ML20024D240

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Forwards Addl Info Re Testing & Operation of Control Rod Drive Mechanisms.Tech Specs Will Be Revised to Require Biweekly Rod Drop Test,Temps Will Be Monitored Periodically & Temp Monitor Devices Will Be Installed
ML20024D240
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 07/18/1983
From: Lee O
PUBLIC SERVICE CO. OF COLORADO
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
P-83239, NUDOCS 8308030358
Download: ML20024D240 (59)
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Text

{{#Wiki_filter:_ l o ,) 1 1 go PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 840 DENVER. COLORADO 80201 July 18, 1983 OSCAR R.1.EE Fort St. Vrain Unit No. 1 v cc m.,ocar P-83239 Mr. John T. Collins, Regional Administrator % %@]M]3 Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement JA. 2 51983 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012 d DOCi'.ET NO: 50-267

SUBJECT:

Fort St. Vrain CRDM Temperature

REFERENCES:

1) 0.R. Lee (PSC) Letter to l

J.T. Collins (NRC) dtd 4/15/83 (P-83132)

2) W. A. Graul, " Fort St. Vrain Control Rod Drive Mechanism -

Thermal Effects"; GA Letter GP-1014, dtd 6/9/81

3) Fort St. Vrain Technical Specification SR-5.1.1
4) G.L. Madsen (NRC) Letter to 0.R. Lee (PSC) dtd 5/16/83 (G-83194)

Dear Mr. Collins:

PSC has reviewed your letter of May 16, 1983 (reference 4) requesting additional information regarding testing and operation of the Fort St. Vrain (FSV) Control Rod Drive Mechanisms (CRDMs). The four commitment items requested in reference 4 are responded to in this letter, along with PSC's proposal for the long-term operation and monitoring of the CRDMs. b 0 (b Il 8308030358 830718 \\ PDR ADOCK 05000267 l P-PDR

T 83239 Page 2 { Six of the 37 regions in the FSV reactor core are currently equipp d with sensors to monitor CRDM' temperatures (Regions 4, 5, 15, 31, 34, and 35). Each of the six CRDMs has three Resistance Temperature Devices (RTDs) located as follows: on the CRDM's closure plate (Sensor #1), the orifice valve motor plate (Sensor #2), and on the CRD motor (Sensor #3). These RTDs are connected to a bridge-type instrument producing a millivolt signal, which can then be converted to a temperature reading. Figure #1 shows the mounting location of the three RTDs and Figure #2 shows, in more detail, the RTD location , on the shim motor of a CRD motor assembly (Sensor #3). The RTDs are installed per a PSC Request for Test Procedure (Attachment #1), which specifies that similar devices be installed on the remaining CRDMs as they become accessible. A FSV Change Notice is being prepared by PSC's Engineering staff to install equipment so that all 37 regions will be equipped with CRDMs that have temperature monitoring capabilities. Since it is only practical to install these devices during plant

outages, no specific time commitment for the installation is feasible.

It should be noted, however, that six more CRDMs are planned to have RTDs installed and be placed into service during the next refueling outage (Regions 3,13,18, 22, 29 and 33). A similar schedule is planned for subsequent refueling outeges, and any CRDMs replaced between refueling outages will also be equipped with temperature monitoring devices. The detailed analysis prepored by GA Technologies Inc. submitted to the NRC in PSC's April 15, 1983 letter (reference 1) provided information regarding the thermal expusion and tolerance buildup i effects cn the CRDMs at a temperatura of 280"F (reference 2). This analysis evaluated all components in a CRDM assembly for worst case tolerance conditions which could inhibit a control rod scram. A temperature approximately 20" higher than the anticipateo CRD motor temcerature at 100% power (discussed later in this letter) was utilized for the GA analysis. Worst case tolerance cxbinations at 280'F resulted in probabilities of the gears faming that were less than one in one million for one CRDN and less than one in one billion for two CRDMs failing to scram. PSC feels this evaluation provides adequate justification that the scram capability of the CRDMs will not be jeopardized by gear jaming at high ambient temperatures. The brake assembly is an electromagnetic friction device which is spring-released when de-energized. When the brake is energized and applied, the control rods are retained in a fixed position. The d.c. brake power must be maintained if the rods are to be held steady in any position other than fully inserted; thus the system is fail safe. PSC's Engineering staff has evaluated the brake assembly and concludes that there are no components which could cause the brake to fail to release due to high ambient temperatures. Also, rod drop tests (reference 3) serve to verify that the brake assemblies are capable of releasing properly. GA Technologies Inc. performed calculations to predict the maximum CRD motor temperature at 100% power conditions (Attachment #2). This =~" T' S-- r >fm W 9

