ML20212P419
| ML20212P419 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/02/1986 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20212N983 | List:
|
| References | |
| NUDOCS 8703160103 | |
| Download: ML20212P419 (83) | |
Text
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IMPROVED DESIGN CONTROL DOCUMENTATION FOR CRYSTAL RIVER UNIT 3 DESIGN BASIS FOR EMERCENCY FEEDWATER SYSTEM The following contains design basis information pertaining to the Plant as of December 10, 1985 (Date of Record).
(
(O. Sh
') DESIGN ENGINEER i/z/ ac
/
DATE
/ E 8b j VERIFICATION ENGINEER DATE Ib> L CTION MANAGER
//2/86 DATE
/
These signatures apply to pages 1 through 49 , Revision 0.
l 8703160103 B70305 PDR ADOCK 05000302 P PDR
Florida CRYSTAL RIVER UNIT 3 3 Power
- c-- Page i of DESIGN 8 ASIS DOCUMENT i Rev. O SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF DESIGN BASIS INDEX FOR EMERGENCY FEEDWATER SYSTEM Section Title Page
SUMMARY
SYSTEM DESCRIPTION 1 DESIGN BASIS FOR EMERGENCY FEEDWATER SYSTEM 4 DESIGN BASIS FOR EMERGENCY FEEDWATER SYSTEM EQUIPMENT 13 Motor and Turbine-Driven Emergency Feedwater Pumps 3A and 3B 13 Motor-Driven Feedwater Pump 3A, Motor and Gear Assemblies 18 Emergency Feedwater Pump 3B Turbine Drive 21
( Chemical Treatment Equipment, Emergency Feedwater System 27 DESIGN BASIS FOR EMERGENCY FEEDWATER SYSTEM VALVES 30 Turbine-Driven and Motor-Driven Emergency Feedpump 30 Auxiliary Feedwater Discharge Isolation Valves (EFV-ll and EFV-14)
Turbine-Driven and Motor-Driven Emergency Feedpump 32 Auxiliary Feedwater Discharge Isolation Valves (EFV-32 and EFV-33)
Chemical Addition Pump External Relief Valve 34 EFIC Control Valves 35 DESIGN BASIS FOR EMERGENCY FEEDWATER INSTRUMENT STRINGS 39 Steam Generator Pressure 39 Operating Range Steam Generator Level 40 Startup Range Steam Generator Level 42 Emergency Feedwater Flow 44
( Condensate Storage Tank Level 45
rioria. CRYSTAL RIVER UNIT 3 Power
- w- DESIGN BASIS DOCUMENT Page 1 of 49 Rev. O SYSTEM NAME: SYSTEM CODE:
SUMMARY
SYSTEM DESCRIPTION The Emergency Feedwater System (EF) is required to assure an adequate feedwater supply to the steam generators to remove reactor decay heat until suitable conditions are attained to start the Decay Heat Removal System. The EF System primarily consists of redundant feedpumps and the Emergency Feedwater Integrated Control System (EFIC) which are required to function during periods when the normal feedwater supply and/or the electrical supply to the vital feedwater auxiliaries has been lost. The EFIC System, a four channel safety grade control system, activates EF System components upon loss of all main feedwater, low level in either steam generator, loss of all reactor coolant pumps, or upon a small break LOCA. EFIC also controls the atmospheric steam dump valves and isolates the affected steam generator in event of a high energy line break. Related EF flow and tank level instrument signals are processed through EFIC for operator information in the main control room and remote shutdown panel. The EF System feedpumps may be supplied from either the condensate storage tank (preferred) or the condenser hotwell, with the water boiled off by the steam generators during cooldown being vented to the atmosphere. The EF System is designed to ANSI B31.1 ES, Seismic Class I.
Piping Line Specifications are per 50-1, 900-1, 600-3, and 125-3.
The following is a brief functional description of the EF System components.
A. Motor Driven Emergency Feedpump 3A (EFP-1)
The Motor Driven Emergency Feedpump receives its electric power through either available offsite power or the emergency diesel generators. The feedpump automatically starts on the loss of plant auxiliary power, tripping of both main feedwater pumps, or a low-low level in the steam generators. Emergency Feedpump 3A is not res. ired for plant startup or normal operation. Motor and gear cooling water is supplied from the Nuclear Services Closed Cycle Cooling System.
B. Turbine-Driven Emergency Feedpump 3B (EFP-2)
The Turbine-Driven Emergency Feedpump provides redundant capacity to the EF System and automatically starts with the motor-driven feedpump. Manual controle provide the operator with the capability of shutting down the pump if the extra feedwater capacity is not required. Emergency Feedpump 3B is not required for plant startup or normal operation.
C. Emergency Feedwater Pump 3B Turbine Drive (EFTB-1)
The Turbine Drive provides rapid startup for Emergency Feedpump 3B.
Turbine steam is supplied by a crosstie with the main steam piping from either steam generator. An alternative source of steam is available from the fossil units, CR-1 and CR-2. A pair of redundant motor-operated steam admission valves control the turbine steam supply and are activated with the motor-driven feedpump.
rioria. CRYSTAL RIVER UNIT 3 O cPower - DESIGN BASIS DOCUMENT Page 2 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF D. Chemical Feed, Emergency Feedwater System (EFT-1, EFMX-1 and EFP-3)
Chemical addition equipment consists of a storage tank with integral mixer and an injection pump. A hydrazine and ammonia solution is added to the feedwater through the suction side of the emergency feedpumps to control steam generator oxygen concentration and pH level.
E. EFIC System Control Valves (EFV-55, EFV-56, EFV-57, and EFV-58)
Feedwater flow control cannot be shared with the main Feedwater System and therefore, four flow control valves are provided for the EF System to properly maintain steam generator feedwater levels. These valves are designed to fail open and the lines are provided with automatic isolation capability if the feedwater level in the steam generators exceeds a high level.
F. Plant Operating Modes
, The Emergency Feedwater System functions during the following plant operating modes:
- 1. Power Operation (Tavg > 2800F, Thermal Power > 5%)
The emergency feedwater pumps are not required to operate but are required to be available during this mode of operation.
- 2. Startup (Tayg > 2800F, Thermal Power 15%)
The emergency feedwater pumps are not required to operate but are required to be available for plant startup. In addition, the emergency feedwater pumps may be used in place of the main feedpumps if desired.
- 3. Hot Standby (Tavg > 2800F, Thermal Power = 0%)
l The emergency feedwater pumps are not required to operate but are required to be available during this mode of operation.
- 4. Hot Shutdown (280 F > Tavg > 200 F, Thermal Power = 0%)
The emergency feedwater pumps are not required to operate but are required to be available during this mode of operation.
- 5. Cold Shutdown (Tavg i 2000F, Thermal Power = 0%)
The emergency feedwater pumps are not required to operate but are required to be available during this mode of operation.
ri.a. CRYSTAL RIVER UNIT 3 Power
.i c- DESIGN BASIS DOCUMENT Page 3 of 49 Rev. 0 6
SYSTEM NAME: SYSTEM COOLE:
- 6. Refueling (Tavg <_ 1400F, Thermal Power = 0%)
The emergency feedwater pumps are not required to operate but aee required to be available during this mode of operation.
- 7. Emergency / Accident EF System emergency feedpumps are both automatically started tm loss of plant auxiliary power, tripping of both of the main feedwa:ar pumps, or on low-low level of a steam generator. The boiling-off of the emergency feedwater in the steam generators is required to reduce the reactor decay heat prior to the start of the Decay Heat Rumoval i System at approximately 2800F and 284 psig reactor coolant conditions. I
- 8. Operational Checks Periodic testing is required to ensure operation of the emergemey feedwater pumps, motor-operated control valves, and various control
\g systems. Testing is accomplished through recirculation piping off the EF pump discharges which feed back to the condensate storage tank (CDT-1).
_ __ _ _ . _ _ _ . . . . _ _ _ _ _ _ - _ _ . . _ . . _ . _ _ . . _ _ _ _ _ _ _ _ . _ . _ _ _ _ ~ . , _ _ _ _ _ - .
- ~ '
norwe CRYSTAL RIVER UNIT 3 Power c- -n.oa DESIGN BASIS DOCUMENT Page 4
OI Rw. g 49 SYSTEM NAME: SYSTEM CODE: ,1 EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON DESIGN BASIS FOR EMERCENCY FEEDWATER SYSTEM The Emergency Feedwater 1. MW Auxiliary 'Feedwater The EF Sys tem provides a System (EF) consists of System Reliabili~ty safety related source of two full capacity Analysis for CR-3, feedwater to the steam independent systems which dated Oct. 1979. generators to remove include two pumps and 2. MW Standard Guide reactor decay heat in associated valves and Specification, NSS the event of loss of main piping. It is designed Auxiliary Feedwater feedwat e r.
to remove reactor decay System Requirements ,
heat through the Specification No.
injection of feedwater 2022/0870, Issue Date -
into the steam generators August 11, 1970.
until suitable conditions 3. MW System Description exist to initiate the -
for EF System for CR-3,
( Decay Heat Removal Doc. No. 15-1121209-04, System. 8 /30 /82.
- 4. FSAR, 7/85, Section 10.2 for reference.
The EF Sys tem is auto- 1. MW Auxiliary Feedwater Thess co dicions all matica11y started by the System Reliability relate to plant emergency Emergency Feedwater Analysis for CR3, dated conditiora in that Integrated Control System Oct. 1979. odequate feedwater is not (EFIC) on loss of plant 2. MW Standard Guide reaching the steam auxiliary power, tripping Specification, NSS generators.
of both main feedwater Auxiliary Feedwater pumps, or a low-low level System Requirements , f indication in the steam Specification No.
generators at the 2022/0870, Issue Date - ,
setpoints listed on August 11, 1970.
Table 1. (See EFIC 3. NUREG 0578, Branch .,
Design Basis Document - Technical Position A&B '
B&W 51-1146561). 10:1,'Rev. 1.
- 4. Sys tem Description,
- Emergency Feedwater Sys tem, FPC/CR3, l 11/3/75 for reference.
l 5. FS Ait, 7/85, Section 10.2 for reference.
, b. Post EFW Upgrade Limits and Precautions, B&W i No. 51-1153083-01, 6/27/85.
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.I -
ri.,w. C'RYSTAL RIVER UNIT 3 rower 5 49
- a . c~a-' DESIGN BASIS DOCUMENT .Page of Rev. 0 SYSTEPt NAMi!: SYSTEM CODE:
e EMEACENCY FEEDWATER SYSTEM EF TABLE 1 I
SYSTDi DESIGN BASIS STEAM CENERATOR LEVEL SETPOINTS Actual Level Instrument Above Tube Level @ Sheet @
Maximum Minimum. Normal Normal Normal Description <
Setpoint Seepoin_t Setpoint Seepoint Setpoint j Low 'JG Level I ti tiate 7.41". 4.56" 6" 6" 12" EFW Control Level
- N/A N/A 24" 24" 30" f
Natural Circulation 375" 285" 285" 279" 285"
- [ Control Level Steam Generator overfill '339" 388" 389" 383" 389" (EIW Isolation)
SG Overfill Rese: ?89"- 106" 352" 346" 352" ECCS Fill 1.iutt** 375" 360" 375" 369" 375" s
A l h -
- Accident envitorusents are not applicable to this measurement since CR-3 pro adures require the RC pumps to be tripped on an ESFAS HPI actuation (small break LOCA) .
