ML20106D277

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Forwards Consistency Review Changes to CESSAR-F & marked-up Affected Pages of Fsar.Addl Changes Will Be Submitted as Soon as Possible & Added in Subsequent Amend to Cessar.One Inconsistency Noted in CESSAR SER (NUREG-0852)
ML20106D277
Person / Time
Site: 05000470
Issue date: 10/22/1984
From: Scherer A
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0852, RTR-NUREG-852 ID-84-061, ID-84-61, NUDOCS 8410250071
Download: ML20106D277 (16)
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C-E Power Systems Tct. 203/688-1911 Combustion Engineering, Inc. Telex: 99297 1000 Prospect Hill Road Windsor, Connecticut 06095 POWER m SYSTEMS ~

STN 50-470F October 22, 1984 LD-84-061 Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 *

Subject:

CESSAR Consistency Review Changes

Dear Mr. Eisenhut:

As a result of a review of the technical specifications for the first System 80" plant, several CESSAR-F chang *>s are found to be necessary.

These changes provide clarification and technical consistency of information given in CESSAR-F. A description of these changes is attached with the marked-up affected pages of the CESSAR FSAR.

Additionally, in this review, one apparent inconsistency involving cechnical information was identified in the CESSAR SER (NUREG-0852).

A suggested correction is, therefore, provided as well.

This package provides one of a series of changes identified in the technical specification review process. Other changes will be forwarded as soon as possible and will be added in a subsequent amendment to CESSAR.

If you have any questions or comments concerning these changes, please contact me or Mr. G. A. Davis of my staff at (203) 285-5207.

Very truly yours, COMBUSTION ENGINEERING, INC.

/ A. E. Scherer Director 8410250071 841022 Nuclear Licensing PDR ADOCK 05000470 A PDR -

AES:jld cc: K. Eccleston (NRC project manager) i

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CESSAR CONSISTENCY CHANGES

~ De's'ign of Structures.- Components. Equipment, and Systems (Chapter 3)

ETable '3.9.1-1 is clarified to indicate that the Primary System hydrostatic test

' and ;1eak-test' design transient cycles are between 120*F and 400'F.

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' Reactor (Chapter 4)

Nable 4.4-9 is changed to delete the word " core" f' rom the average coolant

.enthalpy. The given value'now correctly corresponds to the reactor outlet coolant conditions. Also, the total steam flow per generator is ~ changed to .  ;

' * ,8.59x106 lb/h' tofcorrect a previous' typographical error.

~

, Reactor Coolant System and Connected ' Systems (Chapter 5)

CESSAR.FSAR Table 5.1.1-1 is changed to reflect value of 82x106 lbm/hr for the SG 1A midpoint to correct a previous typographical error.

'CESSAR FSAR Section 5.2.2.4.4 is ' modified to morefaccurately reflect the actual SIS-relief valve design and specificiations.

Section 5.4.13.4.1 is changed to indicate the. actual method used by valve manufacturers to test the primary safety valves.

Figure 5.4.10-2 is changed to reflect the actual installed level program. .The

.new figure is consistent with and bounded by the CESSAR safety analysis.

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Engineered Safety Features ^(Chapter 6)

Table' 6.2.4-1 is" modified to include both post-accident valve position for CH-524 as indicated in the Technical Specifications.

-Instrumentation and Controls (Chapter 7)

Table 7.2-1 is changed to indicate that removal of DNBR and Local Power Density bypass is at 11% power vice > 10 -4%,

c Table 7.3-3 is changed to. indicate that steam generator differential pressure is monitored for EFAS.

4 Auxiliary Systems (Chapter 9)

Section 9.1.4.1.2 item a. is changed to indicate an updated procurement specification. TheoutdatedHolstManufacturersInstitute(HMI-100-74) specification is deleted.

Table 9.3-1 is modified to more accurately depict operating chemistry limits.

