ML20027C243

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Forwards Response to NRC 820409,0514 & 0609 Ltrs Re Request for Addl Info.Responses to Questions CS 421.26,43,51 & 53 & CS 760.162,164 & 176 Will Be Incorporated Into Future FSAR Amend
ML20027C243
Person / Time
Site: Clinch River
Issue date: 08/24/1982
From: Longenecker J
ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To: Check P
Office of Nuclear Reactor Regulation
References
HQ:S:82:086, HQ:S:82:86, NUDOCS 8210150186
Download: ML20027C243 (39)
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{{#Wiki_filter:. ~~ ffjj DJ l / Department of Energy - d /' Washington, D.C. 20545 Cod't u MM 4 <w: Docket No. 50-537 /p/> f'g{ l e HQ:S:82:086 L AUG 2 41982 4 Mr. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation i U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l t

Dear Mr. Check:

RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION ) I

Reference:

Letters, P. S. Check to J. R. Longenecker, "CRBRP Request for j Additional Information," dated April 9, May 14 and June 9,1982. t i This letter formally responds to your request for additional information I contained in the reference letters. I Enclosed are responses to Questions CS 421.26, 43, 51, and 53 and CS 760.162, 164, and 176 which will also be incorporated into a future PSAR Amendment. I J Sincerely, t [ W Joh Longenecker - i Acting Director, Office of the ( Clinch River Breeder Reactor Plant Project j Office of Nuclear Energy Enclosures j i cc: Service List i Standard Distribution Licensing Distribution I i 1 i 3)ool gjo150186820824 ADOCK 05000537 4 PDR i ... -... _,. -... ~., =. -...

AUG 2 5 M32 Docket No. 50-537 =aa' *" 5 HQ:S:82:086 ato svMaa 24 W NE,-5 igptoce - 3/4_ '.32_ afG SvMROL Mr. Paul S. Check, Director N E.5 2....... CRBR Prograni Office '~6'pg Office of Nuclear Reactor Regulation n.acy.... U.S. Nuclear Regulatory Connission o^'t Washington, D.C. 20555 8/ /82.___ RTG $YMB%

Dear Mr. Check:

.5........ RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION , ",,7 s,o. f rfg eckg i DATE

Reference:

Letters, P. S. Check to J. R. Longene:ker, "CRBRP Request for 8/2 /82___ Additional Infonnation," dated April 9 May 14 and June 9,1982. This letter fonnally responds to your request for additional infortnation 'A'i'A U E " " contained in the reference letters. DATE Enclosed are responses to Questions CS 421.26, 43, 51, and 53 and CS 760.162, 164, and 176 which will also be incorporated into a future PSAR Araendrnent. Sincerely, g,.,7 John R. Longe / /s r.ecker Acting Director, Office of the ,,,,y,g g g - Clinch River Breeder Reactor Plant Project ggg-Office of Nuclear Energy RTG SYMBOL Enclosures .....A sE"" cc: Service List Standard Distribution swi" Licensing Distribution RTG STMBOL Dist ,,;,i,EGi"

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t CRBRP Chron RTG SvMBO6 bcc: . Goeser, ULLC0 P. Gross, CRBRP P0 .ss.EGE" ' 1 ..ii DOE F 1325.10 OFFICIAL FILE COPY i (7 79)

rose - i s i - c,. a :;,, y fa-e i Question 421.25 in the PSAR, Section 7.4.1.1.2 discusses the Protected Air-Cooled Condencar (PACC) and how air flow through It is controlled by a combination of f an blade pitch and inlet louver position. The staf f requires a detailed discussion of this instrumentation and in particular the method used f cr f an blade pitch Indications. Resoonse: I The outlet louvers have discrete open and closed position sensors. These provide indication at both tha local control panel and main control panel in the control roan. i The inlet louvers have both discrete open and closed position sensors and a continuous position sensor. The continuous position sensor provides f eedback to the louver control. Both types provide Indication at the local control panel and the main control panel in the control roon. The f an blade pitch uses continuous position sensors f cr both control and indication. The Indication is provided at the local control panel and the main control panel in the control rocm. Both the discrete and continuous sensors are integral to the actuator. The discrete sensors are roller switches activated by a cam and the continuous is a potenticrneter. 1 I l ) QCS421.26-1 f /nend. 71 ( Sept. 1982 ( ^^ ~ ' '

fi;o -2 (tz-Oi b;Lc,13J ilb Ques 11pn 421.43 Section 7.7.1.3.2 of the PSAR deals with the Rod Position Indication System. Discuss the design criteria for this system. Responia: The basic criteria for the Rod Position Indication System are 1) to provide redundant Indication of primary control rod position over the f ull range of possible rod movement and 2) provide position information necessary to insure that maximum control rod misalignments are limited to a value less than 11.5 inches. To meet the first criterion two diverse and independent measuring systems are provided. Each system is capable of measuring the position of the primary rods throughout their range of motion. The Absolute Rod Position Indication System (ARPI) determines the position of the control rod absorber through the position of the mechanism lead screw relative to the control rod drive mechanism. As the ARPI provides a direct measurement of rod position, it does not lose its ref erence af ter a scram or temporary loss of power. The Relative Rod Position Indication system (RRPI) determines the position of the control rod absorber by monitoring the rotation of the roller nut which operates the lead screw. Because the roller nut opens to allow the lead screw to drop during a scram, the RRPl loses its ref erence and must be rezeroed after such an event. To insure that the second design criterion is met, it is necessary to provide system accuracy such that event when readout, accuracy and position uncertainty associated with the position of the absorber assembly relative to the reactor core are consi dered, rod misalignments are limited to a value less than 1.5 inches. The accuracy of the RRPI and ARPi, each being better than 10.3 Inches, insures that the second criterion is met. 1 I i i i i j QCS421.43-1 Amend. 71 l Sept. 1982