- This setpoint is manually selected following a LOCA to assist in establishing naturel circulation if part of the primary system is voided.
All level setpoin.s refer to the equivalent height of a saturated water column (1065 pais) referen:ed from et.c top of the lower tube sheet. It shouM l'e noted that the 1 m st low range instrument sensing tap is at an elevatica of s" above the top of lowne tube sheet.
s me
rww. CRYSTAL RIVER UNIT 3
, 57.5 DESIGN BASIS DOCUMENT Page 6 of 49 Rev. O SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE 4 REASON The EF System is designed 1. General Design Redundant 100% capacity with two 100% capacity Criterion No.19, pumps with different redundant f eed pumps : Federal Register dated power sources are electric motor-driven 7/11/67, Part 50, provided to enhance both EFP-1 and steam turbine Appendix A. system availability and driven EFP-2. 2. B&W System Description reliability.
for EF System for CR-3, Doc. No. 15-1121209-04, 8 /30 /82.
- 3. System Description, Emergency Feedwater Sys tem , FPC/CR3, 11/3/75 for reference.
Automatic initiation will 1. General Design Automatic start close the circuit breaker Criterion No. 24, capability allows the star ting EFP-L ; ES-BUS-3 A Federal Register dated pump to reach full flow providing power for the 7 /11/67, Part 50, capacity as quickly as pump motor. The bus is Appendix A. possible. The emergency g backed by Emergency 2. NUREG 0578, Branch diesel generators provide Diesel Generator 3-A. Technical Position A&B, power for the pump motor 10-1, Rev. 1. in the event of loss of
- 3. NUREG 0787, II.E.1.2, offsite power.
Part I (4)(6) .
- 4. B&W Sys tem Description for EF System for CR-3, Doc. No.15-1121209-04, 8 /30 /82.
- 5. FSAR, 7/85, Section 10.2 for reference.
Steam to power EFP-2 is 1. B&W Auxiliary Feedwater Starting procedure for extracted insnediately System Reliability the turbine driven EW downstream from either Analysis for CR-3, pump maximizes steam generator. It dated Oct. 1979. reliability. Automatic l passes through a normally 2. MAR 80-11-48-01 to -03. start capability allows l open, DC powered stop 3. System Description, the pump to reach full check valve (MS-55, 56) Emergency Feedwater flow capacity quickly, and a check valve Sys tem, FPC/CR3,
~
(MS-186, 187). Automatic 11/3/75 for reference.
I initiation of the EF 4. FSAR, 7/85, Section i
System will open steam 10.2 for reference.
valve ASV-5 and ASV-204 to start Ermergency
( Feedwater Pump 3B Turbine Drive (EFT 5-D .
f a
l
l rioria. CRYSTAL RIVER UNIT 3 Power
. c-- DESIGN BASIS DOCUMENT Page 7 of 49 Rev. 0 SYSTEM NAddE: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON The turbine drive is 1. B&W Auxiliary Feedwater Steam supply arrangement powered by available System Reliability permits the use of the steam generator cooldown Analysis for CR-3, turbine-driven feedpump steam or from fossil dated Oct. 1979. even when steam is not plants, CR-1 and CR-2. 2. B&W System Description available from the steam Gate valves in the for EF System for CR-3, generators. It may be auxiliary steam piping Doc. No. 15-1121209-04, used on emergency and permit fossil plant steam 8 /30 /82. non-emergency occasions .
to be utilized if 3. Sys tem Description, required. Emergency Feedwater System, FPC/ CR3, 11/3/75 for reference.
- 4. FSAR, 7/85, Section 10.2 for reference.
Indication of EF Sys tem 1. System Description for Operator interf ace is feedpump startup, EF System for CR-3, B&W desirable to Lnprove EF flowrate, and the Doc. No. 15-1121209-04, System flexibility by:
feedwater level in the dated 8/30/82.
(
steam generators is 2. System Description, a) Minimizing plant transmitted to the Emergency Feedwater impact in case of control room with System, FPC/CR3, inadvertent actuation.
provisions for manual 11/3/75, for reference. b) Saving time during pump control override 3. FS AR, 7/85, Section plant emergency capability. 10.2 for reference. condi tions .
c) Ability to shutdown a feedpump if their combined capacities are not required.
The EF System is designed 1. B&W Standard Guide Rapid startup requirement to provide a minimum flow Specification, NSS maintains continuity in of 740 gpm (emergency Auxiliary Feedwater the transition from
( feedpump design flowrate) System Requirements, normal operation to
! 40 seconds af ter system Specification No. forced decay heat removal actuation. 2022/0870, Issue Date - and to eliminate the Augus t 11, 1970. possibility of the steam
- 2. GAI Let ter No. B&W-915, generators boiling dry.
l dated Feb. 18, 1975. The 40 seconds include i
- 3. CR-3 LOFW-EFW Upgrade, instrumentation delay, i B&W Doc. No. emergency diesel or steam l
51-1125565-00, dated turbine startup, control 8/28/81. valve stroke times , and
- 4. B&W Sys tem Description feedpump acceleration for EF System for CR-3, time.
Doc. No. 15-1121209-04, 8 /30 /82.
rioria. CRYSTAL RIVER UNIT 3 Power w,o,.- DESIGN BASIS DOCUMENT Page 8 of 49 Rev. O SYSTEM NA,ME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Maximum EF System flow to 1. System Description for Maximum flow is based on a single steam generator EF System for CR-3, B&W the tube vibration from both emergency Doc. No. 15-1121209-04, crossflow velocity limit feedpumps is 1175 gpm. dated 8/30/82. of 5 f t/see which cannot
- 2. MAR 80-10-66-04. be exceeded at any pressure. Value is used for sizing EFIC control valves EFV-55, -56, -57 and -58.
The primary water source 1. B&W Standard Guide The Condensate Storage for both pump trains of Specification, Nuclear Tank supply is preferred the EF System is the Auxiliary System Piping because the condensate Seismic Category I (Functional), water is processed and Condensate Storage Tank Specification No. treated before storage, (cur-1). A backup supply 2023/0370, Issue Date - thereby offering better is the non-seismic main March 16, 1970. water quality. There is condenser hotwell. 2. GAI Let ter No. B&W-845, also a possibility of Normally closed de dated Feb. 12, 1974. contamination in the powered valves EFV-1 and 3. B&W Auxiliary Feedwater condenser hotwell due to EFV-2 are used to draw System Reliability seawater leakage. The suction from the Analysis for CR-3, hotwell source allows the condenser hotwell. dated Oct. 1979. system to be used for
- 4. B&W Sys tem Description normal feedwater supply for EF System for CR-3, during plant heatup and Doc. No. 15-1121209-04, provides a closed cycle.
8 / 30 /82 .
Suction strainers were ECN 2373A dated 4/5/76. Slip-on flanges and added to both emergency temporary strainers were feedpumps EFT-1 and used for the initial EFP-2. startup and testing of the EF Sys ten.
DC powered valves EFV-1 FPC Interof fice The secondary feedwater and EFV-2 are locked out Correspondence f rom C. C. source is available after in their normally closed S trempke/C. B. Doyel to the power is reinstated posi tions . G. Hebb dated manually. Control may be September 28, 1984. from either the Remote
~
Shutdown Panel or the Control Room as plant conditions dictate.
AC powered valves EFv-3, FPC Interof fice Valves are chained and
-4, -7, and -8 have their Correspondence from C. C. locked open to ensure motors disconnected in Strempke/C. B. Doyel to feedwater flow (valve their normally open G. Hebb dated failure and resulting pos itions . September 28, 1984. loss of system capability is eliminated).
rioria. CRYSTAL RIVER UNIT 3 Power
, w.- .- DESIGN B ASIS DOCUMENT Page 9 of 49 Rev. 0 SYSTEM NAAAE: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE ' REASON Both the Condensate 1. B&W 1etter from J.D. 150,000 gallons of Storage Tank and the main Carlton to C.E. Thomas coolant will remove decay condenser hoewell contain dated 10/13/67, B&W heat and pump produced a minimum reserve of File 12E38. heat from two RC pumps 150,000 gallons. 2. B&W Auxiliary Feedwater for approximately System Reliability 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor Analysis for CR-3, shutdown.
dated Oct. 1979.
- 3. Condensate Storage Tank Capacity, B&W Doc. No.
32-1131705-00, 8/18/81.
- 4. System Description for EF System for CR-3, B&W Doc. No. 15-1121209-04, 8 /30 /82.
- 5. FSAR, 7/85, Section 10.2 for reference.
The EF System is provided 1. B&W Standard Guide Catalyzed hydrazine and with a 100 gal. Chemical Specification, Nuclear ammonia are required to 4
Storage Tank (EFT-1) with Auxiliary System Piping maintain a low dissolved Integral Mixer (EFMX-1) (Functional), oxygen level of 7 ppb and Chemical Injection Specification No. (max.) and an adjusted pH Pump (EFP-3) . 2023/0370, Issue Date - of 9.3 - 9.5 for the March 16, 1970. emergency feedwater when
- 2. GAI Letter No. B&W-845 supplied from the dated Feb. 12, 1974. Condensate Storage Tank.
The EF System feedpump 1. B&W System Description Either pump is sized to discharge piping is for EF System for CR-3, provide the minimum cross-tied to both steam Doc. No. 15-1121209-04, feedwater . flow to both generators. Crossover 8 /30 /82 . steam generators, thereby line valves EFV-11, -14, 2. System Description, enhancing system
-32, and -33 are provided Emergency Feedwater operability.
to as sure proper Sys t em , FPC/CR-3, feedwater flowpaths. 11/3/75 for reference.
- 3. FSAR, 7/85 Section 10.2 for reference.
EF System valves EFV-11, MAR 80-10-66-04 Valves were upgraded to
-14, -32 and -33 have assure operability under been upgraded to all plant co ndi tions .
Seismic I requirements .
l
This paga follovad by page 10a.
rioria. CRYSTAL RIVER UNIT 3 Power cm.- DESIGN BASIS DOCUMENT Page 10 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDRATER SYSTEM EF PARAMETER SOURCE ~ REASON The discharge piping of 1. General Design Recirculation piping is both emergency feedpumps Criterion No. 25, required to protect the are provided with Federal Register dated feedpumps during low-flow recirculation piping back 7 /11/67, Part 50, or no-flow (testing) to the Condensate Storage Appendix A. ope ration.