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CESSAR SER Suggestion l-.

t SER Section 6.2.1 - A change is suggested to correct an apparent typographical

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error in the description of the Containment Spray System. CESSAR Appendix 6A indicates 58' seconds from CSAS to delivery of flow, not 50 seconds as indicated l in this SER Section paragraph 2.

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( TABLE 3.9.1-1 TRANSIENTS USED IN STRESS ANALYSIS OF C00E CLASS 1 COMPONENTS (Sheet 3 of 3)

Test Condition Occurrence Conditions Primary system 10 primary side cycle rom 15 lb/in.2 to 3,125 lb/in.2 hydrostatic at a semperature between to 400F. These cycles )

are based on one initial hydrostatic test plus a major repair every 4 years for 36 years which includes equipment failure and normal plant cycles. The secondary side of the steam generator is at atmospheric pressure during this test.

13,0 Primary system 200 cycles hom 15 lb/in.2 to 2250 lb/in.2 at a tempera-leak ture between IDOF to 400F, These cycles are based on a l normal plant maintenance operation involving 5 shutdowns

  • per year for 40 years.

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i TABLE 4.4-9 REACTOR COOLANT SYSTEM COMPONENT THERMAL AND HYORAULIC DATA (a)

(Sheet 1 of 2) l Component Data

. Reactor Vessel l

Rated core thermal powe 3,800 Designpressure,Ib/in.y,MWt a 2,500 Operating pressure, 1b/in.2 a 2,250 Coolant outlet temperature, 'F 621.2  !

Coolant inlet temperature, 'F '

564.5 Coolant outlet state 0 Subcooled Total coolant flow, 10 lb/h 164 o average coolant enthalpy niet, Stu/lb 565 Outlet, Btu /lb 645 Averagecoolangdensity Inlet, lb/ft 45.9 3 -

41.2 Outlet, 1b/ft Steam Generators Number of units 2 ,

Primary Side (or tube sides)

Designpressure/teoperaturg,Ib/in.2,j.F 2,500/650 Operating pressure, Ib/in. a 2,250 Inlet temperature, 'F 621.2 Outlet temperature, 'F 564.5

- Secondary (or shell side)

Design pressure / temperature, Ib/in.2a/*F 1270/575 Full load steam pressure / tempera / 1070/552.86 Zeroloadsteampressure,Ib/in.gure,1b/in.2*F a 1,170 4 Total steam flow per gen. , Ib/h 0.00 m d 8.57 4 /#

Full load steam quality, X 99.75 l

', Feedwater temperature, full power, 'F 450 Pressurizer

! Design pressure, 1/ bin.2, - 2,500 L Design temperature, 'F 700 Operating pressure, lb/in.2 a 2,500 l

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l Operatingtemperatup),'F Internal volume (ft 1,800 L

Heaters Type and rating of heaters, kW Immersion /50 Installed heater capacity, kW 1,800 l a. Full power conditions L

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.- PROCESS DATA POINT TA80LATION*

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/ 5.G. 1-A Pump 1-8 R.V. Pump 1-A S.G. 2-A Pump 2-A Pump 2-8 Paraseter Pressuriter Midpoint Outlet Midpoint Outlet Midpoint Outlet Outlet r

L- Data Point 1 2 3 4 5 6 7 8 Fig. 5.1.2_1 Pressure, psia 2250 2235.3 2325.I 2292.2 2325.I 2235.3 2325.1 2325.1 Temperature

  • F 652.7 592.8 564.5 595.8 564.5 592.8 564.5 564.5 i Mass Flow Rate 6- 6 6 6 6 6 6 g l lba/hr -

GaiG 41.0x10 164.0x10 41.0x10 82x10 41.0x10 41.0x10 BA.ox/O' Volumetric Flow 3 3 3 3 3 3

, Rate, gpa -

233.6x10 111.4x10 4i./ 18x103 111.4x10 233.6x10 111.4x10 111.4x10

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c) + 10*F step' change free 553'F, 10 cylces (normal plant variations). '

d) 75'F to 565'F and return to 75'F at a rate of 100*F/hr with pressures at saturation levels for 500 cycles (plant heatup and cool down). i Note: Heat'up and cool down are separate transients, each beginning at l steady state conditions. j e) Pressurize to 1.5 times set pressure at 100*F - 200*F for 10 cycles plus number of hydros conducted prior to valve shipment (hydrostatic l test). '

f) 480 opening and closing cycles to full stem movement (turbine trip).