.um.... ,a..e w a a ne s Question 421.51 Using draw!ngs (schematics, PalD's), describe the automatic and manual operation and control of the atmospheric relief valves (superheater). Describe how the design complies with the requirements of IEEE-279 (i.e., testability, single failure, redundancy, Indication of operability, direct val ve position Indication in control room, etc.). Resconse: The atmospheric relief valves on the superheater outlet line, val ves 53SGV106, 107, & 108 in Figure 5.1-4, provide overpressure protection for the superheater and also provide superheater blowdown capability in the event of a sodium / water reaction event. The overpressure protection is provided when the steam pressure reaches the valve set pressure. The steam pressure overcomes the f orce exerted by a spring on the pilot valve and opens the pilot valve. This action then causes the main valve to go to the f ull open position, where it remains until the pressure in the steam line is reduced below the set pressure. Both the pilot valve and the main valve then close. This val ve is designed to meet all requirements of the ASME Code, Section 111, Class 3, for overpressure protection devices. An electro-pneumatic actuator is Installed on the pilot valve of each superheater and evaporator relief val ve, which can open, but not close the val ve. For evaporator and superheater blowdown following a SWRPRS event, the rel ief f unction is actuated automatically when the SWRPRS is activated (See PSAR Section 7.5.6.1.2 and Figure 7.5-6 f or SWRPRS trip l ogic). SWRPRS actuation of these val ves is not saf ety related. Each evaporator and superheater outlet relief valve can also be opened individually by means of a control button on the r.aln control panel. This control, along with other val ve controls, permits the operator to isolate and bl ow down a single module in the event that a small leak is identified in an evaporator or the superheater module and the plant is being shut down bef ore a rupture disk bursts. The requirements of IEEE-279 co not apply to the superheater outlet saf ety/rel ief valves, since these val ves perf orm their overpressure protection f unction independent of the electro-pneumatic actuator. Overpressure protection is discussed in Section 5.5.2.4 of the PSAR. l 1 QCS421.51 -1 knend. 71 l Sept. 1982

i c;u e <n. w i.r.e,a j ts/ s Valve position is indicated in two ways: (1) An electromagnetic switch senses the position of the electro-pneumatic actuator on the pilot val ve stem and actuates position lights in the main control to verify the pilot valve has been opened electrically. (2) Acoustic sensors are attached to the valve discharge pipes near the valve outlet to verify the presence of flow through the valve and actuates a group alarm in the main control room. The acoustic sensors are capable of detecting small leaks f rom a val ve which has closed, but not f ully re-seated itsel f end thus, provide direct Indication of valve position. i l QCS421.51-2 Amend. 71 Sept. 1982

veye -> na-va..>Lc,saa u,s Ques 11pn_f 21.53 Section 7.2.1.1, paragraph 2, of the PSAR states the Primary RSS is comprised of 24 subsystems and the Secondary RSS is comprised of 16 subsystems. Each of these subsystems consists of three physically separate redundant instrument channels. This information contradicts the inf ormation in Table 7.2-1 and Figure 7.2-2B and 7.2-20, which shows there are 8 subsystems in the Primary RSS and 7 subsystems in the Secondary RSS. Shouldn't it be that the Primary RSS allows 24 Inputs, the Secondary RSS allows 16 inputs? There are 8 subsystems in the Primary RSS providing 17 inputs to the Primary RSS f ogic and the Secondary RSS consists of 7 subsystems providing 16 inputs to the Secondary RSS logic as follows: PLANT PROTECfl0N SYSTEM PROTECTIVE FUNCTIONS

  1. of inouts Primary Reector Shutdown System 2

1. Fl ux-Del ayed Fl ux (Positive and Negative) 1 2. Flux-Pressure 1 3. High Flux 3 4. Primary to intermediate Speed Mismatch 3 5. Pump Electrics 1 6. Reactor Vessel Level 7. Steam-Feedwater Fl ow Mismatch 3 3 8. lHX Primary Outlet Temperature 7 Spare 9. Secondary Reactor Shutdown System 1. Modif ied Nuclear Rate (Positive and Negative) 2 2. Fl ux-Total Fl ow 2 1 3. Startup Nuclear 4. Primary to intermediate Flow Ratio 2 3 5. Steam Drum Level 3 6. Evaporator Outlet Sodium Tanperature 3 7. Sodium Water Reaction 0 Spare _Resoonse: The Primary RSS coincidence logic allows 24 comparator inputs, the Secondary RSS coincidence logic allows 16 comparator inputs. Not all of the potential inputs are presently utilized. Table 7.2-1 has been revised to indicate the number of inputs. i i QCS4 21.53-1 Amend. 71 Sept. 1982

ago - I tec u!ia Lc,1J 1,v

~ TABLE 7.2-1 PLANT FROTECT10N SYSTEM PROTECTIVE FUNCT10NS Primary Reactor Shutdown System Humher of inputs o-Flux-Delayed Flux (Positive and Negative) 2 o Fl ux-Pressure 1 1 o High Flux o Primary to intermediate Speed Mismatch 3 1 o HTS Pump Frequency 1 o Pump Electrics o Reactor Vessel Level 1 o Steam-Feedwater Fl ow Mismatch 3 o IHX Primary Outlet Temperature 3 Secondary Reactor Shutdown System Number of inouts o Modified Nuclear Rate (Positive and Negative) 2 o Fl ux-Total Fl ow 1 o Startup Nuclear Flux 1 o Primary to intermediate Flow Mismatch 2 o Steam Drum L' vel 3 o Evaporator Ou-t Sodium Temperature 3 o HTS Pump Voltage 1 o Sodi um Water Rea 'lon 3 i I The Primary RSS can accept a total of 24 inputs and the Secondary RSS can I accept 16 inputs. There are 9 spare Primary inputs. t i 7.2-18 Amend. 71 Sept. 1982

i; g - T (PZ-DiU J Ld,e d rev s puestion CS760.162 in CRBRP-3, Vol.1, Rev. 2 the applicant describes a method f or evaluating certain components loaded during an HCDA wherein component response is evaluated using linear static calculations with " appropriate" dynamic ampi lf ication f actors. The reactor vessel nozzles, head mounted components, and vessel appurtenances wil l be evaluated with this method. The first step is to evaluate the complete reactor vessel system with a dynamic inelastic model. Canponents then will be evaluated using the system response at their specific location as input. Each component wil l be analyzed first by applying loads and/or displacements to a static model using what is cal led an "appropr iate" dynamic ampl if ication f actor. If the component in question f alls this test, it is evaluated using a dynamic elastic moael. Finally, if the component f alls this test, a more complex inelastic dynanic analysis is perf ormed. The procedure of using a static analysis with dynamic amplification f actors is comaon in linear systems where the appropriate amplification f actors are easily obtained. Results are usually conservative because dynamic phasing of dif ferent load components is neglected. The appropriate amplification f actors for a nonlinear system are not easy to ottain and may not even be unique def inable quantitles since the vibration I f requencies and damping of the component change as it plastical ly def orms. The applicants must describe how the dynamic amplif ication f actors are to be derived. I Resconse: The applicant agrees with the NRC regarding the use of dynamic amplification f actors f or static analysis of linear elastic systems. The current CRBRP-3 analyses do not use dynamic amplification f actors for analysis of non-linear systems. CRBRP-3, Volume 1, Section 5 wil l be amended to clarify th is. J ) l 1 I i i I I QCS760.162-1 Amend. 71 Sept. 1982