Tank. 2. Letter from T.R.
Kernkamp (I-R) to J.
Colby (FPC) dated March 5, 1976.
- 3. Sys tem Description, Emergency Feedwater System, FP C/ CR-3, 11/3/75 for reference.
- 4. FSAR, 7/85 Section 10.2 for reference.
Emergency feedwater 1. B&W Standard Guide Feedwater injection in enters the Steam Speci fic a tion, NSS the superheater section Generators (RCSG-1 A and Auxiliary Feedwater is required for proper
( RCSG-1B) auxiliary System Requirements, thermal circulation.
feedwater nozzles located Specification No.
in the steam generator 2022/0870, Issue Date -
superheater section. Augus t 11, 1970.
- 2. Sys ten Des cription, Emergency Feedwater System, FPC/ CR3, 11/3/75 for reference.
i 3. FS AR, 7/85, Section 10.2 for reference.
Flow is regulated by EFIC MAR 80-10-66-04. Flow control valves System control valves EFV-55 through -58 EFV-55, -56, -57, and provide an independent
-58. emergency feedwater flow control systen.
The EFIC System Control 1. General Design Valves are designed for valves are designed to Criterion No. 26, fail-open condition to fail opened. Federal Register dated prevent interruption of l
7/11/67, Part 50, feedwater flow to the
~
! Appendix A. steam generators. This
( 2. MAR 80-10-66-04. greater flow condition i
will be isolated if the j feedwater level in the steam generators exceeds a high level .
l l
, This pags followsd by pags 11.
rioria. CRYSTAL RIVER UNIT 3 9cPower .- DESIGN BASIS DOCUMENT Page 10a Of 49 "**- 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON The EF System is B&W Sys tem Description Constant cycling of the designed to minimize for EF System for CR-3, control valves will cycling of the EFW Doc. No. 15-1121209-04, reduce their reliability.
control valves during 8 /30 /82, normal plant operation when the EF System is not in operation.
The EF System is provided B&W Sys tem Description The dump valve controls with an atmospheric dump for EF System for CR-3, the cooldown rate of the valve. Doc. No. 15-1121209-04, OTSGs and also has manual 8/30/82. override capability.
Water chemistry B&W System Description These water conditions recuirements for the for EF System for CR-3, are necessary to prevent Emergency Feedwater Doc. No. 15-1121209-04, undesirable chemical System are shown on 8/30/82. reactions taking place Table 4. between OTSG material and water contaminants.
t
- .m-. . -- , ___
rioria. CRYSTAL RIVER UNIT 3 cU1 DESIGN BASIS DOCUMENT Page 11 of 49 Rev. 0 SYSTEM NAJAE: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON The EF System is designed 1. CR-3 LOFW-EFW Upgrade, The minimum EF flow of to supply a minimum B&W Doc. 51-1125565-00, 740 gpm is assumed in the feedwater flow to the dated 5/22/81. B&W analysis to be steam generators of 2. System Description for delivered to either one 740 gpm, with a total EF System for CR-3, B&W or both steam generators dynamic head of 3000 ft. Doc. 15-1121209-04, at EF System initiation.
at a design temperature dated 8/30/82. Dynamic head is based on of 2000F. 3. System Description, the maximum steam Emergency Feedwater generator operating System, FPC/CR3, pressure of 1050 psig 11/3/75 for reference, plus suitable design
- 4. FSAR, 7/85, Section margin. Design 10.2 for reference. temperature is based on the maximum fluid operating temperature of 1100F plus suitable design margin.
The EF System is 1. B&W Standard Guide The EF System codes, fabricated per the Specification, Nuclear temperatures, pressures, requirements of Line Auxiliary System Piping and fluid requirements Specs. 50-1, 125-3, (Functional), are compatible to those 600-3, and 900-1. Specification No. of the listed piping line 2023/0370, Issue Date - specifications.
March 16, 1970.
- 2. GAI Specification R0-2891, Rev. 8, for reference.
The EF System is 1. General Design The EF System is classified as Essential Criterion No. 15, essential .to the safe Services (ES) piping and Federal Register dated shutdown of the plant is designed, fabricated, 7/11/67, Part 50, when under adverse erected, and tested in Appendix A. conditions. Code accordance with ANSI 2. FSAR, 7/85, Section determined to be in i B31.1.0, 1967 Edition. 10.2 for reference, compliance with i 10CFR50.55a guidelines at the time of issuance of the construction permit for CR-3 (9/25/68).
l L
rioria. CRYSTAL RIVER UNIT 3
. c ." DESIGN BASIS DOCUMENT Page 12 OI 49 Rew 0
SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON ISI requirements for the 1.10CFR50.55a Codes and Code determined to be in EF System are per the Standards. compliance with ASME Code,Section XI, 2. FPC Letter No. GAI 10CFR50.55a guidelines at 1974 Edition through 0736, dated 7/12/82, the time of startup and Summer of 1975 Addenda, Design Modification testing for CR-3.
and 1977 Edition through Guidelines.
Summer of 1978 Addenda for articles IWA-4400,
-4600, and -7000.
Modifications made on the FPC Letter No. GAI 0736, Modifications to existing EF System shall be in dated 7/12/82, Design systems are to be made accordance with ANSI Modification Guidelines. per the original B31.1.0, 1967 Edition. construction codes.
The procurement of new 1. FPC Letter No. EF System requirements equipment for the EF GAI-0736, Design are in compliance with System (piping, valves, Modifications ASME Section III, Class 2 tanks, etc.) shall be in Guidelines, dated and 3, and ANSI B31.1, i' accordance with Section 7/12/82. non-safety equipment III of the latest ASME 2. Reg. Guide 1.26, Feb. guidelines identified in Code for Classes 2 & 3 1976, Rev. 3, Classifi- Reg. Guide 1.26.
and ANSI B31.1 for cation Standards for non-safety equipment, as Components of Nuclear noted on Flow Diagram Power Plants.
FD-302-082, Rev. 22.
The EF System safety- 1. B&W Standard Guide The function of the EF related components are Specification, Nuclear System is essential to designed to Seismic I Auxiliary System Piping the safety of the plant.
requirements. (Functional),
Specification No.
2023/0370, Issue Date -
March 16, 1970.
- 2. General Design Criterion No. 2, Federal Register dated 7/11/67, Part 50, Appendix A.
. 3. Safety Guide 29, 6/7/72, Seismic Design Classification.
Florida CRYSTAL RIVER UNIT 3 Power
, cm.. DESIGN BASIS DOCUMENT Page 13 of 49 Rev. O SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON DESIGN BASIS FOR EMERGENCY FEEDWATER SYSTEM EQUIPMENT EQUIPMENT TITLE: MOTOR-AND TURBINE-DRIVEN EMERGENCY FEEDWATER PUMPS 3A and 3B TAG NO.: EFP-1 and EFP-2 Two 100% capacity 1. General Design The EF System is designed feedpumps are provided Criterion No. 20, with one, 100% capacity for the EF System. Federal Register dated motor-driven feedpump 7/11/67, Part 50, with power source Appendix A. redundancy provided by
- 2. System Description, the emergency diesel Emergency Feedwater generators and a 100%
System, FPC/CR-3, capacity turbine-driven 11/3/75 for reference. feedpump powered by steam
, 3. FSAR, 7/85, Section generator cooldown steam 10.2 for reference. or fossil plant auxiliary steam from units CR-1 and CR-2.
Design Temperature 32 - 1200F 1. Standard Engineering Temperatures are based on Practice. ambient conditions for
- 2. GAI B/M No. 3RC-9, P.O. the atmospheric No. PR-3 1374 for Condensate Storage Tank reference. (CDT-1) and the operating l 3. R0-2931 Rev. B, for temperature of 1060F for l
reference, the condenser hotwell plus suitable design margin.
rioria. CRYSTAL RIVER UNIT 3 Power c-.- DESIGN B ASIS DOCUMENT Page 14 Of 49 R'V-0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Design Capacity 740 gpm (max.) @ 4050 rpm 1. B&W Standard Guide The required EF System Speci fic a tion, NSS flow of 740 gpm is for Auxiliary Feedwater decay heat removal to System Requirements, either one or both steam Specification No. generators at EF System 2022/0870, Issue Date - initiation.
August 11, 1970. (P/P = 0.43 forty
- 2. Letter from R.W. seco$ds after shutdown).
McCracken (I-R) to C.H.
Thompson (FPC) dated June 23, 1970,
- 3. I-R Pump Curve N-184 (Rev.) dated 7/30/70.
- 4. CR-3 LOFW-EFW Upgrade, B&W Doc. 51-1125565-00, dated 5-22-81.
g 5. GAI B/M No. 3RC-9, P.O.
No. PR-3 1374 for reference.
20 gpm (recirculation) Letter from R.W. McCracken Flow orifice furnished by (I-R) to C.H. Thompson Ingersoll-Rand to provide (FPC) dated June 23, 1970. 20 gpm flow to protect each pump at low-flow or no-flow (testing) conditions.
Design Modification Temporary Globe 1. ECN 2905, Rev. A, dated Globe valves temporarily Valves May 20, 1976. replaced the old orifices
Permanent recircula- Kernkamp (I-R) to J. Rev. A deleted the valves tion orifice Colby (F C), dated when the new orifices (70 gpm) March 5, 1976. were obtained. The new
- 2. ECN 2351, Rev. A, dated orifices were required March 19, 1976. due to excessive pump discharge temperatures
! during no-flow (testing) conditions.
rioria.
Power CRYSTAL RIVER UNIT 3 c .- DESIGN BASIS DOCUMENT Page 15 Of Rev.
49 O SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE '
REASON 370-375 gpm (min.) @ 1. "Feedwater System Original feedpump 1080 rpm Design Criteria", capacity requirement just established by B&W, prior to the transfer of
- 2. I-R Pump Curve N-184 decay heat removal to the (Rev.) dated 7/30/70. Decay Heat Removal
- 3. GAI B/M No. 3RC-9, P.O. System. This minimum No. PR-3 1374 for flow is retained for reference. conservatism.
- 4. R0-2931, Rev. B for reference.
Design Modification 1. Letter No. GAI-380 Reduced steam generator 320 gpm (min.) dated March 18, 1970. minimum feedwater flow is
- 2. GAI memo by R.H. based on a reduction in Kreisinger with F. the decay heat (previous Norman (B&W) dated values were based on March 25, 1970. infinite irradiation) and also that cooldown cannot
( be maintained at 100oF per hour continuously.
Operating Conditions TDH - 2875 ft. 1. GAI Calculation, Pump- Original discharge Turbine Performance pressure equal to the Requirements, dated system friction losses 4/8/69. plus the steam generator
- 2. R0-2931, Rev. A for operating pressure of reference. 910 psig.