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P-83239 Page 3 e o analysis pre'dicted a maximum CRD m'otor temperature of 260*F if the orifice valve is fully closed. At a 10% open orifice valve position, a maximum temperature of~ 250*F is predicted. A'10% orifice valve position is generally expected to be~ the least: open position at: 100%- power. Tests were conducted on November 7, 1981 to determine the CRD = motor' temperatures with the plant operating at 100% power. The maximum CRD motor temperature recorded in the RT-485 "B" test was 218*F,-which occurred in Region 5. Presently, per FSV Technical Specification SR5.1.1 (reference 3), PSC is conducting two different " rod drop" tests. To ensure that a scram time of less than 160 seconds can be met, a yearly rod drop test is conducted (FSV Technical. Specification SRS.I.la) where all 37 control rod pairs are individually scrammed from the full out to full in _ positions, and the scram times are measured. To verify the operability of the position indicators, motion indicators, brake mechanisms, and cable slack indicators, a monthly rod drop test (FSV Technical Specification SR5.1.lb) is conducted. In this monthly rod drop test, (currently being run on a bi-weekly basis), the brake assemblies are de-energized, the contrci rods are dropped approximately 6 inches, and the time and distance are measured. Tne time a ;d distance data is then extrapola ted to inaure that the maximum of 160 second scram time can be met. It is PSC's opinion that the rod drop tests provide adequato verification that all control rod pairs can be inserted within the specified time parameters such that safe reactivity control of the reactor is always mair.tained. Regarding the temperature limit specified in the data collection surveillance, S R-RE-4-W provided with Reference 1, the 200*F temperature limit in step 5.2.2 of this surveillance was intended to enco:npass the upper temperature limit for all instrumented locations on ' a CPDM. The temperature surveillance is normally run when the Reactor Power level is 50% or greater, or the core differential pressure is 3 psid or greater. This surveillance is currently l performed monthly in conjunction with the rod drop test (reference j_ 3). The temperature surveillance will be revised so that 1) the FSV Station Manager will be advised if the CRD motor temperature reaches 250 F and/or the upper helium environment temperature reaches 300*F.

2) In the event a CRD motor temperatu're is found to be above 215*F during the monthly surveillance, the frequency of the temperature surveillance test on the CRDMs will be increased to weekly until the temperature returns to less than 215*F.

PSC's Engineering staff had previously detennined the limiting component in a CRD motor assembly was the electrical cable, which was j-rated at 125 C (257*F) per drawings provided with reference 1. Subsequent discussions -with the motor manu facturer, Varo Inc. Electrokinetics Division of Santa Barbara, Ca., revealed that a higher-than-specified grade of wire was used and that the lead wire insulation is, therefore, rated for continuous operation at 150 C L (302*F) ambient temperature (Attachment 3). Hence, the component l r i i i

P-83239 Page 4 / that limits thn CRD motor ttmperature is tha motor's Class H insulation, which is de-rated to an ambient temperature of 133.5 C (272*F). This de-rating accounts for motor temperature rise, frictional torque increase, and winding life expectancy. After reviewing these analyses and test results, PSC concludes that Fort St. Vrain will not experience the inability of one or more control rod pairs to enter the core for automatic reactor shutdown due to CRDM temperature conditions. Per the telephone conversation between Mr. P. Wagner (NRC) and Mr. J.R. Reesy (PSC) on July 7,1983, the following commitments will be implemented upon receiving concurrence from the NRC: 1. Revise Technical specification SR 5.1.1 b such that the rod drop test will be required bi-weekly on each CRDM that has withdrawn control rods. 2. Continue to monitor CRDM temperatures periodically. This will be included in the " Basis" section of Technical Specification SR 5.1.1 b. 3. Revise the CPDM temperature surveillance, SR-SE-4-U to recuire Station Marager notification if the CRD motor tecperatum exceeds 250'f. 4. Install temp 3ra tttre monitoring dev1cas on all CRDMs via a FSV Change Notice at describea carlier. If voa have any questions, please contact Mr. J.R. Reesy at (303) 571-8406. Very truly yours, adn

0. R. Lee, Vice President Electric Production ORL/DYA:pa Enclosures

P-83239 Page 5 se i List of Figures 1. Resistance temperature device placement location; PSC-FSV Request for Test Procedure T-187 pg. 58 2. Control Rod Drive Motor Assembly; PSC-FSV drawing D-1201-200. 4 Attachments 1. PSC-FSV Request for Test Procedure T-187. '2. W.A.