.-Se - 2 itJ-J7L3) LL,.Cj F20 Duestion CS760.164 in Sec. 5.4 of CRBRP-3, Vol.1, Rev. 2, the appl icant states that resul ts of both analyses and experiments indicate that the closure head will withstand SMBD8 loads without structural f ail ure. This conclusion is based in part on the results of scale model tests SM-4 and SM-5 where the head model showed no visible plastic def ormation. A probice exists in using these test results to denonstrate the capability of the head in that the design of the scale model heads was non-prototypic. The shielding plates were bolted directly to the bottcm of the head, possibly overstif fening it considorably and, theref ore, not allowing def ormations that lead to the most probable head f ailure mode (disengagement of the intermediate rotating plug). Because of the design of the model head, we are not convinced that the applicants conclusions regarding the acceptability of the head design can be made based on the experiments done to date. The analysis presented does indicate that, under SFSDB leading, the head only displaces 23% of its predicted f ail ure displacement. This analysis is acceptable if the applicant can benchmark the analytical model with experimental data. Benchmarking with other analyses is not acceptable, especial ly because many analytical techniques, in particular the finite eleme t method, overpredict the stif fness of structures being modeled by m several percent. To resolve this issue of vessel head capability the applicant should benchmark the analytical model being used and show that it predicts a comfortable margin to head f ailure. The required margin will be less if the model is benchmarked with both static and dynamic test data. Resconse: The analytical model used to predict strains and displacements of the CRBRP Reactor System under SMSDB loading wil l be benchmarked against static (SM-1) and dynamic (SM-5) test data. These analyses wil l be completed by October 30, 1982, and the documentation wil l be provided to NRC by November 30, 1982. I I l J l QCS760.164-1 Amend. 71 i Sept. 1982

.agu - s ur usiruo,.; a.. s Question CS760.176 In preparation f or writing those sections of the SER dealing with PCRDM, we have found it necessary to secure additional documentation on the D. C. stepper moter used in the system. Specifically, we would like to obtain the following information: 1. Complete description of the motor 2. Equipment specification for the motcr, and 3. Test inf ormation or data establishing that the specif ications are met, including the maximum withdrawal speed in the event an over-speed signal is sent to the control ler. We would also like to know the maximum slew rate of the motor and what power input conditions, however improbable, that would be required to obtain it. F [ t I ? i i l l l 1 l l QCS760.176-1 Amend. 70 Aug. 1982 m

RespDn191. ITEM 1 Descriotion of PCROM Motor The PCRD4 utilizes a collapsible roller nut design which has been successfully used in the past on pressurized water reactors. This type of drive has a non-rotating leadscrew which is driven up or down by a fixed elevation roller nut formed by four ball bearing mounted rollers, equally spaced around the l ea dscr ew. The rollers are inc!!ned from vertical at the leadscrew helix angle and have teeth which engage the leadscrew threads to provide a positive connection to the translating assembly. Two rollers are mounted in each segment arm which are attached by pivot pins to a rotor carried on ball bearings in the motor tube. The complete assembly is shown in PSAR Figure 4.2-101. The motor tube is shown in Figure QCS760.176-1, the segment arms and roller nuts in Figure QCS760.176-2, and the stator in Figure QCS760.176-3. The roller nut is actuated by a six-phase, four pole stator mounted outside the matcr tube. The stator and segment arms together form a reluctance type synchronous stopping motor. The stator windings are energized by direct current which can be swi tched in a progratmed sequence anong the six-phase to produce a stepwise rotating magnetic field in the annature region (see Fig. QCS760.17 6-4). The two segment arms, which make up the motor annature are f abricated from permeable stainless steel and tend to align themselves with the rotor field so as to minimize the magnetic circuit reluctance between adjacent stator poles. The motor armature is, theref ore rotated in synchronism with the rotating stator f iel d. The segment arms pivot in a vertical plane through the leadscrew centerline and are constrained to move through the same angle by means of a synchronizer bearing mounted at the top of the rotor. The armature region of each segment arm is located above the pivot pin, while the rollers are mounted below the pivot pin. When the stator is not energized, the segment arms are held in the collapsed position by springs acting outward below the pivot pin. In this position, the,rol lers are disengaged f rom the l eadscrew, and the armature section of the segment arms are displaced inward toward the mechanism centerline. When the stator is energized, the armature section of the segment arms are magnetically attracted toward the stator with a fore,e suf ficient l 4 t \\ QCS760.176-2 i Amend. 70 Aug. 1982

I e j to overcome the segment arm spring f orce end engage the rollers wIth the l eadscr ew. l The direction of leadscrew travel is detennined by the direction of rotor rotation which, in turn is determined by the particular switching sequence applied to the stator phase windings. The speed of rotation is controlled by the switching rate, which is adjustable over a wide range by the controller. The rollers remain engaged to the leadscrew during reversal of rotation direction. If the switching sequence is stopped and the stator is lef t energized in any of the twel ve (12) possible phase combinations, the segment arms continue to be attracted outward and they will hold the leadscrew Ir.def initely at the elevation achieved when the rotation was stopped. The windings comprising the six phases are so arranged that when energized in a 3 - 2 sequence, the f orce-pole magnetic paidern f ormed by the stator rotates in space in 15-degree

steps, if the six phases are designated by the letters, A, B, C, D, E and F the sequence f or rotation is shown below.

