ML20069G580
| ML20069G580 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/22/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8303280045 | |
| Download: ML20069G580 (9) | |
Text
{{#Wiki_filter:, TENNESSEE VALLEY AUTHORITY CH ATTANOOGA.,TENN ESSEE 37401 400 Chestnut Street Tower II March 22, 1983 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Ms. Adensam:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 Please refer to a letter from R. L. Tedesco to H. G. Parris dated January 25, 1982 which transmitted a Franklin Resear-ch Center request for additional information on environmental qualification of equipment for the Sequoyah units 1 and 2. Responses to item A of the request were previously submitted letters from M. R. Wisenburg to you dated April 7, 1982 and from me to C. J. Crane, of the Franklin Research Center, dated July 16, 1982. In response to part of item B of their request, we are providing equipment qualification sheets (EQS) and supporting qualification documentation on acoustic monitors for PORV and SV position indication (TMI action plan, item II.D.3). The test procedures and results are documented in Technology for Energy Corporation (TEC) reports 517-TR-01, appendix H, 517-TR-02, appendix I, and 517-TR-03, revision 2, including appendices A, B, C, D, E, and F. The NRC may obtain this information directly by contacting TEC. TEC's address is One Energy Center, Pellissippi Parkway, Knoxville, Tennessee 37922. The response to the remainder of equipment qualification documentation for the TMI action plan equipment identified by item B of the Franklin Research request will be submitted along with TVA's response to the 10 CFR 50.49 final rule dated January 21, 1983 The final rule requires each holder of an operating license to identify by May 20, 1983 the electric equipment important to safety which is already qualified and to submit a schedule for either the environmental qualification or for the replacement of the remaining electric equipment important to safety. [h O f P An Equal Opportunity Employer s
-2 Director of Nuclear Reactor Regulation March 22, 1983 If you have any questions, please get in touch with K. P. Parr at FTS 858-2685. Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Sworn o an subsce for me this ay of ( 983 2Arla yC Expires Yflk // Enclosure oc (Enclosure): l U.S. Nuclear Regulatory Commission Region II Attention: Mr. J. P. O'Reilly, Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30303 Mr. Cyril J. Crane Franklin Research Center The Parkway at Twentieth Street Philadelphia, Pennsylvania 19103
I q . See-Appendtr I-I ' f (,__ 1 _ l "' isi m n R I R R EQS flo. $0NFFR1064 7 e-Jo-tra / [_ [/' S.,.ds.;r$uM TVA 10 No: See Appendix I w,;..,..,.4 n.,./).$_. &3o42k,/.,_/ / / / fyEnUIPMENTGUALIFICATIONSHEET(EOS}M3) lianu acturer and Model Number See Aoperdix I Verification of Table Information, (Table _See Appendix I) X _ Equipment Type - The equipment has been ide'ntified as per TVA 1&-number EsTgaations (e.d., MOV, SOV, etc. ). X Location - The location har. been identified (E.G., Inside Pri.cary Containment, Annulus, Individually Cooled Rooms, General Spac'es,- or area affected by HELB outside primary contain=cnt). Ccmoor.ent-AuniqueTVAIDnumberharbeenassigned(e.g.,IqSV-68-303). y X Function - A functional"descriptTon'o^f the component has been given (e.g., Steam Gencrator Blowds.vn). X Contract do., Manufacturer, and tiodel No. - The contract number, manufacturer, and model number has bcon given. X Abnormal or Accident Environment - All abnormal. or accident environmental cor.ditTcas applicable to tr.is equipuent.have been identified either in tables or by references to figures froa tables. y Environment to Which Qualified - Tha environment to which the equipment nas been qualified is acdressed in cither the tables or the environmental analysis attached. X Categerv - A category of a, b, c, or d has been defined for the equipment. X Operation and Accuracy Recuired and Camonttrated - The operation and accuracy required ond