Design Modification 1. GAI Calculation EF-1, Pump TDH requirements TDH - 3000 ft. Work Order 4203, dated were revised to provide
- 6/3/70, sufficient margin for
- 2. Letter from R.W. normal pump wear.
i McCracken (I-R) to C.H.
Thompson (FPC) dated June 23, 1970.
- 3. I-R Pump Curve N-184 (Rev.) dated 7/30/70.
j . 4. R0-2931, Rev. B for I reference.
l I
l
rioria. CRYSTAL RIVER UNIT 3 c . DESIGN BASIS DOCUMENT Page 16 f "'#'
. 49 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE ' REASON NPSHR - 20.5 ft. 1. Letter from R.W. Ingersoll-Rand NPSH McCracken (I-R) to C.H. requirements for adequate Thompson (FPC) dated pump operation. GAI June 23, 1970. designed pipe routing
- 2. I-R Pump Curve N-184 pressure drop calculation (Rev.) dated 7/30/70. shows that NPSHA > NPSHR
- 3. GAI Calculation EF-3, as follows:
Work Order 4203, dated 10/3/70. Flow NPSHA 300 gpm 49.85 ft.
500 gpm 47.01 ft.
700 gpm 40.44 ft.
Code / Seismic Class ASME Section VIII 1. General Design Code applicable to system Division I (casing) Criterion No. 2, design at the time of Seismic Class I Federal Register dated startup and testing for i 7/11/67, Part 50, CR-3. EF System Appendix A. components are critical
- 2. Safety Guide 29, for plant safety.
6/7/72.
- 3. R0-2931, Rev. B for reference.
Pump Type Single Suction, In-Line 1. Engineer's Judgement. Type of pump is Multi-Stage; Ingersoll- 2. I-R Proposal No. acceptable for EF System Rand Model 3X9N-7 ATL-4787-13 dated application.
January 19, 1970.
Design Modification Ingersoll-Rand 1. Letter from R.W. Revised pump is better Model 4X9N-7; McCracken (I-R) to C.H. suited for EF System (I-R Drawings Thompson (FPC) dated applications and future C-4X9-7N86X2-B and May 15, 1970. maintenance
. C-4X9-7N86X1-B) 2. Letter from W.S. considerations. Model O'Brien (FPC) to E.R. 3X9N-7 may be dropped Hottenstein (CAI) dated from I-R's line thereby May 29, 1970. causing future spare
- 3. GAI B/M No. 3RC-9, P.O. parts problems.
No. PR-3 1374 for reference.
rioria. CRYSTAL RIVER UNIT 3 Power o cm.- DESIGN BASIS DOCUMENT Page 17 of 49 Rev. O SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDRATER SYSTEM EF PARAMETER SOURCE ; REASON Pump Bedplate 1. Letter from D.L. Finch A heavier baseplate for Modification (I-R) to B.R. Wheelock the Model 4X9N-7 pumps (GAI) dated July 17, was required for I-R to 1970. accept the high nozzle
- 2. GAI memo from B.R. loads which are predicted Wheelock to E.R. at both the suction and Hottenstein dated discharge connections.
December 14, 1970.
- 3. Letter No. FPC-2843 dated December 14, 1970.
- 4. Letter from R.W.
McCracken (I-R) to C.H.
Thompson (FPC) dated January 11, 1971.
Pump Bearing Cooling
( Pump bearing cooling 1. Letter from D.L. Finch Pumps were designed to recommended if operating (I-R) to E.R. operate without bearing temperature exceeds Hottenstein (GAI) dated cooling water; however,
- 1650F. August 18, 1970. bearings are found to
- 2. Letter from T.R. heatup excessively when
! Cooling Flow - 5 gpm Kernkamp (I-R) to J. the pumps are in the Colby (FPC) dated recirculate mode.
Pressure Drop - 5 psi March 5, 1976. Bearing cooling water is
- 3. MAR-79-12-88-00 supplied to the feedpumps by routing seal water through existing but previously. unused bearing l coolers and then returning to the seals.
Materials - Casing Cast Steel - ASTM SA-217 1. Industry Standard. Vendor material is l
Grade C5 2. GAI B/M No. 3RC-9, P.O. compatible with EF System No. PR-3 1374 for fluid type and pressure reference, and temperature requirements.
l Environmental Conditions I
Accident (6 months) - Environmental and Seismic Pumps are located on N/A Qualification Guide Intermediate Building el.
Specification and Data, 95'-0", Environmental 40 yr. (Normal SP-5095, 4/29/83. Zone 14.
Operating) -
1.0 x 104 Rads l
rioria. CRYSTAL RIVER UNIT 3 Power c .--a DESIGN BASIS DOCUMENT Page 18 OI Rev.
49 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE " REASON EQUIPMENT TITLE: MOTOR-DRIVEN FEEDWATER PUMP 3A, MOTOR AND GEAR ASSEMBLIES TAG NO.: EFP-1 Motor-Driven Feedwater 1. I-R Proposal No, Motor and gear assemblies Pump 3A is provided with ATL-4787-13, revision were sized for the 100%
an electric motor and dated March 10, 1970. capacity Motor Driven gear reducer assemblies. 2. Ingersoll-Rand Drawing Feedwater Pump 3A.
No. C-4X9-7N86X2-B.
- 3. GAI B/M No. 3EJ-3, P.O.
No. PR-3 1197 for reference.
- 4. GAI B/M No. 3RC-9, P.O.
No. PR-3 1374 for reference.
( Motor Power Data 700 hp I-R Proposal No. Motor power required for ATL-4787-13 dated January the I-R Model 3X9N-7 19, 1970. pump.
Design Modification 1. Letter from R.W. The revised I-R Model 800 hp (Electric McCracken (I-R) to C.H. 4X9N-7 pump requires 757 Machinery Mfg. Co. Thompson (FPC) dated BHP to meet the EF Sys tem Model IC, Frame June 23, 1970. requirements.
2419-S) 2. Letter from W.F. Pflum, Jr. (GAI) to C.R. Boese (E-M) dated Augus t 19, 1970.
- 3. Letter from W.F. Pflum, Jr. (GAI) to S.W.
I Howard (E-M) dated September 16, 1970.
- 4. GAI B/M No. 3EJ-3, P.O.
No. PR-3 1197 for reference.
Motor Load Inertia 180 lb-ft2 1. Letter from S.W. Howard Load inertia value is l
(E-M) to W.F. P flum, required for pump Jr. (GAI) dated August starting duty rating.
28, 1970.
- 2. Letter from W.F. Pflum, Jr. (GAI) to S.W.
Howard (E-M) dated September 16, 1970.
noria. CRYSTAL RIVER UNIT 3 cI.1 DESIGN BASIS DOCUMENT Page 19 of 49 Rev.
O I SYSTEM NASAE: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Motor Cooler Flow - 45. 3 gpm 1. Electric Machinery Mfg. Required motor vendor's Pressure Drop - 2.6 psi Co. Drawing No. cooling water flow based 123C493. on cooling water
- 2. GAI B/M No. 3EJ-3, P.O. conditions of 1050F and No. PR-3 1197 for 200 psig as supplied from reference. the Nuclear Services Closed Cycle Cooling System (see SW System DBD).
Gear Data 800 hp rating, 1. Letter from R.W. Gear assembly meets motor 1 to 2.2413 ratio McCracken (I-R) to C.H. and pump design criteria.
(Philadelphia Gear Corp. Thompson (FPC) dated Model 209 HSD) June 23, 1970.
- 2. Philadelphia Gear Corp.
< Drawing No.
03-051-0238-4.
- 3. GAI B/M No. 3RC-9, P.O.
No. PR-3 1374 for reference.
Gear Oil Cooler l
l Flow - 9 gpm 1. Philadelphia Gear Corp. Required vendor's cooling Pressure Drop - 2 psi Drawing No, water flow requirements 03-051-0238-4. based on cooling water
- 2. GAI B/M No. 3RC-9, P.O. conditions of 1050F and No. PR-3 1374 for 200 psig as supplied from reference. the Nuclear Services Closed Cycle Cooling System (see SW System DBD).
Motor and Gear Seismic Class
. Seismic Class I 1. General Design EF Sys tem components are Criterion No. 2, critical for plant Federal Register dated safety.
7/11/67, Part 50, Appendix A.
- 2. Safety Guide 29, 6/7/72.
- 3. R0-2931, Rev. B and R0-2840, Rev. D for reference.
l _ _ _ .. ____ _ __
rioria. CRYSTAL RIVER UNIT 3 O cE".1 DESIGN BASIS DOCUMENT Page 20 I
49 N'*
0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE ' REASON Environmental Conditions Accident (6 months) - Environnental and Seismic Motor and gear are N/A Qualification Guide located on Intermediate Specification and Data, Building El. 95'-0",
40 yr. (Normal SP-5095, 4/29/83. Environmental Zone 14.
Operating) -
1.0 X 104 Rads
(
l l
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,, , -.-- ,- ,_,._n,._,r,,..,7-w,.- , , &
-ea-_.,,,._-,m,,-.- -,-.,.--.,--.-----.----,..--,--=-r mon,---g------
=. _ __ _. _ _
rioria.
Power CRYSTAL RIVER UNIT 3 c -- DESIGN BASIS DOCUMENT Page 21 Of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON EQUIPMENT TITLE: EMERGENCY FEEDWATER PUMP 3B TURBINE DRIVE TAG NO.: EFTB-1 One steam powered turbine 1. I-R Proposal Turbine drive assembly drive is provided for the ATL-4787-13 revision was sized for the 100%
EF System Emergency dated March 10, 1970. capacity Turbine-Driven Feedwater Pump 3B 2. Ingersoll-Rand Drawing Emergency Feedwater Pump (EFP-2). C-4X9-7N86X1-B. 3B.
- 3. GAI B/M No. 3RC-9, P.O.
No. PR-3 1374 for reference.
Design Conditions
( 6000F 1. Standard Engineering Based on the 6000F steam Practice. design temperature when
- 2. GAI B/M No. 3RC-9, P.O. supplied from either the No. PR-3 1374 for steam generators or reference. fossil plants CR-1 and
- 3. R0-2931 Rev. B, for CR-2.
reference.
Design Pressure 1135 psig 1. GAI Calculation, Pump- Based on the 1050 psig Turbine Performance steam design pressure l Requirements, dated when supplied from either 4/8/69. the steam' generators or 1 2. GAI B/M No. 3RC-9, P.O. fossil plants CR-1 and l No. PR-3 1374 for CR-2 plus suitable design I reference. margin.
l 3. R0-2931 Rev. B, for reference.