Rotational Degrees 0 15 30 45 60 75 90 105 120 135 150 165 Phases Energized AB ABC BC BCD CD CDE DE DEF EF EFA FA FAB As shown above, the motor is energized in either a two phase or three phase mode in the hold condition and switches f rom two phase-to three phase-to two phase while in the run mode. Since the motor is either in a two phase or three phase condition during hold, the two conditions will produce dif ferent magnetic f iel d strengths. Theoretically, the three phase condition should produce 1.5 times the magnetic flux of the two phase mode, but in the.real motor, it is less than this ratio due to temperature and saturation ef fects. 4 I QCS760.176-3 Amend. 70 Aug. 1982 em mmmm

i i [ For the motcr io produce torque, the induced poles in the rotcr must lag the statcr poles. The tcrque is roughly a sinusoidal function of the lag angle, and in actual operation, the lag angle adjusts itsel f to the value Just suf ficient to balance the applied tcrque resisting rotation, up to the pull out cr pol e sl i p val ue. The radial moment on the engaged segment arms, called hol ding mcment, is also a f unction of the rotcr leg angle, and in this type of ro.tcr increases senewhat as the l ag angle departs f rom zero. l i The radial mccent also varies strongly as a f unction of the collapse angle of j the segment arms (as does the peak tcrque) because of the large change in air j gap and the corresponding change in flux IInking the ams. Since the segment arms are held in the collapsed position by eight coil springs, the mcnent l required to overcome the springs and bring the rollers into angaganent (latch) l l plots as a straight line, with force increasing tcvard the fully engaged c j position. This relationship is shown in Figure QCS760.176-5. 1 During steady state operation (run or hold mode) the available tcrque and l mcment are determined by the available current. The run - hold voltage is l specif ied to be 17515 volts DC, and will be controlled within this range. Theref ore the available current is determined by the resistance of the l winding, and the resistence is a f unction of the stator winding tcrnperature. i The tunperature of the winding is controlled by a constant flow of nitrogen gas. The specif ied operating paraneters of this statcr cooIIng system are t inlet tcuperature 551 5 F j r Outlet f(cperature 140 F maximum i l Pressure at inlet 90 psig minimum i 100 psig minimum ( Ficv 157 i 10 scf m i I During acceptance testing of the PCRD4s at the vendors plant the f ollowing i typ!.A operating paraneters were determined-I f Outlet coolant tcmperature = 12015 F 0 Phase resistance = 24.6 i 4 ohms (hot) Phase current = 7.1 i.1 anps I l l 1 i l i t l i' i l I l QCS760.176-4 { Amend. 70 l Aug. 1982 l t ,n

ITEM 2 r The equipment specification for the PCRDM motor Is contained in and is a part of the equipment specification f or the Primary Control Rod Drive Mechanisn. The following are those sections which epply to the motor. l." ASME Code Classification A. The mechanisn motor tube, nota-tube holddown ring, and position Indicator housing act as part of the reactor primary system boundary, and shall be constructed as a Class 1 vessel meeting requirements of the ASME Boller end Pressure Vessel Code, Section Ill. i B. The design of the CRDM shall be based on the Fast Flux Test Facility (FFTF) CRDM as def ined on component drawings. ll. Environment and Duty Cycle l A. The external surf aces of the CRDM are exposed to the Head Access Area i (HAA) air temperature of 851$$0F during normal operation and 1400F l maximum f or loss of HAA cool ing. Normal CRDM internal pressure ranges i from 0-20 psig. Design condition f or ASME Code evaluation are 5000F i and 35 psig. ? B. Neutron Environment Neutron dose levels above the closure head in the vicinity of the l control rod dr Ive mechanisms may range f rom 100 mr/hr to <2 mr/hr. A [ shield system / selsmic support will shleid areas above 100 inches. The corresponding total neutron flux range is approximately 2 x 104 2 r/cm /see to 2 x 102 x 102 n/cm2 sec. [ The above total fluxes correspond to a f ast neutron f lux <2 x 102 2 n/cm /sec. t C. The design l if e of the CRDM shal l be 30 years. d QCS760.176-5 Amend. 70 Aug. 1982 . _ ~ _ _,

D. Duty Cycle Total start-stop cycles 8 x 106

    • Total lifetime screms 732
  • **L if etime travel (0.36 to 9.0 Ipm) 17,000 feet One motcr step equals a start-stop cycle
    • Includes 150 Isothermal test scrams
      • Incl udes start-stop cycl es Ill.

Loading Conditions A. Stroke The CRDM shall provide a minimum withdrawal stroke of 36.00 Inches as measured f rom the nominal position (station -351.025) of the top of the control assembly disconnect coupling to the minimum up position of the CRDM rotational stop. The CRDM insertion stroke shall reach and couple'with the control assembly at the lowest position with the top of the control assembly disconnect coupling at -351.750. The CRDM maximum withdrawal stroke shall not exceed 37.80 inches as measured f rom the lowest position (station -351.750) of the top of the control assembly disconnect coupling to the maximum up position of the CRDM rotational stop. The stroke requirenents are ref erenced to a 700F temperature environment. The CRDM shall be capable of providing an incremental motion of 0.025 inches (nominal). The nominal selectable in and out CRDM speed range shall be 0.36 to 9.0 Inches per minute. The maximum possible withdrawal speed of the CRDM with a f ailed controller shall be less than 73 Inches per minute, I I I l l QCS760.176-6 Amend. 70 i Aug. 1982 ] ~~__~~-

I B. CRDM/CRD Operating Forces The CRDM shall be designed to exert the f ollowing f orces: 1. Minimum insertion f orce on control rod (stuck rod) 1,000 lbs. 2. Minimum withdrawal force suf ficient to overcome all worst case f orces acting on the control rod assembly is 285 lbs. This f orce includes control assembly weight (167 lbs), bouyant forces (-30 lbs) and rod friction (148 lbs) acting over the first 8 inches of w ith dr ewal. When the rod is withdrawn above 8 inches and the rod friction force is reduced to 48 pounds and the total force is reduced to 185 lbs. The CRDM and CRD shall be designed to withstand the following loads. The temperature under which these loads are to be applied is 4000F. j 3. Maximum leadscrew driveline tensile load 20,000 lbs 4. Maximum position Indicator rod compressive 1,000 lbs load at ref ueling temperatures. The CRDM shall resist outward mott'on of the translating assembly; 5. With the segment arm rollers engaged to the leadscrew (latched), the translating assembly shall not move up when a constant up f orce of 1800 lbs, or less, is applied to the control rod coupling interf ace. 6. During a screm operation (stator power interrupt and roller uniatching) the translating assembly outmotion shall be limited i when a constant up f orce of 1800 lbs, or less, is appiled to the control rod coupling Interf ace. 7. With the rollers disengaged (unlatched) and the pawl engaged to the leadscrew, the translating assembly outmotion shal l be l imited when a constant dynamic up f orce of 1800 lbs, or less, is appIIed to the control rod coupling interf ace. Prior to pawl engagement the out-motion velocity is limited (by sodium flow rate) to 25 lps. QCS760.176-7 Amend. 70 Aug. 1982