demonstrated have been cefined. ~ Qualification Status (c!'ec!: if acclicable, MA if not) Qualified Life 7 years X Qualification Report and ththod - A qualificatio1 report and the method of qualif'ication nas Man idritified. X Environmntal Analysis - An environmsntal analysis has been done, attached to the ETS, anc indes--ndently reviewed by the responsible organization. NA. Qualification bv Similarity (If applicable) - A' justification for qualifiTation b'y similarity is attached to the EQS considering all the above factors and referenced to the appropriate tables. _ Oualification of Several Exact Comocnents (If applicable) - When an EQS y is use7 for more than one item, a list of all exact components are given as an appendix ":ith all references to appropriate tables with justification for qualification considering all the above factors. NA _I_nteria Qualification (If applicable) - (0 pen item) - Component has been detercII'ned to be qualified only for a limited interim operation, an NCR has been written, and plan of action has been determined to yield a qualified component. Term of Interim Qualification NCR No. NA hqualified Component-(0 pen item) - (If acpliccble) - Component has been determined to be unqualified; the fellcwinc is attached to l:QS: NCR number, reason for acn-qualification, and justification of continued operation. L ' NCR No. t; NMm .n R n P Ohn'.GV,W:.El NY5{} f yg g l l ~ ~ e
~ Preparer /Date M N /SA// 6 - mo -7.:3 EQS No. SONEEB1064 Reviewer /Date /~2s. o d~300 e 1 of I r Manufacturer Technology for Eneroy Corporation Component VaTve Flow Monitoring System Component ID - Model No. Table / Sheet 1,2 XE-68-340A ^ ENDEVC0 2273A 3.11-4/la 1,2 XE-68-334 1,2 XE-68-363 1,2 XE-68-364 1,2 XE-.68-365 1,2 XT-68-340A T5C 504A ~ ~ 1,2 XT-68,-334, 1,2 XT-68-363 1,,2 XT-68-364 a ~ 1,2 XT-68-365 2 XE-68-366 ENDEVC0 2273A 2 XT-68-366 TEC 504A l l l l 1 1 l t i
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h S ~ 3 0 ~ T 1' Y ..preparar/Oct2 EQS No. SQNEEB1064 d u c -- Y ee o 3 Reviewer /Dat \\ ^ Technology for Energy Corporation (TEC) has qualified their valve flow monitoring system by testing to the requirements' delineated in IEEE Standard 323-1974. Test proced. ires and results are documented 'in TEC reports 517-TR-01 and 517-TR-03, revision 2, respectively. All qualification tests were ' performed at test levels or conditions in excess of known maximum application requirements. Margins were in accordance with those suggested by IEEE Standard 323-1974. i This equipment is located inside containment (lower cxnpartment) whebe the -maximum normal operating tempe N ture is"120 F. The system is subject to a 0 LOCA/HELB condition inside primary containment which is,shown in figures 1 and 2. The system is required to operate for one year after the start of an accident. ( Operating Environment ~ \\ The system is required to operate in the following environment: i Normal Abnormal Accident \\ s t Temperature: 120 F 1304 -( 3270F 0 Pressure: 14.7 psia 14.7 psia l 26.4 psia Relative Humidity: 80% 100% 100% Radiation: 2x107 rads N/A 1x108 rads (40 year' TID) L LOCA/HELB: Temperature and pressure profiles are shown in ' figures 1 and 2, respectively. Figure 1 shows the worst case temperature versus time prcfiles for both upper and lower compartments. inese curves take into account the effects of both a double ended pump suct(on break (LOCA) and the most severe steam line break (HELB). Relative humidity in both compartments will increase to 100 percent during the first few seconds and will remain at that value until 105 seconds, at which the it will decrease linearly to the normal maximum value of 80 percent at 30 days. The pressure curve (figure 2) is for a LOCA and completely envelopes the HELB pressure profile. The manufacturer has tested this system to the following envircnment: 7 $ mal Accident i 0 Temperature: 257 F 450 F Pressure: Atmospheric 85 psig ,t Relative Humidity: 80% 100% Radiation: (2.1x108 rads total) s LOCA/HELB: -{See description below) 1 e 5 a:.ka.:--- .a.
