish to bring these facts to the attention of NRC in order to receive a determination from you regarding them. 1 sooMaDIX INC. conmwr owers . n Arou.o omvE. wHiPPAnv. NEW JERSEY 07981 e GD1) m7 4700 j
a,. . o Mr. Gary G. Zech March 30, 1987
., 3 Obviously, any effects upon the ASCO tests will also affect testi performed for other customers, since the same systems were used to performithe work. We would therefore appreciate hearing from you regarding this matter in order to guide our planning in this area and to assist our customers whose projects may be affected. .
Sincerely yours,. . ISOMEDIX INC. M/V f^- . Steven R. Thompson Quality Assurance Manager SRT:js cc: G. Dietz ' W. Owens J. Young L. Olsen, ASCO IsoMEDIX INC. CORPORATT OFFCfs e 11 APOLLO DRIVE. WHIPPANY, NEW JEASEY 07081
- GD1) 574700
Ga
, , , , Attachment 6' -
r- ~. n n i x _., i g April 27,1987 To: All Nuclear Power Plant Qualified Pressure Switch Users Re: Preliminary 10CFR PART 21 Notice SOR is investigating a potential problem with our gauge pressure switches. We direct your attention to NRC Information Notice (N 87-16. This notice addresses the SOR Series 1, 4, 5, 6, 8, 9,12 and 54 switches. h We have discovered several switches at Davis-Besse Nuclear Generating Station which have contained a gas bubble format!on betweer the diaphragm layers within the sensing element of the switches. The cause of the problem . I has not yet been isolated. The use of 316 stainless steel diaphragms has not completely eliminated the bubble formation as previously concluded in l IN87-16. An indicator of a bubble formation is the increase in deadband of the pressure switch (i.e.: the rise of the increasing set point anu/or the fall of ! the decrea' sing set point). The formation of the bubble may cause tne set I point to shift outside the technical specification limits. l SOR continues to investigate the phenomena. For any questions, please ! contact the factory at (913) 764-2630, and ask for Nuclear Sales. Regards: s
- .I y<s.: 1. .,
James R. Johnson Vice President - General Manager 042787-07/ES132 l l 1 i l -- f M M 6/04* 7 I S ADOCK 05000346 a l PDR l
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