4. Since the CRDM employs a pawl design which positively prevents axial outmotion ef ter engagurent, the axial outmotion prior to motion arrest shal l be l imiteo as f ol lows: Paragraph (Ill.B.5) - 0.200 Inches i Paragraph (Ill.B.6) - 0.600 Inches Paragraph (I l l.B.7) - 3.25 inches The design shall be capable of resisting outward motion in each of the above operating modes a minimum of two times during plant operation. The up f orce is not an ASME Code requirenent. Str uctural Integrity of the primary pressure boundary to prevent generation of missIIes must be maintained under this loading condition. J The CRDM Scran spring shall meet the following: 1. Minimum Spring Force 362 lbs at minimum spring compression with the translating assembly in the "f ull out" post-tion as limited by the rotational stop. 2. Minimum Spring Stroke 25 Inches 3.

    • Spring Force at beginning 0.00 lbs of dashpot operation 4.

Design Temperature 4000F

    • Def ined as elevation (-175.87) where the dashpot piston enters the end of the tapered section of the dashpot cylinder.

I l l l QCS760.176-8 Amend. 70 l August 1982

a IV. Scr an A. Scran Requironents The overall Primary control Rod System serem requirements are depicted in PSAR Section 4.2,3 and on PSAR Figure 4.2-93 and include the total time f rom stator poser interrupt to roativity insertion. The uniatch time is def ined as the time f rom the start of stator current decay to the initial insertion motion of the leadscrew and shall be 90 msec maximum at normal CRDM and stator operating temperatures. B. Dashpot A dashpot shal.1 be included in the CRD for decelerating the translating driveline and control rod during the last nine Inches of a scram insertion. The energy of the scrammed assembly shal l be absorbed at a ceceleration rate which will limit stresses in the drivel ine components to an acceptable level. The dashpot shal l reduce the velocity of the CRD and Control Rod when scrammed from any position between 0 and 37 inches to less than 14 inches /sec at the time of impact on the hard stop at the end of screm insertion. V. Independence Each control rod shall be driven and positioned by its own mechanism. Each control rod shall be independent to the extent that protective action is not delayed. The CRDM shall be designed to minimize the probabil ity of simultaneous disabil ity in the scram mode of al l CRDMs through systematic, concucrent, undetected f ailures in the CRDMS resul ting f rom commonal ity of components or susceptibil ity to f ail ure due to common environmental conditions, duty cycles, or loads. VI. CRDM Position Indicators Two independent CRDM position Indicator systems shall sense the position of the leadscrew and thus produce two separate signals indicating the relative position of the control rod in the core. The rotary (relative) position Indicating system shall consist of an electrcmagnetic sensor that counts the revolutions of salient poles of an Indicating disc attached to the drive mechanism rotor. The axial resolution of the rotary position Indication system shall be 0.10 inches (nominal). The absolute position Indication system shall measure the position of the leadscrew through a sensor located in a housing that projects into the inside dianeter of the leadscrew. This system shall not lose its i' ref erence position because of mechanism scram. The resolution of the QCS760.176-9 Amend. TO Aug. 1982

absol ute position Indication system shall be 0.50 Inches. The systan poslTion accuracy over f ull stroke shall be i 3.5%, of the f ull stroke. The accuracy of the position Indication sensor over the range of environmental conditions shal l be i 1.62% of the f ull stroke. the accuracy refers to the ebility to measure the true position of the top of the leadscrew. Vll. Cooling A stator cooling system shall be provided. This system shal l not act as part of the reactor primary system boundary. The design shal l incorporate thermocouples into the stator cooling system and provide the corresponding electrical Interf ace Inf ormation. V I i 1. Reactor Ref ueiIng Tr.9 mechanism design shall permit ref ueling and f uel transfer ope. ations inside the reactor vessel in the space above the core withaut disassembly and removal of the mechanism. The design shal l perml+ access to the actuating shaf t Interlock ring and disconnect actuating shaf t so that the disconnect coup!!ng between the driveline and control assembly can be manually operated i l QCS760.176-10 hvend. 70 August 1982

i The design shall have provisions f cc the operation of a manual i disconnect tool (not provided as part of this speelfication) for [ disconnecting the control rod from the driveline and for holding the l l eadscr ew in a withdrewn position f or ref uel ing operations. i 1X. Out-Motion L imited Pawl An OML pawl shall be provided to limit outward motion of the translating assembly. Str uctural integrity of the pawl system (paw! and mounting brackets and hardware) shall be maintained f or a static up ( force of 4000 lbs acting on the control rod coupIIng Interf ace. During a screm the pawl shall not produce a drag force on the leadscrew in excess of 19 lbs. (everage) based on worst case dimensions with a friction coefficient of 0.8. X. Internal Seal Requiranents The Seal Requirements listed here are for Internal Seals and not the CRDM pressure boundary. l (a) Each CRDM shall be equipped with seal arrangenents which consist of a Main Bellows Seal, Position Indicator Rod Bellows, Disconnect Actuating Shaf t Bellows, and Lower CRDM to Nozzle Extension l Conoscal. l (b) The Seals shall separate the CRDM rotor assembly and leadscrew frcra the y eactor environment. (c) All bellows paraneters (length of stroke, etc.) shall be compatible witn the CRDM paraneters. l l (d) The Main Bellows shall collapse upon withdrawal of a control rod I and extend upon Insertion of a control rod. l 4 i 1 t i l f l l l l QCS760.176-11 l Amend. 70 t August 1982 -- ~-