Graul,

" Transmittal of the Review of the Control Rod Drive Temperature Data", GA Letter GP-1283, December 22, 1981. 3. Lead Wire Drawing; Varo Inc. Electrokinetics Division, Dwg. No. 78667. t Y a I a h l i-l ,--,n...nc, ,----n-,------.., ,,-..w--,, -.-,rc

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter ) ) Public Service Company of Colorado Docket No. 50-267 Fort St. Vrain Unit No.1 AFFIDAVIT 0. R. Lee, being duly sworn, hereby deposes and says that he is Vice President of Public Service Company of Colorado; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached response to the NRC Letter from G.L. Madsen to 0.R. Lee dated May 16, 1983 (G-83194); that ha is familiar with the content therecf; and that the matters set forth therein are true and correct to the test of his knowledoe, information and be. lief. O. R. i.ee Vice President STATE OF cme ) ) COUNTY OF M ) Subscribed and sworn to before me, a Notary Public in and for on this /'7 day of N , 1983. e t Notary Public yo.tL L //3 WM QL.Is ,u) fok33 My commission expires O/4d /7 , 1983.

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Test Ref. No. T-187 Syst. Ref. No. 12 Page SE of 5 4 SENSOR INSTALLATION PROCEDURE 1. Place CRD in ESW #1, and lower control rods sufficiently to reduce radiation levels in the inspection window area just below the primary seal. - 2. Remove inspection windows after lifting CRD and setting on work stand. 3. Remove safety wire and bolts to allow lifting of the CRD motor and pulley assembly (-200 assy). i 4. Insta11' ambient temperature sensor per sketch, sheet 58. 5. Install (cement in place) the surface temperature sensors per sketch sheet 58 this RT. 6. Gather the lead vires together and route them upward toward the connectors at the top of the -200 assy. Take care to insure that these wires cannot interfere wit 5 tne mecnanisms and equionent in this area. 7. Connect sensor wiring to spare terminals in the power cable connector. Make connections per sheet 5C. 8. Reinstall. the -200 assy, install and torque bolts, and re-safety wire. 9. Replace access windows and return CRD to ESW. Pull rods to full retract in preparation for handling with the ATC.

10. The thermocouples used for secondary closure and missile plate temperature measurements are located per sheet 58.

Route leads over to handrail around top head on northwest side.

11. These T/Cs to be glued down after closure and missile plates are reinstalled.

Cover all T/Cs (except ambient air) with a small piece of insulation material.

12. After all wiring is complete perform a calibration procedure on all sensors and linear bridges.

l f t

a.' R ; e -~ v - - o .,,,, j m e ~-:c-GENWIAL ATOtsC COtePANY P.o. box 81608 SAN OIEOo, CALIFORNIA 92138 (714) 45*A000 December 22, 1981 GP-1283 Mr. H. L. Brey, Manager Nuclear Engine

  • ring Division Public Service Company of Colorado 12015 East 46th Avenue, Suite 440 Denver, CO 80239

Subject:

Transmittal of the Review of the Control Rod Drive Motor Temperature Data

References:

PSC P.O. N-3398 GP-1032

Dear Mr. Drey:

CAC has completed its review of the Control Rod Drive (CRD) Motor Temperature data taken during the rise-to-power / fluctuation testing. A copy of GAC memorandun SAB:144:J7DB:81, which documents this review, is enclosed. All available data were used to predict CRD motor temperatures at 1005 power conditions. This prediction, shown in Figure 1 of the enclosed memorandum, indicates that the maximum CRD motor temperature expected is 2600F. This temperature occurs only if the orifice valve is fully closed. At 10% open, as would be expected to be the least open posi-l tion, a maximum CRD motor temperature of 2500F is predicted. These temperatures, while higher than those used to qualify the CRD assembly, are within the acceptable temperature ranges based on the ratings of the components in the assembly. As has been previously noted, the components are capable of operating up to 2500F to 2750F. Other plots of these data are included using different dimensionless temperature ratios to further examine the behavior of these data. These data correlate well for each individual region. However, when data for all regions are combined, the correlation is not clear. In addition to the various correlations, the raw data and dimensionless temperature ratios are included in the memorandum. This will allow you j to perform any additional analysis you believe is needed. 7 M k h& r va c% ~ A T TACMMENT 2