5.2.2.4.3.3 Environment. The main steam safety valves are designed i to operate in the following environmental conditions:

5.2.2.4.3.3.1 Normal Environment a) 104*F maximum b) Relative humidity 95% at 60*F to 80*F.

c) Fixed mositure content equivalent to 95% relative humidity at 80'F, up to 104*F.

5.2.2.4.3.3.2 Main Steam 1.ine Break (One Occurrence) a) 330*F maximum for 3 minutes b) Relative humidity of 100%.

L t. e 5.2.2.4.4 Safety Injection System Sde4y Valves S r - it. e. 4 -a SI-n5 T h e a c. v e i.e f Th: -i;;;11: :ce: ::fety valves are direct acting, spring loaded, stainless steel valves with enclosed bonnets. The design parameters of these valves are:

213 f }

set pressure 260& psig i rated flow 15 gpm Y

water chemistry 0 - J weight percent boric acid l throat area .023 in 2 design temperature 650*F

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r 5.2.2.4.4.1 ' Valve Operation.

. As the set pressure is reached, the disc raises off the nozzle seat. This lift continues until the valve it fully open at 10 percent acccumulation. The lift decreases as pressure drops until the seat and disc contacts and seals closed. The valve is fully closed at a maximum of 10% below set pressure (10% blowdown).

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5.2.2.4.4.2 Transients. 'h: ci;;;il:creus ==faty valves are designed [

to withstand the following transients without failure or malfunction. l vc0 YDO fr a) 60*F to 444PF in 5 seconds, 469PF to 60*F in 15 minutes for 44 cycles.

J.9 b) 60*F to 350*F in 15 minutes, 350*F to 60'F in ab4rhours for 500 cycles.

c) 120*F to 60*F in 5 seconds, 60*F to 120*F in 15 minutes for MNMF cc o cycles. I 7 h.4 re s.. r 5.2.2.4.4.3 Environment. Thi; si;;ellenese; :sfety- valves are designed i to operate in the following environmental conditions, a) 122*F maximum b) 95% relative humidity at 60*F to 80*F.

c) Fixed mositure content equivalent to 95% RH at 80*F, at t=-evrat-<.s a hve E :

5.2.2.4.4.4 Material Specifications. Material specifications for the primary safety valves are given in Table 5.4.13-1.

Material specifications for the main steam safety valves are given in Table 1 5.0 14. 5. v. s 3 - 2.

th.s. r i. = F Typical materials used for the -iecel-leneces-sefety- valves are:

Body ASME SA351 GR. CF 8M Disc -- Stellite No. 6B Nozzle ASME SA 479 Type 316 with l Stellite Seat.

l l Inlet Stud ASME SA 193 GR. 86.

5.2.2.5 Mounting of Pressure-Relief Devices See Applicant's SAR 5.2.2.6 Applicable Codes and Classification The applicable codes and classifications for the overpressurization protection system are contained in Table 3.2-1. The applicable codes and classification for the secondary safety valves are identified in Section 5.1.4.

5.2-5

5.4.13.4 _ Tests and Inspections The valves are inspected during fabrication in accordance with ASME III  !

Code requirements. l 5.4.13.4.1 Pressurizer Safety Valves The inlet and outlet portions of the valves are hydrostatically tested with het_a90licable section of water at Code.

the ASME the appropriate Set pressure pressures and seatrequired leakag b ~ V (na siAerformed with l steam using a pro-rated spring. Final set pre ts are performed with the_fina rings using either high pressur r low pressure steam l 1 with an frl"' assist device. Final seat leakage ests are performed prior 9 to shi w th the final springs using either hot air or hot nitrogen.