(e) The Disconnect Actuating Shaf t Bellows end the Position Indicator [ Rod Bellows expand and collepse only during operation of the l } menual disconnect. i (f) Maximum hellwn leek rate for cach of the four seals listed in (a) l above is 1 x 10-5 cm3/sec at standard temperature and pressure. (g) Bel lows seal environment { o Tamperature - 4000F (maximum) i o CRDM - argon gas The Internal fluid in the mechanisn above the bellows is normally reactor grade argon gas at 0 to 20 psig. The composition of this gas is as follows: r Argon -99.996% pure Oxygen - 5 ppm maximum (vol ume) Hydrogen - ? ppm maximum (volume) Nitrogen -13 ppm maximum (vol ume) Carbonaceous Gases - 5 ppm maximum (vol ume) Water (D.P. -840F) - 6 ppm maximum (vol ume) Other - 7 ppm maximum (vol ume) An environment of Argon saturated with sodium vapor is to be considered an abnormal condition. The mechanism shall be 4 designed to operate throughout a reactor operating cycle (1 year) when exposed to this abnormal environment. In order to assure that the mechanism continues to operate with a f ailed bel lows, the design shal l make provision to prevent sodl um f rom depositing on the rotor essembly parts. Af ter repair and/or replacement of e f ailed bellows and cleaning of the CRDM to return it to its normal condition, the mechanism'shall continue to f unction f or the renalnder of its i design life. [ I r I I i i + t QCS760.176-12 Amend. 70 August 1982

Reactor cover gas side - Argon gas saturated with sodium vapor o (external to bellows). The environment external to the bellows is reactor grade Argon cover gas saturated with sodium vepor. Normal operating pressure is 612 in, w.g. Maximum operating pressure is 7

psig, during shutdown maximum pressure is 11 psig.

The composition of the gas is identical to 3.5.2S except as follows: Oxygen 10 ppm maximum Hydrogen 50 ppm maximum Nitrogen 2000 ppm mcximum o Pressure - Normal operating pressure dif ferential is 0 to +20 psig. Maximum operating pressure dif ferentiel is -7 to +20 psig. During shutdown, maximum pressure dif ferential is -11 psig. During CRDM f il l with Argon gas, maximum over pressure is 35 psig (not an operating condition). For the leadscrew and position Indicator shaf t bellows, a positive (+) pressure dif ferential denotes a higher Internal bollows pressure with respe'et to the external pressure and a negative (-) pressure dif ferentiai denotes a lower internal bel lows pressure with respect to the external pressure. For the actuating shaf t bellows, a positive (+) pressure dif ferential denotes a lower internal pressure with respect to the external pressui e, and a negative (-) pressure dif ferential denotes a higher Internal pressure with respect to the external pressure. (1) A pressure switch will be provided in the CRDM to sense Internal pressure and indicate seal f ail ures. XI. Instal lation and Removal The mechanism shall be arranged so that all operations incident to its installation on, and anoval from, the reactor can be perf ormed with access only to the head of the reactor vessel. Replacement of the stator assembly shall be possible without penetration,of the primary reactor system boundary. J i \\ 00S760.176-13 Amend. 70 August 1982

Xil. El ectr ical Stator Design A redesign of the FFTF stator which meets the requirements of Section ll! " Loading conditions" and its subsections shall be provided. The l design shall be consistent with a mechanism design which is balanced over all parameters, particularly with respect to load capability, screm reliability and stator cooling requirements. The design basis shall be increased margin over worst case loading allowing higher segment arm spring f orce f or improved scram reliabil ity and possible reduction of electrical and cooling power demand. The stator shall be designed for y 20-year life. Motor lead wire shall conf orm to MIL-N-8777C and MS-21471. The stator shal l have monof ilar windings of the double ML type wire. The cooling Jacket f or the stator shall also be redesigned to be compatible with the cooling requirement of the redesigned stator conf iguration. The cooling requirements shal l not exceed FFTF values: Cooling Gas Nitrogen i Supply Pressurs 90 to 100 psig inlet Gas Temperature 50 to 600F Outlet Gas Temperature 1300F maximum Pressure Drop Across Stator 1.5 i.5 ps! Heat Load-Each CRDM 12,000 BTU /hr maximum Flow Rate 157 i 10 SCFM Motsture Content 8 ppm by weight maximum i 1 l 1 QCS760.176-14 Amend. 70 August 1982

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Testing Requironents A. Stator Tests The stator shall be tested at various points during f abrication as indicated below. The results of these tests shall be recorded and maintained in the record book f or each particular stator. If thennocouples are required to be incorporated into the stator, these thermocouples shall conform to ASTM E 230. The Individual coil group resistance shall be checked prior to inserting the coils into the stator. Any coil whose resistance varies by more i 2% from the naninal design value shall be rejected. Af ter all windings have been Inserted into the stator and bef ore the lead connections are permanently made, the stator shall be subjected to a DC Insulatin Test and an AC Dielectric Strength Test as described below: The following tests shall be made on the stator upon completion of the lead connections and bef ore varnish impregnation. 1. DC Winding Resistance Test The resistance of each phase of the stator shall be checked. Resistance which varies by more than i 2% from the nominal-design value, shall be cause f or rejection. Also, en unbalance of phase resistance which exceeds 11.5% of the average value for all the phases of the stator shall be cause f or rejection. 2. DC Insulation Resistance Test The insulation resistance from all phases and neutral lead to ground shall be checked. The minimum acceptable phase-to-ground resistance at 2500 is 10 megohms. 3., AC Dielectric Strength Test Apply 1500 volts rms 60 Hz between the stator Iron and any one i of the stator leads. Voltage shall be applied at a rate of { 1 I 1 QCS760.176-15 Amend. 70 August 1982

epproximately 100 volts per second, maintained at 1500 volts f or 15 seconds, then reduced to zero at approximately 100 volts per second. All of the phases of the stator shall be checked. The stator insulation must not exhibit dielectric breakdown when subjected to the above test voltages. All six phases may be tested simultaneously. In addition, measurements of the maximum compensated current leakage between colis and between windings and the core stack will be recorded for the prototype GDM statcr. From these values an acceptance criteria will be established for the plant unit CRDM stators. 4. Surge Comparison Test Surge testing shall be conducted using 3000 volts DC and shall check the wavef orm of power thru the stator phases. Any sharp or jegged Indication of a trace, regardless of proximity of comparison between traces, shal l be cause f or rejection of the st ator. Stators which include test Instrmneniction may be tested at lower voltage subject to Purchaser approval. Af ter successf ul completion of these tests, the stator shall be varnish vacuum impregnated and baked. During this processing, the stator leadwires must be protected to prevent the varnish for making them inf lexible. Upon completion of j this processing the tests described above shall be reperf ormed and the results recorded. 5. Cooling Jacket Leak and Strength Test The cooling Jacket supplied with the CRDM shall be tested f or leekace and strength against pre-def ined acceptance criteria. B. Hel ium Leak Test A hellun leak test shall be performed on the completed CRDM components that serve as part of the primary system environmental boundary. The maximum acceptable leak rate f or this test shall be 1 x 10- sec/sec/CRU4 total f or al l external leak paths. I ) 1 QCS760.176-16 Amend. 70 Aug. 1982