EQS No. SQNEEB1064 ~. Appendix 2, Rev 0 Sheet 2 of 3 The equipment was subjected to a MSLB/t.0CA simulation test. The transient portion of the test was repeated twice as required by IEEE Standard 323-1974. The first transient was performed as follows. The test chamber / was stablized at 1800F and remained in this condition for 10 minutes. The test chamber temperature was then increased to 4650F in 48 seconds, and the pressure increased to 88 psig in 32 seconds. The pressure and temperature rises were simultaneous..The pressure was then reduced to 85 psig, and this condition was maintained for a period of 1.5 minutes. At the conclusion of the 4650F and 85 psig dwell, the temperature was reduced to 3650F in 25 seconds. Approx-imately.eight minutes after completion of the first transient, the test chamber decayed to 1800F and ambient pressure. The second transient was initiated after test chamber stabilization, and the temperature of 1800F and ambient pressure had been maintained for approximately 10 minutes. During the second transient, the chamber temperature was increased to 4500F in 31 seconds, and the pressure increased simultaneously to 88 psig in 24 seconds. The pressure was then i reducrd to 85 psig, and this condition was maintained for 1.5 minutes. At the ion of the 4500F and 85 psig dwell, the chamber temperature was x red' 3650F in 21 seconds. After four days and 12 hours, the chamber r 4 had or reduced to a temperature of 2650F and 50 psig. The chamber remained at these conditions for five days and 12 hours for a total of 10 + days. After 10 days, the TEC 160 Transient Shield malfunctioned due to i shorting of the inputs. The input connections were then modifed to those in the TEC 160-2 Transient Shield with the connections sealed with Raychem ,e{ WCSF-N heat shrink. In this configuration it was successfully tested an additional 23 days for a total of 33 days. However, for our qualification purposes, we will consider only the first ten days. The one year post-LOCA life requirement can be extrapolated from the actual ten-day test using the Arrhenius Equation, which' states: E 1 1 E .~ ~ 7T2 1 s. 11=12 e t t where Q 11 = Qualified life 12 = Accelerated (test) life 3',4 / E = Worst-case activation energy, e = Boltzmann's constant, 8.617x10-{ eV/0K AC K / { T1 = Qualified temperature, absolute e tl T2 = Elevated (test) temperature, absolute p[ e = Base of natural logarithms
Reference:
EPRI, NP-1558, Research Project 890-1, dated September 1980. The portion of the temperature versus time profile (shown in figure 1) that extends from 2000F at 5x103 seconds to 1150F at 2.59x106 seconds respresents the period during the actual test that extends from 3650F immediately after the second transient to 2650F after four and one-half 1 ..:n 4f ie )g: a.m - a, w _ = __ _. ,.v
~ EQS No. SQNEEB1064 Appendix 2, Rev 0 Sheet 3 of 3 d ays. Using 3150F as an average temperature for T, 2000F as a 2 conservative value for T, and 0.6eV as a conservative value for E, 1 0.20/ years can be derived from the Arrhenius Equation. Then using 2650F for T, 1150F for T, and 0.6eV for E, 1.375 years can be derived 2 1 from the remaining five and.one half days of the test. This yields a total post-LOCA life of 1.582 years. It is our engineering judgment that satisfactory performance can be expected from this system in the LOCA/HELB environment for a period of sie year'. Agina (Qualified Life) TEC has thermally aged this system for 1000 hours at 2570F (1250C). The qualified life at 1200F for this system is 7.116 years based on the Arrhenius Equation. The required temperature, pressure, radiation, and humidity are well within TEC's test data. It is our engineering judgment that satisfactory performance can be expected from this system in the normal operating. environment for seven years. Chemical Spray The system is located inside containment so it is subjected to a chemical spray. The test specimen was exposed to a chemical spray at the rate of approximately 0.15 gpm per square foot of test specimen area projected onto a horizontal plane. The spray solution was prepared with 5,500t500 ppm boron buffered with sodium hydroxide to achieve a pH factor of 9 +1. The spray remained on throughout the entire phase of the LOCA simulation. The chemical composition of the containment spray at Sequoyah is a concentration of 0.1847 molar H 803 (2000 ppm boron), and 0,.033 molar NaOH 3 resulting in a pH of 8.2 at 2500. The system successfully completed the LOCA simulation without incurring any corrosion or operability failures. Since the chemical concentration of Sequoyah's containment spray is less severe than the concentration used in the LOCA simulation, the system should not be affected. 052180.04 4 V 3 N-e.mm,s - D- %.h a .,ew,-*y,
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