Valve adjustment shall be made to a valve ring setting combination selected to provide stable vg{je operation on the basis of the EPRI Safety Valve Test Program results 5.4.13.4.2 Main Steam Safety Valves The inlet portion of the valve is hydrostatically tested with water in accordance with the ASME Code. Set pressure and set leakage tests are performed using steam. Adjustment is made to provide a valve blowdown ,

meeting the requirement specified in Tatle 5.4.13-2.

.n l (1) CEM-227 " Summary Report on the Operability of Pressurizar Safety Relief Valve in C-E Designed Plants", December 1982.

i 5.4-42 Amendment No. 9 February 27,1984 I

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i 1 0.0 568.3 592.8 REACTOR COOLANT AVERAGE TEMPERATURE, up i

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TYPICAL PRESSURIZER LEVEL SETPOINT PROGRAM ggj 3,4,1g_2

I Abl[ 6.2.4-1 (Cont'd.) (Sheet '4 of 5)

CONIAINNfMI 150LAll0N SV5 FEM Valve Position Primary II Secondary II [5f I3I Closure Penetration Applicable Valve Actuation Actuation Shut- Post- Actuation flee Poises-Systes g4)

Number COC Operatur Mode Mode Normal doien Accident failure Signal _M Source 28 55 SCS Motor R M C 0 or C 0 or C IAI None 30 (A Motor R M C 0 0 or C IAI None 80 (A Motor R R C 0 0 or C IAl None 80 EC 29 55 SIS None M M C 0 or C C IAI Mone N.A. M.A.

Air A R C 0 or C C IC SIAS 5 EA 40 55 CVCS Air A R, M 0 C C TC CIAS/51A5 5 [8 Air A R 0 C C IC CIAS 5 [A 41 55/56 CVCS Mutor R h 0 0 IAl Mone 5 [B None A A C 0 or C 0 or N.A. None N.A. N. A. lI None A A 0 0 or C 0 or C kN.A. None N.A. N.A.

Hand M M C C C N.A. None N.A. N.A.

Hand M M C C C N.A. None N.A. N.A.

43 55 CVC5 Air A NM 0 0 or C C FC CIAS 5 [8 Air A R 0 0 or C C fC CIAS 5 EA 44 55 CVCS Air A R 0 or C C C IC CIA 5 5 (A Air A R, M 0 or C C C IC CIA 5 5 [8 45 55 CVCS None A A 0 or C C C N.A. None N.A. N.A.

Air A N. M 0 or C C C IC CIA 5 5 EA 51 SS CVCS Mutur H H 0 0 0 or C IAI None 5 EA h, Nune A A 0 0 0 or C N.A. None N.A. N.A.

Amendment No. 7

. 48 .

March 31, 1982 l

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TABLE 7.2-1 ( ,_ ,

REACTOS PROTECTIVE SYSTEM 8YPASSES Title Function Initiated By Removed By Notes- t DN8R and local Disable low DNBA and Key-operated switch Automatic if Allows low power i power density high local power (1 per channel) s testing bypass density trips >10 Pressurizer' Disables low pressur- knual switch Automatic if ,

pressure rizer pressure trip, (1 per channel) pressure is bypass SIAS, and CIAS if pressure is >500 psia

<400 psia High log power Disables high logarith- knual switch Automatic if Sypassed during level bypass mic power level trip (1 per channg]) if powgg is reactor startup power is >10 1 <10 1 Disables any given Manually by Same switch Interlocks allow only Trip channel one channel for any bypass trip channel controlled access switch one type trip to be bypassed at one time

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TABLE 7.3-3 l

IGNITORED VARIABLES REQUIRE 6 FOR ESFAS PROTECTIVE SIGNALS C1AS CSAS RAS MSIS SIAS EFAS Pressurizer Pressure 1 3 Containment Pressure ,1 2 1 1 l Stems Generator Pressure 3 y i Refueling Water Tank Level 3 3

Steam Generator Water Level 1 l

1 High

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High-High 3 -

Low M - Q b$tOL I

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9.0 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 9.1.1 NEW FUEL STORAGE i i

See Applicant's SAR. See Sections 4.2.5 and 9.1.4.6 for interface requirements.