If it is determined that a dangerous situation would not exist from pressurization of helium gas, the leak test and strength test, as described below, may be combined. However, if they are not combined, the leak test shall be perf ormed af ter the strength test. C. Strength Test ~ A strength test shall be perf ormed on the 'emmpleted CRDM components that serve as part of the primary system environmental boundary and shall be either pneumatic or hydrostetic. This test shall be in accordance with NS-6000 of Section lli of the ASME Boller and Pressure Yessel Code. The f ol lowing general. requirements apply to the strength test: 1 1. Prior to testing, all Interior surf aces shall be cleaned. The Supplier shall prepare and submit a detailed cleaning procedure as part of the Fabrication Plan. 2. The component shall be tested at a minimur, temperature of 700F and the test tar.perature shall be reported in the Fabrication Report. 3. The number of tests above design pressure shall be mi,nimized. 4. Any indication of Icakage in the fluid or gas boundary of the components at other than a flanged joint shall be reported. The location and extent of any leak Indication and the corrective action taken shall be reported in the Fabrication Report. 5. If a hydrostatic strength tesi is perf ormed, following this test the mechanism shall be completely drained and Internal surf aces shall be completely dried by flushing the still-sealed test assembly with heated dry nitrogen or drawing a vacuum. The pressure component being tested shal i be protected from contamination by maintaining the sealed condition end Internal envircnment of dry nitrogen until the helium leak test required by Section Xi lB is perf ormed. J QCS760.176-17 Amend. 70 Aug. 1902

D. CRDM Ferf ormance Tests i i The prototype CRDM shal l be tested to show conf ormance with the design objectives. This testing will be perf ormed in accordance with detailed requirements designated in this specification. For successf ul completion of the work, this testing will demonstrate i compilance with the design objectives with or without any specified addlilonal equipment attached to the mechanism, as applicable. As a minimum, the following parameters will be investigated and reported: 4 1. Maximum possible l if ting f orce exerted; 2. Normal !!f ting f orce exeried; 3. Maximum possible driving-down f orce exerted; ( 4. Normai driving-down f orce exerted; 5. Max! mum torque exerted on the leadscrew; + 6. Normal torque exerted on the leadscrew; f i 7. Total travel during the test f or maximum, and normal ly exerted forces t 8. Stator coil amperage and voltage f or maximum and normally exerted, f orces and drivel ine speeds; i 9. Stator coli anperage, voltage, and resistance as f unctions of l temperature; l 10. Stator coli steady-state temperature variation during operation and hoiding periods; i i J l ) \\t i QCS760.176-18 Amend. 70 Aug. 1982

=_ t l l 11. Stator current decay time end total leadscrew release time as i l e function of tanperatur6, load, statcc power, and [ l misalignment. The unit shall be tested f or celay tima and release time at f our cliferent rotor to motor tube (Index) i i positions and stator to motor tube (Index) positions; } o \\

12. The CRDM scram characteristic; as f unctions of the stator I

l power, rod speed, and load;

13. Mechanism internal environment paraneters including, but not

[ limited to: [ t a. Tanperature v b. Pressure r J c. Contained atmosphere d. Lubrication; i 14 Dynamic response of the CRDM leadscrew to a single pulse from the controller as well as to travel speeds of 0.36 inches / i minute and 9.0 Inches / minute;

15. Mechanism oooling system paraneters, as applicable; l

16. Any other paraneters or f actors that may have an ef fect on the mechanism meeting the design objectives. E. Acceptance Test f 1. Acceptance tests shall be perf ormed on each plant unit CRDM/ l CRD and associated equipment which will establish that the i perf ormance of each unit is within acceptable limits established as satisf actory for the CRBRP mechanisms. i 1 i { 4 l i QCS760.176-19 Amend. 70 Aug. 1982 .,,,.r- ,--._.---.-v _m. --_..,__,.____,y,,,

2. The translating essembly out-motion requirement shall be verified by testing. Testing shall include the three specified modes of Intched, screm and unlatched. The test article shall include the Upper CRDM and leadscrew as a minimum. A mass equivalent to the mass of the remaining translating assembly components shall be attached to the l eadscrew. The specified up force shall be appiled to the bottom of the leadscrew and maintained constant for a stroke of 10 inches at 1011 inches withdrawn and 25 i 1 inches withdrewn f or the latched and scram mode. For the unlatched mode the leadscrew shall be a position, with the pawl above the top leadscrew tooth, such that the impact velocity, when the pawl engages the leadscrew top tooth, is equal or greater then 25 Ips. 3. The OML pawl maximum drag force requirement shall be verified by test. The system shall meet the requirement during inward motion of the leadscrew with the actual friction coef f icient. k i i t l l QCS760.176-20 Amend. 70 l Aug. 1982