/' GP-1283 pags 2 e In general, these data correlate well for a given penetration with the various ratios used in the analysis. However, these data for different peaetrations do not correlate together. This lack of correlation may be indicative that a penetration other than one of the instrumented penetrations may have a higher helium leakage and higher CRD motor temperature than measured. GAC recommends PSC continue to monitor the CRD motor temperatures and instrument additional drives. Should you have any questions, please contact Gary Hein at (714) 455-2645. Very,truly yours, /s / ^' L L'};. Lii v L' William A. Graul, Manager Fort St. Vrain Project s e f d 1 o e i r, -w, -7,- -n 4

e o.3 tons Attachmtnt to GP-1283 l / IN REPLY FROV. J. V. el Bene /J. F. Follin REFER TO SAB:144:JVDB:81 To G. L. Hein DATE December 10, 1981 SUBJECT Correlation of FSV Control Rod Calculation File Drive Motor Temperatures SA381002 1. Del Bene and Follin, " Correlation of FSV Control Rod Drive Motor Temperaturos," GA Memo SAB:066:JVDB:81 dated June 4, 1981. 2. Young, K. A., " Orifice Calibration (SUT B-4, Part 3)," CA-D15527, July 1979. 3. Del 3ene, J. V., " Additional Thermal Analysis of the FSV Control Rod Drive Penetration," GA Memo SAB:JVDB:07:78, dated February 2, 1978.

SUMMARY

ANDRESULp Control red drive (CRD) penetrations R-4, E-5, R-34, R-35, and R-36 are instrumented with thermocouples to' measure several temperatures within the psnetration including the CRD motor temperature. During time periods from July 1979 to April 1981, data were taken up to 80% reactor power. The correlation of these data is reported in Ref.1. This memo reports the correlation of several data points taken during November 1981 at reactor powers from 75% to 100% with the data of Ref.1. As discussed in Ref.1, the data are correlated as: J. i T E CRD Motor C.W. orif " #' E Core Inlet C.W. orif + 4fL/D [ ~ where T is the liner cooling water temperature and is taken as 100*F, C.W. K is the flow control valve loss coefficient which is related to the percent of orifice valve opening (Ref. 2), and l 4fL/D is the core frictional loss which is taken as 19. l l The square root term on the right hand side of the above equation is proportional l to the leakage flow through the control rod drive penetration (Ref. 1). l

The correlation of the data in this manner is shown in Figures -6 for each individual region and in Figure 7 for all of the regions taken together. In general, the data correlate well for a given penetration; however, the data for different penetrations do not correlate together. An examination of the most recent data points (see Tables 1-5) fall within the scatter of the previous data. All the data were used to predict CRD motor temperatures at 100% reactor power. This final result is shown in Figure 1 in a plot of CRD motor tempera-ture versus fraction of orfice valve opening. The fixed variables in this plot are a core inlet temperature of 750*F and a core pressure drop of 5.0 psid (conditions representative of 100% reactor power). Curves are shown for each region based on a best fit curve through the data for that region. The curve labeled "ALL" is based on a curve that envelopes all of the data. This curve represents a conservative prediction of the CRD motor temperature at 100% reactor power at least for the given regions. It is possible that a region other than the five instrumented CRD regions has a higher helium - leakage and a higher CRD motor temperature, , Other plots of the data were made with different dimensionless tempera-ture ratios to further examine the behavior of the data. These tempera-ture ratios included: The CRD motor temperature with the orifice valve motor plate temperature. The secondary cover plate temperature with the CRD motor temperature, and The orifice valve motor plate temperature with the core inlet temperature. Typically for these different plots the data correlate well for each individual region. However, when all the data for the five regions are plotted together, there exists considerable differences in the data from region to region. The raw data and the reduced data are tabulated for each of the regions in Tables 1-5 for reference purposes. ANALYSIS As previously stated, the relation T ~ CRD Motor C.W. l orif Core K D f TCore Inlet C.W. orif + ~

l is the basis for correlating the raw data since it relates the CRD motor temperature to measurable quantities. The core inlet helium temperature and the PCRV cooling water temperature represent the maximum and minimum temperatures, respectively, for the CRD motor temperature. These two limiting temperatures are therefore used to define a non-dimensional temperature ratio for the CRD motor temperature. As shown in Ref. 1, the helita leakage flow into the penetration base on a simplified analysis is proportional to the following group of measurable quantities ~ g orif l 1eakage