I l
(
i l
i i
l
i I
rioria. CRYSTAL RIVER UNIT 3 l S c= Power =- DESIGN B ASIS DOCUMENT Page 22 Of 49 Rev. o SYSTEM NAJWE: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF '
PARAMETER SOURCE ' REASON Normal Operating Conditions Maximum Inlet 1. B&W Standard Guide Steam inlet conditions Temperature - 5800F Specification, Nuclear are based on the maximum Pressure - 1131.9 psig Auxiliary System Piping steam design conditions (Functional), of 1135 psig @ 6000F, Specification No. minus friction losses, 2023/0169, Issue Date - when the EF System is January 9, 1969. initiated.
- 2. GAI Calculation EF-2, Work Order 4203, dated 10/7/70.
- 3. GAI B/M No. 3RC-9, P.O.
No. PR-3 1374 for reference.
- 4. R0-2931 Rev. B, for reference.
I Minimum Inlet 1. B&W Standard Guide Steam inlet conditions Temperature - 2600F Specification, Nuclear are based on the steam Pressure - 19.7 psig Auxiliary System Piping generator operating (Functional), conditions of 20.7 psig @
Specification No. 2600F, minus friction 2023/0169, Issue Date losses, at the conclusion January 9, 1969. of EF System decay heat
- 2. GAI Calculation, 6" removal and initiation of Steam Line to Emerg. the Decay Heat Removal Feedwater Pump Turbine, System (DH).
dated 9/4/70.
i
- 3. GAI B/M No. 3RC-9, P.O.
- No. PR-3 1374 for reference.
- 4. R0-2931 Rev. B, for
! reference.
l i Outlet
- 1. General Industry Design Turbine exhaus t steam Pressure - 1 psig, Standard. conditions reflect sat. 2. GAI Calculation EF-2, efficient turbine Work Order 4203, dated operation and are 10/7/70. required for exhausting
- 3. GAI B/M No. 3RC-9, P.O. directly to the No. PR-3 1374 for atmosphere.
i I reference.
- 4. R0-2931 Rev. B, for l
reference.
rioria. CRYSTAL RIVER UNIT 3 Power
. cm.i DESIGN BASIS DOCUMENT Page 23 Of 49 Rev.
O SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Power 1280 hp (max.) 1. Letter from R.W. The steam turbine must 757 hp (req'd) @ McCracken (I-R) to C.H. meet the feedpump 4030 rpm Thompson (FPC) dated performance condition of June 23, 1970. 757 hp. The turbines'
- 2. Terry Performance Curve maximum capability K-12194 transmitted exceeds the design 7/21/70. requirements for
- 3. GAI B/M No. 3RC-9, P.O. conservatism.
No. PR-3 1374 for reference.
Acceleration 0 - full speed in 30 1. B&W Standard Guide The EF Sys tem is designed seconds Specification, NSS to provide the required Auxiliary Feedwater flow of 740 gpm forty System Requirements, seconds after system
( Specification No. actuation. This time 2022/0870, Issue Date - includes instrumentation August 11, 1970. delay, valve stroke times,
- 2. CR-3 LOFW-EFW Upgrade, and feedpump acceleration B&W Doc. 51-1125565-00, time.
dated 8/28/81.
- 3. GAI B/M No. 3RC-9, P.O.
No. PR-3 1374 for reference.
- 4. R0-2931 Rev. B, for reference.
Turbine Governor Woodward, NEMA D I-R Proposal ATL-4787-13 Original governor revision dated March 10, specified in the proposal 1970. for the steam turbine.
, . _ . , - - - - - - w -w
rioria.
Power CRYSTAL RIVER UNIT 3
. c- DESIGN BASIS DOCUMENT Page 24 Of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE: !
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Design Modification 1. Letter from H.E. It is preferred that the Constant speed governor - Haeseler (CAI) to R.W. turbine control system Woodward Type PG-D McCracken (I-R) dated consist of a constant August 26, 1970. speed governor.
- 2. Letter from W.D. Albert This governor will: (I-R) to H.E. Haeseler (GAI) dated October 13,
- a. have a hand speed 1970.
changer with a maximum 3. Terry Steam Turbine Co.
range of 3:1; Drawing 68665-D.
- b. not accept an external 4. GAI B/M No. 3RC-9, P.O.
signal of any type to No. PR-3 1374 for act as a remote speed reference.
changer; and
- c. have a manually set dial control.
Trip and Throttle Valve
( (ASV-50F)
Type -
Schutte and Koerting 1. Ingersoll-Rand Vendor-supplied trip and Fig. 64-XE-42 Instruction Manual for throttle valve provided 600 psi Differential Centri fugal Pumps , with the turbine drive.
Florida Power Corpora- Valve controls, by tion Unit No. 3 Crystal throttling, steam River Plant, Emergency admitted to the turbine l Feedwater Pumps, when bringing it up to l GPM-740, TH-3000. speed and also acts as a
- 2. Terry Turbine Dwg. quick-closing or l 68665-D for reference. emergency trip valve.
l Body Material - 1. Letter from R. W. Body material meets fluid Carbon Steel, McCracken (I-R) to design conditions of A216 WCB C. H. Thompson (FPC), 600 F, 1135 psig steam, dated August 5, 1970.
- 2. Letter from H. E.
Haeseler (GAI) to R. W.
McCracken (I-R), dated August 26, 1970.
- 3. Ingersoll-Rand Instruction Manual for Centrifugal Pumps ,
1 Florida Power Corpora-l y tion Unit No. 3 Crystal River Plant, Emergency Feedwater Pumps ,
GPM-740, TH-3000.
rioria. CRYSTAL RIVER UNIT 3 Power c-a. DESIGN BASIS DOCUMENT Page 25 Of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON End Connections - 1. Ingersoll-Rand Flanged connections for 4", 900# ASA Instruction Manual for CR-3 piping line RF Flanges Centrifugal Pumps, Specification 600-1 are Florida Power 600 lb RF. Vendor's Corporation Unit No. 3 900 lb end connections Crystal River Plant, are supplied for Emergency Feedwater cons e rvatism.
Pumps, GPM-740, TH-3000.
- 2. Terry Turbine Dwg.
68665-D for reference.
- 3. R0-2891, Rev. 8 for reference.
- 4. GAI B/M No. 3RC-9, P.O.
No. PR-31374 for reference.
Turbine Type i
Helical Flow, solid wheel 1. I-R Proposal Type of turbine is turbine (Terry Steam ATL-4787-13 revision acceptable for steam and Turbine Co. Type GS-2) dated March 10, 1970. EF System power
- 2. CAI B/M No. 3RC-9, P.O. applications.
No. PR-3 1374 for l reference.
Materials - Casing ASTM SA-217 WCI plus S-3 1. Industry Standard. Vendor material is and S-5 2. GAI B/M No. 3RC-9, P.O. compatible with the No. PR-3 1374 for design requirements of reference. 6000F, 1135 psig steam.
- 3. R0-2931 Rev. B, for reference.
Code / Seismic Class ASME Section VIII 1. General Design Code applicable to system
~
Division I (Turbine Criterion No. 2, design at the time of Casing) Tederal Register dated startup and testing for 7/11/67, Part 50, CR-3. EF Sys tem ANSI B31.1 ES (Trip and Appendix A. components are critical l Throttle Valve) 2. Safety Guide 29, for plant safety.
6/7/72.
l Seismic Class I 3. R0-2931 Rev. B, for I reference.
- 4. GAI B/M No. 3RC-9, P.O.
! No. PR-31374 for l reference.
l
rioria. CRYSTAL RIVER UNIT 3 Power c-.- DESIGN BASIS DOCUMENT Page 26 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Environmental Conditions Accident (6 months) - Environmental and Seismic Turbine drive is located N/A Qualification Guide on Intermediate Building Specification and Data, El. 95'-0", Environmental 40 yr. (Normal SP-5095, 4/29/83. Zone 14.
Operating) -
1.0 X 104 Rads Turbine Cooling Water Flow - 4 gpm Terry Steam Turbine Co. Required Vendors' cooling Pressure Drop - 5 pstg Drawing 68665-D. water flow based on 850F cooling water.
Governor Cooling Water Flow - 2 gpm 1. ECN 2323 dated 6/25/75. Governor oil temgerature Pressure Drop - 3 psi 8 2. Terry Steam Turbine Co. would exceed 200 F and a Dwg. 68665-D. small oil cooler is required to maintain a governor oil temperature of 180 F. Required cooling water flow based on 85 F cooling water.
Cooling Water Source SW System Cooling Water 1. Engineer's Judgement. Original EF System Supply 2. GAI Flow Diagram feedpump turbine drive FD-302-601 Rev. 16 for cooling water source.
reference.
l l
l Design Modification 1. MAR-79-12-88-00. EFP-2 turbine bearing and
( EF System Cooling Water 2. GAI Flow Diagram governor cooling water Supply FD-302-082 Rev. 18 for are supplied from the reference. second stage feedpump
. discharge piping and returned to the existing
! pump suction drain.
Revised per NRC l requirement to remove all l AC power dependency from EFP-2 to allow availability during a station blackout. SW System cooling water dependent on AC powe r.
meia. CRYSTAL RIVER UNIT 3 Power
("" DESIGN B ASIS DOCUMENT Page f ""
27 49 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON EQUIPMENT TITLE: CHEMICAL TREATMENT EQUIPMENT, EMERGENCY FEEDWATER SYSTEM TAG NO.: CHEMICAL FEED PUMP, EFP-3; STORAGE TANK, EFT-1; AND SOLUTION MIXER, EFMX-1 The EF System chemical 1. B&W Standard Guide A chemical feed sys tem treatment equipment Specification, Nuclear using hydrazine to consists of a feed pump, Auxiliary System Piping scavenge the dissolved a storage tank, and a (Functional), oxygen and amonia for pH solution mixer. Specification No. adjustment is required to 2023/0370, Issue Date - prevent steam generator March 16, 1970. tube corrosion problems.
- 2. GAI Letter No. B&W-845 B&W reconsnends a maximum dated Feb. 12, 1974. dissolved oxygen concentration of 7 ppb and a pH'of 9.3 - 9.5.
Design Temperature i
Ambient 1. Standard Engineering Based on the ambient Practice. temperature of the EF
- 2. Material List ML-31, System supply from the 9/10/74 Issue. Condensate Storage Tank
- 3. GAI B/M No. 3RI-13, (CDT-1).
P.O. No. PR-3 7980 for reference.
Design Pressure 150 psig 1. GAI Calculation EF-3, Pump discliarge design (Injection Pump Dis- Work Order 4203, dated pressure of 65 psig charge) 10/3/70. specified in the material
- 2. Material List ML-31, list based on operating 9/10/74 Issue. pressure of : 50 ft. plus
- 3. GAI B/M No. 3RI-13, suitable design margin.
P.O. No. PR-3 7980 for Vendor design pressure of reference. 150 psig is provided for l conse rvatism.
l
rioria. CRYSTAL RIVER UNIT 3 Power c-- DESIGN BASIS DOCUMENT Page 28 Of Rev.