ITEM 3 and f ollowing request TEST DATA 1. One of the specif ications f or the mechanism is that under the most unusual conditions the withdrewal speed shall not exceed 73 Ipn. Conf ormance to this requirenent was demonstrated at the vendors f acility as part of the perf ormance test. The maximum withdrewal speed test was run to determine the axial force which could be exerted by the mechanism as a f unction of current and j withdrewal speed bef ore pole slippage occurs. If the speed is increased I or the current decreased beyond the point of pole slippage, the roller nuts will roll out of the leadscrew and the mechanism will screm. The data f rom th is test is shown i n Tabl e QCS760.176-1. At the design condition of 175 volts and 7.2 anps rollout occurs at 43 Ipm. The total force required is comprised of the net weight of translating assembly, friction and drag f orces, and spring f orces f rom the bel lows and scran assist spring. The maximum force at the top of the stroke is 1135 lbs. and the minimum f orce at the botton of the stroke is approximately 400 lbs. As the assembly is withdrawn the scram and bel lows f orces increase. Thus the f orce in Table QCS760.176-1 is dependent on the axial position of the translating assembly when rollout occurs. To exceed the design voltage of 175 volts, a series of significant f ail ures must occur in the controller and M-G sets. If al l of these f ailures occurred at the same time, the maximum voltage which could be applied to the stator is 252 volts. As shown in the data in Table QCS760.176-1, at 258 volts, rol lout wil l occ9r between 60 and 70 Ipm ' If the translating assembly is withdrawn s ess than 10.5 inches where the spring f orces are applied. If the translating assembly is in a normal operating range of 16 Inches to 28 inches withdrawn rollout will occur between 5') and 60 Ipn. Thus the PCRDM meets the design requirement that It shall never be withdrawn at a speed greater than 73 1pm. II. All 18 mechanisms (9 plant units and 9 spares) were acceptance tested. The ecceptance test data show that all 18 mechanisms met all test requi rements. ) s QCS760.176-21 Amend. 70 Aug. 1982 \\

i Ill. To determine the response of the PCRDM to loss of stator coolant flow, a series of tests were run a W-ARD. In these tests the stator winding temperature and outlet coolant temperature were measured as a f unction of time for a variety of coolant flows including complete loss of flow. The results f or a canplete Icss of coolant f low is shown in Figure QCS760.176-6. For this condliton, the maximum stator temperature reached an asymfotic value of 6600F in 250 minutes. It should also be noted that the thermocouple measuring the outlet coolant temperature followed the maximum stator tunperature heat up rate f airly closely. At 260 minutes, power to the stator was turned of f and the stator temperature and outlet coolani temperature were monitored during the cool down, without the benef it of coolant f low. As shown in Figure QCS760.176-6 the maximum stator temperature and outlet coolant temperature dropped rapidly. During this test, the assembly was withdrawn to 36.0 inches and placed in 3-phase hol d. In this condition the maximum spring force was applied J to the driveline, and the maximum heat was generated in the windings. When the maximum stator tcaperature was obtained, the mechanism was drive down to 25 inches withdrawn and back up to 36 inches f ive times to I demonstrate that the mechanism f unctioned properly and did not roll out or scram under these abnormal conditions. The mechanism was then scrammed and the uniatch time and scram time were measured. The results Indicated that the uniatch time was f aster than normal and the scram' time was normal. When the test was completed and the stator had cooled to ambient temperature, the stator winding resistance and Insulation resistance were measured and f ound to be unchanged. l+ was concl uded that the mechanism and stator has f unctioned properly di. ring these abnormal conditions and had suf fered no degradation or loss of operating life. In the plant unit mechanisms there is an operating thennocouple and a spare thermocouple which measures the temperature of the outlet cooling n i trogen. These thermocouples will alarm at 2000F to indicate a reduction in stator cooling and an increase in stator tanperature. At this time some action may be taken to resolve the problem since the mechanism should not operate Indef initely without coolant f low. This conditl'on is not a saf ety probl em but one of degradation of the mechani sn I nsul ati on. ) I h 4 I QCS760.176-22 Amend. 70 Aug. 1982

4... TABLE QCS760.176-1 FJtXIMUM AXIAL FORCE FOR NO POLE SLIPPAGE IN POUNDS Withdr awal 6 mps/ 7 mps/ 8 mps/ 9 mps/ ~ Speed 135 V 170 V 210 V 258 Y 1 2510 2890 3180 3270 t 2270 2700 2990 3180 10 1980 2420 2610 2890 15 1650 2030 2420 2840 20 1320 1700 2230 2610 30 RolIs out' 900 1560 2030 40 RoiIs out 980 1510 50 Rolis out 1080 60 600 I l 70 RolIs out l I l 4 i 4 QCS760.176-23 Amend. 70 Aug. 1982 -_._om...,_. - ~...

r.;e - a e,_ - .4 /t ~,iij f M s... Figure QCS760.176-1 Motor Tube, Hold-Down Ring, F. D. Housing, and Pressure Switch I

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e.. Figure QCS760.176-2 Rotcr Assembly ROTOR TUBE , y RMS ROTOR -9 R ) I RADIAL BEARING ~'l, / y SYNCHRONIZER f BEARING i ? h, tf ; *' i ?. IGN k SEGMENT ARM N y SEGMENT ARM y,

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c '.,;;R b- .i i ROLLER %g) ROLLER ogy.y $, D[ '.rh \\ l' l l ( QCS760.176-25 Amend. 70 ^"o l

< w. . m n oo Figure QCS760.176-3 Statcr-Jacket Assembly i-LIFTING LUG THERMOCOUPLE NITROGEN OUTLET CONNECTOR POWER CONNECTOR 7 O NITROGEN INLET I; i 9,, dJ[. ll l l q %a r.g g> LIFTING LUG r a.

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  • .. i Figure QCS760.176-4 PCRDM and Controller Systen Schtmatic CONTROL ROOM SCRAM SIGNALS (RUN, HOLD, SICNR LATCH, SPEED) 1 I

j ELECTRONICS 3 0 AC 3 0 AC ' SCRAM l l 6 0 SCR's (6 PER M BREAKER -9 PHASE) M n i: M t l 3 0 MOTOR 30 ENj i[ ]Q N s N-3 0 AC p 6 0 AC :: I DC .... c.g <-g 1 MOTOR LINES REDUNDANT XFORMER !P M I i ji _ d, M-G SETS i i !H M i !! W Ly CONTROLLER SYSTEM ARPI DIGITAL ARPI SIGNAL ELECTRONIC READOUT CONDITIONER [% 1 ARPI POSITION 13.3 gfDETECTOR PROBE NET [/ RRPI ELECTRO-RRPI SIGNAL MECHANICAL COUNTER CONDITIONER RMS COILS 1 3 .3 5 RMS ROTOR ' ROTOR ASSY' ( l o STATOR ' NE AC POWER <<^ DC POWER STATOR COILS SIGNALS LEADSCREW g s QCS760.176-27 Amend. 70 Aug. 1982

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