9.1.2 SPENT FUEL STORAGE RACKS See Applicant's SAR. See Sections 4.2.5 and 9.1.4.6 for interface requirements.

9.l.3 SPENT' FUEL POOL COOLING AND CLEANUP SYSTEM See Applicant's SAR. See Section 9.1.4.6 for interface requirements.

9.1.4- FUEL HANDLING SYSTEM 9.1.4.1 Desian Bases i

9.1.4.1.1 System The fuel handling system is designed for the handling and storage of fuel assemblies and control element assemblies (CEAs). Associated with the fuel handling system is the equipment used for assembly, disassembly and storage of the reactor closure head and internals. As appropriate, the fuel handling equipment included interlocks, travel limiting features, and other protective devices to minimize the possibility of mishandling or equipment malfunction that could result in inadvertent damage to a fuel assembly and potential fission product release.

The refueling water provides the coolant medium during spent fuel transfer.

The spent fuel pool is provided with a pool coo. ling and purifications system.

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( All spent fuel transfer and storage operations are designed to be conducted underwater to insure adequate shielding during refueling and to permit visual control of the operation at all times. The arrangement of the "uel handling system is shown in Figure 9.1-1.

1' l 9.1.4.1.2 Fuel Handling Equipment

l. The principle design criteria for the fuel and CEA handling equipment i'

(refueling machine, fuel transfer equipment, spent fuel handling machine, l CEA change platform and new fuel and CEA elevators) are as follows:

a. For non-seismic operating conditions, the bridges, trolleys, hoist units, hoisting cable, grapples and hooks conform to the requirements i

of Crane Manufacturina Association of America snacification #70, n l

LHoistE"racturing Institute Soncification HMI' 100-743 -

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.. l TA8LE NO. 9.3-1 (Sheet 1 of 2)

OPERATING LIMITS 1.0 MAKEUP WATER Analysis Nomal Abnormal Chloride (C1) <0.15 ppe < .15 ppe

-Silica (SiO2 ) <0.01 ppe < .02 ppe Conductivity <1.0 pahos/cm < 2 pahos/cm pH 6.0 - 8.0 (1) -

Fluoride (F) (2) < .1 ppe <0.1 ppa Suspended g

Solids < .5 ppe - t i.

2.0 1RIMARY WATER Core Load and Analysis Hot Functionals (3) Initial Criticality Power Operation pH (77*) 9.0 - 10.4 4.5 - 10.2(4) 4.5 - 10.2(4).

Conductivity (5) (5) (5)

Hydrazine 30 - 50 ppe 30 - 50 ppm 1.5 x 0xygen ppe (max. 20 ppm)

Ammonia <50 ppe <50 ppa <0.5 ppe.

i Olssolved Gas --- ---

(6)

Lithium 1-2 p's . 0.2 - 1.0 ppe (7) 0.2 - 1.0 ppe (8)

Hydrogen --- ---

10 - 50 cc (STP)/kg (H2}

0xygen 10.1 ppa 10.1 ppe (I) .,0.1

< ppe l

. Suspended Solids <0.5 ppe, 2 ppe ex. <0.5 ppe, 2 ppe max. <0.5 ppe, 2 ppa max.

l l Chloride <0.15 ppe <0.15 pga <0.15 ppe l Fluoride <0.1 ppe <0.1 ppe <0.1 pps Baron ---

< Refueling <4400 ppe foncentration

- - - -- .-- - . . . - _ , . . . - . - - . . . _ _ _ - . .-. _

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