49 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Design Capacity Injection Pump - 1. Material Lis t ML-31, Variable pump capacity of 0 to 75 gph 9/10/74 Issue. O to 37 gph required to
- 2. GAI B/M No. 3RI-13, provide manual adjustment P.O. No. PR-3 7980 for to meet B&W feedwater reference. quality recommendations.
Vendor capacity of 0 to 75 gph is provided for conservatism.
Tank Capacity - 1. Material List ML-31, Tank volume required for 125/115 gallons 9/10/74 Issue. chemical addition during (Total / Mixing) 2. GAI B/M No. 3RI-13, the estimated three to P.O. No. PR-3 7980 for four hour operational reference. time of the EF feedpumps.
(
Code / Seismic Class Non-Safety / 1. General Design Chemical feed system is Seismic Class III Criterion No. 2, not essential for the Federal Register dated safe shutdown of the 7/11/67, Part 50, plant.
Appendix A.
- 2. Material Lis t ML-31, 9/10/74 Issue.
- 3. GAI B/M No. 3RI-13, P.O. No. PR-3 7980 for reference.
Components Storage Tank - Waters 1. Material Lis t ML-31, EF System Chemical Equipment Division 9/10/74 Issue. Treatment Equipment Model CT-IS (304 SS) 2. GAI B/M No. 3RI-13, supplied by Waters P.O. No. PR-3 7980 for Equipment Division meets Injection Pump - Chemcon reference. the requirements of the
. Model 1140-316SS-135 specification sheet.
(316 SS)
Agitator - Philadelphia Gear Silver Streak D-14 C-Clamp Model 102-0115-116 (316 SS)
noria. CRYSTAL RIVER UNIT 3 Power c-=. DESIGN BASIS DOCUMENT Page 29 Of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON
, Motors Pump Motor - 1/2 hp, 1. Standard Industry Vendor supplied motors Reliance Model Practice, for the EF System TE-SXT 2. GAI B/M No. 3RI-13, Chemical Treatment P.O. No. PR-3 7980 for injection pump and tank Agitator Motor - 1/4 hp, reference. mixer.
Reliance totally enclosed I
I l
l 1
i
_, ..,.m.- _ - - - - - - - - - - - - - - ,-. , -
rioria.
Power CRYSTAL RIVER UNIT 3 ww.= DESIGN B ASIS DOCUMENT Page 30 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON DESIGN BASIS FOR EMERGENCY FEEDWATER SYSTEM VALVES VALVE TITLE: TURBINE-DRIVEN AND MOTOR-DRIVEN EMERGENCY FEEDPUMP AUXILIARY FEEDWATER DISCHARGE ISOLATION VALVES TAG NO.: EFV-ll AND EFV-14 Quantity - 2 1. General Design Two flow paths are Criterion No. 19, required to Steam Federal Register dated Generator 3A so that 7/11/67, Part 50, either feedpump can Appendix A. supply emergency
- 2. R0-2809 through feedwater.
Addendum G, for reference.
- 3. P.O. No. PR-3 1001 for reference.
Size - 6" 1. GAI Calculation EF-1, Piping size required to Work Order 4203, dated minimize pressure drop 6/3/70. from the emergency
- 2. R0-2809 through feedpumps to the steam Addendum G, for generators, reference.
- 3. P.O. No. PR-3 1001 for reference.
Type - Gate, Chapman 1. R0-2809 through Gate valves are preferred Fig. L-900 Addendum G, for when serving isolation reference. function.
- 2. P.O. No. PR-3 1001 for reference.
Body Material - Carbon 1. R0-2809 through Body material meets fluid Steel, A216 WCB Addendum G, for design conditions.
reference.
- 2. P.O. No. PR-3 1001 for reference.
End Preparations - 1. R0-2891, Revision 8. Butt weld ends for CR-3 Butt Weld 2. R0-2809 through piping line Specification i Addendum G, for 900-1 when pipe is reference. 2 1/2" or larger.
Pipe Wall Thickness - R0-2891, Revision 8, for Piping thickness for CR-3 i Sch 80 reference. piping line Specification 900-1.
rioria. CRYSTAL RIVER UNIT 3 Power Page 31 Of 49 4
c- .- DESIGN BASIS DOCUMENT d'V- 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON USASI Rating - 900 psi R0-2891, Revision 8, for Pressure class per CR-3 reference. , piping line' Spe:ification 900-1.
Design Pressure - 1. R0-2809 through Design pressure is based 1600 psig Addendum G, for on the maximum-refere'nce. differential shutof f
- 2. P.O. No. PR-3 1001 for Pressure of 1500 psig at reference. the valve plus'suitabla design margin.- ,
Design Temperature - 1.R0-2809throughi Da.s ign temperat,ere is 340oF Addendum G, for based on the tcaperature reference, gradient from the stears
- 2. P.O. No. PR-3 1001 for generators.
reference.
Applicable Codes - 1. R0-2809 through
- Safety-class valves
( ANSI B31.1ES Addendum G, for required for the EF reference. System, which is
- 2. P.O. No. PR-3 1001 for critical for plant reference. safety.,
Seismic Capability - 1. General Design Valves are critical for Class I Criterion No. 2, P l ant safety and are i
Federal Register dated designated Class I.
7/11/67, Part 50, Appendix A.
- 2. R0-2809 through Addendum G, for reference.
- 3. P.O. No. PR-3 1001 fer reference.
Ope rato r Type - 1. Limitorque Drawing Motor operators are Limitorque, Motor - No. 02-408-0393-3. Preferred for valves Operated, Type SMB-0 2. MAR-80-10-66-10. serving isolation function.
Electrical Power - 1. Limitorque Drawing Power requirement 240 volts DC No. 02-408-0393-3. specified for the valve
- 2. MAR-80-10-66-10. operators.
Motor Power - 1. Limitorque Drawing Operator motor power 1.8 hP No. 02-408-0393-3. required for the Chapa:an
- 2. MAR-80-10-66-10. gate valve.
O
@M
, _,r, -. _ _
rioria.
Power CRYSTAL RIVER UNIT 3 emua DESIGN 8 ASIS DOCUMENT Page 32 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EXERGENCY FEEDWATER SYSTEM EF PARAJWETER SOURCE REASON i
VALVE TITLE: TUKBINE-DRIVEN AND MOTOR-DRIVEN EMERGENCY FEEDPUMP AUXILIARY FET.DUATER DISCHARGE ISOLATION VALVES TAG NO.: EFV-32 AND EFV-33 i
Quantity - 2 1. General Design Two flow paths are Criterion No. 19, required to Steam Federal Register dated Generator 3B so that 7/11/67, Part 50, either feedpump can i Appendix A. supply emergency
- 2. Ro-2951 through feedwater.
- Addendum A, for reference.
- 3. P.O. No. PR-3 1390 for reference.
Size - 6" 1. GAI Calculation EF-1, Piping size required to
( Work Order 4203, dated minimize pressure drop 6/3/70. from the emergency
- 2. R0-2951 through feedpumps to the steam Addendum A, far generators.
reference.
- 3. P.O. No. PR-3 1390 for reference.
Type - Gate, Velan 1. R0-2951 through Gate valves are preferred Fig.-B14-07057P Addendum A, for when serving isolation reference. function.
- 2. P.O. No. PR-3 1390 for reference.
f Body Material - Carbon 1. R0-2951 through Body material meets fluid i
Steel, A216 WCB Addendum A, for design conditions.
reference, i
i
- 2. P.O. No. PR-3 1390 for reference.
End Preparationc ~ 1. R0-2891, Revision 8. Butt veld ends for CR-3 Bute Weld 2. RD-2951 through piping line Specification Addendum A, for 900-1 when pipe is 2 1/2" reference. or larger.
I Pipe Wal'1 Thickness - R0-2891, Revision 8, for Piping thickness for CR-3 Sch 80 reference. piping line Specification 900-1.
t rior m CRYSTAL RIVER UNIT 3 Po w-ar cm a DESIGN BASIS DOCUMENT Page 33 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON USASI Rating - 900 psi R0-2891, Revision 8, for Pressure class per CR-3 reference. piping line Specification 900-1.
Design Pressure - 1. R0-2951 through Design pressure is based 1600 psig Addendum A, for on the maximum reference. differential shutoff
- 2. P.O. No. PR-3 1390 for pressure of 1500 psig at reference, the valve plus suitable design margin.
Design Temperature - 1. R0-2951 through Design temperature is 3400F Addendum A, for based en the temperature reference. gradient from the steam
- 2. P.O. No. PR-3 1390 for generators.
reference.
Applicable Codes - 1. R0 -2951 through safety-class valves t ANSI B31.1ES Addendum A, for required for the EF reference. System, which is
- 2. P.O. No. PR-3 1390 for critical for plant reference. safety.
Seismic Capability - 1. General Design Valves are critical for Class I Criterion No. 2, plant safety and are Federal Register dated designated Class I.
7/11/67, Part 50, Appendix A.
- 2. RO-2951 through Addendum A, for reference.
- 3. P.O. No. PR-3 1390 Po-reference.
Operator Type - 1. Limitorque Drawing Motor operators are Limitorque, Motor - No. 15-477-2759-3*9. preferred for valves Operated, Type SMB-O 2. MAR-80-10-66-10. serving isolati.'on function.
Electrical Power - 1. Limitorque Drawing Power requirement 240 volts DC '
No. 15-477-2759-3*9. specified for the valve
- 2. MAR-80-10-6 6-10. operators.
Motor Power - 1. Limitorque Drawing Operator motor power 1.8 hp No. 15-477-2759-3*9. required for the Velan
- 2. MAR-80-10-66-10. gate valve.
u,p rioria. CRYSTAL RIVER UNIT 3 Power cm. DESIGN BASIS DOCUMENT Page 34 of 49 Rev. o SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON VALVE TITLE: CHEMICAL ADDITION PUMP EXTERNAL RELIEF VALVE TAG NC.: EFV-43(F)
Quantity - 1 1. Material List ML-31 An injection pump dated 9/10/74, for discharge relief valve is reference. specified for the
- 2. GAI B/M No. 3R-13, Chemical Feed Package.
P.O. No. PR-3 7980 for reference.
Size - 1/4" GAI B/M No. 3RI-13, Vendor sized relief line P.O. No. PR-3 7980 for size to provide adequate reference. relief capacity for the Chemical Feed Package.
( Type - Relief, Circle GAI B/M No. 3RI-13, Vendor supplied relief Seal Model 5120 - P.O. No. PR-3 7980 for valve provides EF System 4MP-140 reference. overpressurization protection.
Body Material - 316 SS 1. Material List ML-31 Body material specified dated 9/10/74, for to meet chemical design reference. conditions.
- 2. GAI B/M No. 3RI-13, P.O. No. PR-3 7980 for reference.