  • core Kodf*19

~ j where 4fL/D has been taken as 19. This square root term is called the helium flow leakage parameter. i Figures 2-6 show plots of the non-dimensional CRD motor temperature versus the helium flow leakage parameu r for each of the five instrumented CRD penetrations. Figure 7 shows the s e e plot with the data from all regions plotted together. The straight Unes through the data points for the individual region plots represent the best fit straight lines. The straight line drawn in Figure 7 envelopes all the data. The lines are replotted together in Figure 8 for comparison. All lines have approximately the same slope (%.5 - 0.6) except for R-36 which has a slope of %.10. No explanation is known for the steeper slope for R-36. An equation for calculating the CRD motor temperatures at 1001k reactor power (or any reactor operating condition) is obtained by utilizing the straight lines drawn in the figures. These lines relate analytically the dimensionless CRD motor temperature to the leakage flow parameter. An i equation from Ref. 1 is used to express the orifice loss coefficient Kori'# as a function of the fraction of orifice valve opened. Combining these two equations and rearranging, one can relate the CRD motor temperature tc the orifice valve position, the core pressure drop and the core inlet t l temperature. This method was used to construct Figure 1. Figures 9-13 attempt to correlate the orifice valve motor plate temperature with the CRD motor temperature. The data are plotted as: .g 00 K T CRD Motor orgf y, g l T ~1

  • 1 OYM Plate orif e

i

s 4, From a thermal point this dimensionless temperature ratio should be constant and independent of the helium leakage parameter. In any case, the tempera-ture ratio should be less than unity. Except for region R-36 the data correlate well for each separate region. This indicates consistency at least among the orifice valve motor plate temperatures and the CRD motor temperatures. A review of the raw data for R-36 indicates that many of the orifice valve motor plate temperatures are not consistent with other measured temperatures in R-36. Figure 14 shows the data for all five regions plotted simultaneously with the CRD motor temperature and the orifice valve motor temperature as the dimensionless temperature. Figure 15 shows the same plot using the straight lines from the separate region plots of Figures 9-13. The reason for the separation of the data from region to region is not known. Possibly, parametric studies with the thermal model (Ref. 3) would show reasons for data separation. Figures 16-20 attempt to correlate the CRD motor temperature with the secondary cover plate temperature as: T2nd cover - Tamb orif E T -T

  • ** 19
  • K CRD h tor ab orif Again, heat transfer theory says that the temperature ratio should be constant.

(In these plots the ambient air temperature is used for the lower reference temperature rather than the liner cooling water tempera-ture of 100*F. At the location of the secondary cover plate the ambient air dominates more as the heat sink rather than the liner ecoling. Plots were made using both Tamb and 100*F (T.TC w ) as the lower reference tempera-ture. The data correlated better using amb as the lower reference i temperature.) ( If the above correlation were successful, the secondary cover plate temperature could be measured for each penetration and the CRD motor temperature could then be deduced from the correlation. Figures 16-20 show that the data for each region correlate reasonably well. However, when all the data for the five regions are plotted together (Figure 21), they do not correlate well as a group. 1 ~ __.. _, _ -

.s. Figures 22-26 are plots correlating the orifice valve motor plate temperature to the core inlet temperature. These plots are similar to Figures 2-6 for correlating the CRD motor temperature. Again, the data for the individual regions correlate well; however, when the data for the five regions are plotted simultaneous (Figure 26), there is significant differences among the regions. Figure 13 and an examination of the measured temperatures for the orifice valve motor plate for R36 (Table 5) show that the lower grouping of data for R36 in Figures 26 and 27 are suspect. The raw data and the calculated temperature ratios and leakage parameter for all data points are given in Tables 1-5. These tables are included for reference purposes and for checking where individual data points lie on the various data plots. I JVDB:se cc: FSV Data File RCB i l l l l

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