Design Temperature - 1. Material List ML-31 Based on the normal Ambient dated 9/10/74, for environmental temperature reference. of the Turbine Building
- 2. GAI B/M No. 3RI-13, area.
l P.O. No. PR-3 7980 for reference.
Seismic Capability - 1. General Design Relief valve and chemical Class III Criterion No. 2, treatment package are not Federal Register dated required for plant 7/11/67, Part 50, safety.
Appendix A.
- 2. Material List ML-31 dated 9/10/74, for reference.
Set Pressure - GAI B/M No. 3RI-13, Based on the chemical 150 psig P.O. No PR-3 7980 for injection pump designed reference. discharge pressure.
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rioria. CRYSTAL RIVER UNIT 3 cY.E DESIGN BASIS DOCUMENT Page 35 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON VALVE TITLE: EFIC CONTROL VALVES TAG NO.: EFV-55, -56, -57, -58 Quantity - 4 B&W Data Sheet 34-1123146 1 Size - 4" B&W Data Sheet 34-1123146 2 Type - Globe B&W Data Sheet 34-1123146 3 Body Material - SA105 CS B&W Data Sheet 34-1123146 4 End Preparation - BWE B&W Data Sheet 34-1123146 5 Pipe - 4", Schedule 80 Target Rock Dwg. 82G-001-A 5
( ANSI Class - 900 lb. B&W Data Sheet 34-1123146 5 Design Pressure -
1725 psig B&W Data Sheet 34-1123146 6 Design Temperature -
4650F B&W Data Sheet 34-1123146 6 cv (Design) - 126 Target Rock Dwg. 82C-001-A 2 Stroke Time - 10 see B&W Specification 7 08-1123147-03 i
Special Conditions -
N Stamp B&W Specification 8 08-1123147-03 l Hydro Test Pressure 3350 psig for 10 Target Rock Dwg. 82G-001-A 9 minutes
- Design Life Cycles B&W Data Sheet 34-1123146 9 Full stroke - 100 20% stroke - 4000 20-80% stroke - 2000
rioria. CRYSTAL RIVER UNIT 3 Power c- .- DESIGN BASIS DOCUMENT Page 36 Of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Applicable Code - Table 3 B&W Data Sheet 34-1123146 9 ASME Section III, Class 3 IEEE-382 Seismic Capability - 3G Target Rock Dwg. 82G-001-A 9, 10 Class 1 Active Operator Type - B&W Data Sheet 34-1123146 3 Modulating Solenoid Motor Operator Power - Target Rock Dwg. 82G-001-A 9 105 - 140 V DC Fail - Open B&W Data Sheet 34-1123146 9 Energize to close Signal - Target Rock Dwg. 11 4 - 20 MA input 1173140-2A 4 - 20 MA feedback Environmental Conditions Environmental and Seismic 9 Guide Specification, Table 2 - SP-5095, 4/29/83.
Intermediate Building i
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rioria. CRYSTAL RIVER UNIT 3 Power c = .- DESIGN BASIS DOCUMENT Page 37 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF DESIGN BASIS FOR THE EF SYSTEM VALVES REASONS 1 QUANTITY Four flow paths are required so that either EF pump can feed either or both steam generators.
2 -
SIZE AND Cv DESIGN Valve size was based on the design Cv required to ensure adequate flow to one steam generator under the specified operating modes: A P = 1400 PSI @ 50 GPM to A P = 65 PSI Q 350 GPM. e
(
3 - TYPE Modulating solenoid motor operated globe valves were selected for delivery of ASME III control valves in time for installation during Refuel IV Outage.
4 -
BODY MATERTAT.
Body material chosen on basis of fluid design conditions.
5 -
EED PREPARATION, FIPE, AND ANSI CLASS Butt weld ends per CR-3 pipe line Specification 900-1.
l 6 -
DESIGN PRESSURE AND DESIGN TEMPERATURE Fluid design conditions per CR-3 pipe line Specification 900-1.
l l
l 7 -
l Stroke time to be 10 seconds maximum per B&W Specification 08-1123147-03.
1
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rioria. CRYSTAL RIVER UNIT 3 cY.1 DESIGN 8 ASIS DOCUMENT Page 38 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF REASONS (Cont'd) 8 - SPECIAL CONDITIONS N stamp required for ASME III Class 3 valves.
9 -
HYDRO TEST PRESSURE, DESIGN LIFE CYCLES, AND APPLICABLE CODE To conform with B&W Specification 08-1123147-03.
10 -
SEISMIC CAPABILITY Valves are Seismic Class 1 active since they are safety related and must operate during a loss of feedwater event.
(
11 - SIGNAL Valve demand and feedback signals are 4 to 20 MA for compatability with the EFIC electronic control system.
noria. CRYSTAL RIVER UNIT 3 Power c m .noa DESIGN BASIS DOCUMENT Page 39 of 49 Rev. o 2
SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON DESIGN BASIS FOR EMERGENCY FEEDWATER SYSTEM INSTRUMENT STRINGS INSTRUMENT TITLE: STEAM GENERATOR PRESSURE INSTRUMENT STRINGS STRING NO.: MS-106, -107, -108, -109, -110, -111, -112, AND -113 Steam generator pressure System Description for EF Provides the EFIC System is measured and indicated System, B&W 15-1121209-4, with an indication of SG between 0 psig and 8/30/82. pressure for density 1200 psig. compensation of level and also ADV control and SG isolation.
The response time of the System Description for EF This response time was instrument string is System, B&W 15-1121209-4, chosen so as to not I sec. 8/30/82. adversely affect EF System operation.
( Instrument string errors EFIC Instrument String String errors are are as follows: Error Calculation - B&W quantified to ensure that Doc. 32-1158577-00, extreme environmental o Normal Operating 6/18/85. conditions do not Environment adversely affect EF
+ 12.38 psi system operation.
Indicator errors are additional.
Environmental conditions Environmental and Seismic These conditions apply to are listed on Table 2 - Guide Qualification the transmitter portion Intermedite Building. Specification, SP-5095, of the instrument string, 4/29/83. which is subject to accident environment.
Applicable codes and 1. System Description for These codes and standards standards are listed on EF System, B&W apply to the EF system l Table 3. 15-1121209-4, 8/30/82. instrument strings.
I
- 2. Electric Transmitter Specification, SP-5061, Rev. 1.
(
noria. CRYSTAL RIVER UNIT 3 Power c-.- DESIGN BASIS DOCUMENT Page 40 of 49 Rev. o SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON INSTRUMENT TITLE: OPERATING RANGE STEAM GENERATOR LEVEL INSTRUMENT STRINGS STRING NO.: SP-017, -018, -019, -020, -021, -022, -023, AND -024 Steam generator level is System Description for EF Provides an accurate measured in both SGs System, B&W 15-1121209-4, indication when SG water using taps at elevations 8/30/82. level is high for SG 102" and 394". level control and SG overfill protection.
The SG level string System Description for EF Indication alerts indicates SG 1evel System, B&W 15-1121209-4, operator of potential between 100" and 400". 8/30/82. overfill conditions.
The string sensors are Electric Transmitter EF Sensors are specified to
(
designed for 1200 psig at Specification, SP-5061, match SG design 6000F. Rev. 1. temperature and pressure.
The instrument string EFIC Instrument String String errors are errors are as follows: Error Calculations - B&W quantified to ensure that Doc. 32-1158577-00, extreme environmental o Normal Operating 6/18/85. conditions do not Environment adversely affect EF
+ 4.80" system operation.
- 3.84" Indicator errors are additional.
o Small LOCA Environment *
+ 44.47"
- 18.34" Reference Leg Heatup
+ 26.12" o Design Break Environment *
+ 44.47" 18.34" Reference Leg Heatup
+ 26.12"
- Including Reference Leg Heatup Error I. . __- - -. . - . _ . . - _ . - . - . . . . - .
rioria. CRYSTAL RIVER UNIT 3 cU.1 DESIGN BASIS DOCUMENT Page 41 of 49 Rev.
0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Environmental conditions Environmental and Seismic Those environmental are listed on Table 2 - Guide Qualification conditions apply to the Reactor Building. Specification, SP-5095, transmitter portion of 4/29/83. the instrument string which is subject to the accident environment.
Applicable codes and 1. System Description for These codes and standards standards are listed on EF System, B&W apply to the EF system Table 3. 15-1121209-4, 8/30/82. instrument strings.
- 2. Electric Transmitter Specification, SP-5061, Rev. 1.
l
meia. CRYSTAL RIVER UNIT 3 c Y.*'a DESIGN B ASIS DOCUMENT Page 42 of 49 Rev. o SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON INSTRUMENT TITLE: STARTUP RANCE STEAM GENERATOR LEVEL INSTRUMENT STRINGS STRING NO. : SP-025, -026, -027, -028, -029, -030, -031, AND -032 Steam generator level is System Description for EF Provides an accurate measured in both SGs System, B&W 15-1121209-4, indication when SG water using taps at elevations 8/30/82. level is low for EF 6" and 277". system actuation and Control.
The SG 1evel string System Description for EF Indication alerts indicates SG 1evel System, B&W 15-1121209-4, operator of potential SG between 0" and 150". 8/30/82. dryout.
The string sensors are System Description for EF Sensors are specified to designed for 1200 psig at System, B&W 15-1121209-4, match SG design t 6000F. 8/30/82. temperature and pressure.
The instrument string EFIC Instrument String String errors are errors are as follows: Error Calculation - B&W quantified to ensure that 32-1158577-00, 6/18/85. extreme environmental o Normal Operating conditions do not Environment adversely affect EF
+ 4.56" system operation.
- 3.59" Indicator errors are additional.
o Small LOCA Environment *
+ 44.47"
- 18.34" Reference Leg Heatup
+ 26.12" o Design Break Envirorunent*
+ 44.47"
- 18.34" Reference Leg Heatup
+ 26.12"
- Including Reference Leg Heatup Error i
l
rioria. CRYSTAL RIVER UNIT 3 c,"1".1 DESIGN BASIS DOCUMENT Page 43 Of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON Environmental conditions Environmental and Seismic Those environmental are listed on Table 2 - Guide Qualifiction conditions apply to the Reactor Building. Specification, SP-5095, transmitter portion of 4/29/83. the instrument string which is subject to the accident environment.
Applicable codes and 1. System Description for These codes and standards standards are listed on EF System, B&W apply to the EF system Table 3. 15-1121209-4, 8/30/82. instrument strings.
- 2. Electric Transmitter Specification, SP-5061, Rev. 1.
(
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rioria.
Power CRYSTAL RIVER UNIT 3 c u.oa DESIGN BASIS DOCUMENT Page 44 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON INSTRUMENT TITLE: EMERGENCY FEEDWATER FLOW INSTRUMENT STRING STRING NO. : EF-023, -024, -025, AND -026 Emergency feedwater flow System Description for EF Provides computer and is measured and indicated System, B&W 15-1121209-4, panel indication of between 160 and 820 gpm. 8/30/82. maximum pump flow to a steam generator down to minimum design flow per steam generator of 160 gpm (320 gpm total l
minimum prior to decay heat system transfer).
See Design Modification on page 15.
( Environmental conditions Environmental and Seismic These conditions apply to are listed on Table 2 - Guide Qualification the transmitter portion Intermediate Building. Specification, SP-5095, of the instrument string, 4/29/83. which is subject to accident environment.
Applicable codes and 1. System Description for These codes and standards standards are listed on EF Syetem, B&W apply to the EF system Table 3. 15-1121209-4, 8/30/82. instrument strings.
- 2. Electric Transmitter Specification, SP-5061, Rev. 1.
(
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CRYSTAL RIVER UNIT 3 rioria.
cYE DESIGN BASIS DOCUMENT Page 45 of 49 Rev. o SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF PARAMETER SOURCE REASON INSTRUMENT TITLE: CONDENSATE STORAGE TANK LEVEL INSTRUMENT STRING STRING NO.: CD-98 AND -99 The condensate storage Electric Transmitter Provides full tank level tank level is measured Specification, SP-5061, indication of which and indicated between 0 Rev. 1. 150,000 gallons is and 35 feet of water. dedicated for the EF system.
Environmental conditions - Electric Transmitter Engineering judgement Turbine Building. Specification, SP-5061, that transmitters Rev. 1. suitable for the Reactor Building and Intermediate Building will be suitable for the milder Turbine j Building environment.
Applicable codes and 1. System Description for These codes and standards standards are listed on EF System, B&W Doc. apply to the EF system Table 3. 15-1121209-4, 8/30/82. instrument strings.
- 2. Electric Transmitter Specification, SP-5061, Rev. 1.
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noria. CRYSTAL RIVER UNIT 3 )
Power 49 1
. c-- DESIGN BASIS DOCUMENT Page 46 of Rev. O SYSTEM NAME: SYSTEM CODE: i EMERGENCY FEEDWATER SYSTEM EF !
INSTRUMENT STRING NOTES
- 1. Instrument strings listed are those providing signals to the EFIC system.
Those strings that are associated with EF actuation and control functions are safety related Class 1E and have response times and string error requirements as stated on the data sheets.
- 2. EF flow and tank level instrument strings are powered and routed through EFIC for computer, main control board, and remote shutdown panel indications and have manufacturers' standard accuracies.
- 3. Transmitters are the only instruments in the EF strings subject to harsh accident environments listed on Table 2. EFIC electronics, computer, and indicator portions of the strings are all located in the mild control complex environment.
- 4. Indicators are seismically qualified and have an accuracy of 1-1/2%, which j must be added to the transmitter / electronics portion of the string to determine total string accuracy.
- 5. Level measurements are density / pressure compensated over a pressure range of atmospheric to 1050 psig assuming a saturated volume of steam and water.
Since the level measurement is density compensated, the unic " inches" refers to the actual level in the steam generator over the specified pressure range.
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rioria. CRYSTAL RIVER UNIT 3 c5EE DESIGN BASIS DOCUMENT Page 47of 49 Rev. O O
SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF TABLE 2 EFIC CONTROL VALVES AND INSTRUMENT STRING ENVIRONMENTAL CONDITIONS Normal Accident Reactor Building Pressure Atmospheric 49.6 psig peak Temperature 40 - 109oF 298 F peak Relative Humidity 40 - 90% 100%
Radiation (maximum) 1.4 x 107 Rads 1.4 x 107 (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 5.5 x 107 (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) 9.2 x 107 (30 day)
(
1.8 x 108 (6 month) 1.9 x 108 (40 year)
Intermediate Building Pressure Atmospheric 4.7 psig Temperature 70 - 1400F 3450F (2 sec) 240oF (10 sec) 2120F (40 see)
Relative Humidity 20 - 90% 100%
4 Radiation 1.0 x 10 Rads 1.0 x 10' Rads i
> rio,ia. CRYSTAL RIVER UNIT 3 1, c5U.S DESIGN BASIS DOCUMENT Page 48 of 49 Rev. O SYSTEM NAME: SYSTEM CODE:
EMERCENCY FEEDWATER SYSTEM EF TABLE 3 CODES AND STANDARDS GOVERNING EF SYSTEM INSTRIRIENTATION AND EFIC CONTROL VALVES Ceneral Design Criterion 19, Control Room, is related to the design capability of system instrumentation and controls for prompt hot shutdown of the reactor and potential capability for subsequent cold shutdown.
General Design Criterion 44, Cooling Water, to assure:
(1) The capability to transfer heat loads from the reactor system to a heat sink under both normal operating and accident conditions.
(2) Redundancy of components so that under accident conditions the safety
, function can be performed assuming a single active component failure.
(This may be coincident with the loss of offsite power for certain events.)
(3) The capability to isolate components, subsystems, or piping if required so that the system safety function will be maintained.
Regulatory Guides 1.22, Feb. 1972 Periodic Testing of Protection System Actuation Functions 1.26, Rev. 3, Sept. 1978 Quality Group Classifications and Standards for Water, Steam, and Radioactive Waste Containing Components 1.29, Rev. 3, Sept. 1978 Seismic Design Classification 1.47, May 1973 Bypassed and Inoperable Status Indication 1.53, June 1973 Application of the Single Failure Criterion 1.62, Oct. 1973 Hanual Initiation of Protective Actions 1.75, Rev. 2, Sept. 1978 Physical Independence of Electrical Systems (Intent) 1.102, Rev. 1, Sept. 1976 Flood Protection for Nuclear Power Plants 1.89, Nov. 1974 Qualification of Class IE Equipment for Nuclear Power Plants 1.100, Rev. 1, Aug. 1977 Seismic Qualifications of Electric Equipment for Nuclear Power Plants
This pnga followsd by page 49a.
1, - rioria. CRYSTAL RIVER UNIT 3 Power
) ,
c- = DESIGN BASIS DOCUMENT Page 49 of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF TABLE 3 (Cont'd)
CODES AND STANDARDS GOVERNING EF SYSTEM INSTRUMENTATION AND EFIC CONTROL VALVES IEEE Standards 279-1971 Criteria for Protection Systems for Nuclear Power Generating Stations (for initiation portions of EFW System) 323-1974* General Guide for Qualifying Class I Electrical Equipment 338-1971 Trial Use Criteria for Periodic Testing of Protection Systems 344-1975 Seismic Qualifications of Class 1E Electrical Equipment 379-1972 Trial Use Guide for the Application of the Single Failure Criterion 382-1980 Standard for Qualification of Safety-Related Valve Actuators g 384-1977 Separation of Class IE Equipment and Circuits (Intent)
NUREG's 0578 TMI Short-Term Lessons Learned Report 0588 Interim Staf f Position on Environmental Qualification of Safety Related Electric Equipment
- Transmitters per IEEE 323-1974; EFIC Electronics per IEEE 323-1971
\
. - . _ . , , . _ _ - - _ - . . . . . _ _ - _ - - . - _ ~ . . _ . , _- .. _- -- . . _ - - - - -
0 Florida CRYSTAL RIVER UNIT 3 0, 9 cPower -- DESIGN B ASIS DOCUMENT Page 49a Of 49 Rev. 0 SYSTEM NAME: SYSTEM CODE:
EMERGENCY FEEDWATER SYSTEM EF TABLE 4 OTSG EMERGENCY FEEDWATER CHEMISTRY REQUIREMENTS ph at 770F Same as normal requirement (1)
Dissolved oxygen (02)
OrSG at < 2500F No requirement (see hydrazine)
OTSG at > 2500F Notual 7 ppb max.
Upset 100 ppb max. for a period not to exceed I week Total Iron 100 ppb max.
Hydrazine
( Catalyzed Hydrazine OTSG at < 2500F Added to at leas t 300% of Stoichiometric oxygen concentration OTSG at > 2500F 20-100 ppb residual Cation Conductivity 1.0 mho/cm, max. for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Notes:
(1) 8.5 - 9.3 at 770F - with aus tenitic stainless steel feedwater heater tubes and stainless steel or copper-nickel reheater tubes.
- 9. 3 - 9. 5 at 770F - Carbon steel feedwater heater tubes or combinations of carbon steel and stainless steel feedwater and/or reheater tubes.
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ITEM 6 I
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+=- , - - - , . - - - - - . ,_,,,,,_. ..._..,,. ,_,_ _ . , , , , , , _ , . , _ _ , _ _ __ _ _
o DERGENCY FEEDHA'IER AND EFIC ANAI.YS5 DOCDENT G-3 M IM NTIFIER Dh'E SPECIFIC
- 1. ECG to Determine Minimum 77-1125999-01 7/81 N OISG Ievel for Natural Circulation
- 2. Overcooling Reply to Denton 86-1106752-03 3/80 N Show cause
' 3. Steam Generator Isval 32-1117414-00 2/80 N W = 7 in Reflux Mode
- 4. FOGG Verification Study 51-1123786-01 5/81 N
- 6. Condensate Storage Tank 32-1127434-00 8/81 Y Capacity
- 7. CcE-@Laal Design Study BAW-1612 Rev.01 3/80 N for AFW System Feed Rate Control for B&W 177FA Plants
- 8. Option 1 Failure Analysis 51-1132681-00 4/82 Y
- 9. Option 2 Failure Analysis 51-1132682-00 4/82 Y 10.EFW LDJrade Reliability 32-1125434-02 6/82 Y Analysis for CR-3 32-1126041-00 12/81 Y 11.'Ihree Pump EIW Reliability 7/81 Y Analysis for G-3
- 12. Design Report EFWS Cbnt:el 33-1011476-00 8/82 Y Valves .
13.EFW t% grade: Setpoints, 51-1153083-02 7/85 Y Limits and Precautions l
- 14.EFW 14 grade Draft Technical 51-1153204-01 Y Specifications I
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FLORlbkPOWERCORPOR[kb CRYSTAL 8tIVER Pt. ANT ._.
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TUR8tNE PIPIE C.O. SYSTDs FLos OLAGRAu CONDENSATE a
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t EFWA REV 06 Date 12/06/85 AP-450 EMERGENCY FEEDWATER ACTUATION ENTRY SYMPTOMS CONDITIONS
- 1. Annunciator alarms o Loss of main feedwater.
associated with emergency feedwater actuation. o Loss of OTSG secondary side integrity.
o Trip of all Reactor Coolant
- 2. Annunciator alarms Pumps associated with loss of both MFPs. o RC Pressure < 1500 ps I
- 3. Either OTSGs level < 18".
- 4. HPI Actuation.
THIS PROCEDURE ADDRESSES SAFETY RELATED COMPONENTS
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i Reviewed By PRC bMM m Date 12/06/85 Mtg.# 85-49 I
Approved By NPM //v//N Date / //
' t i ff g AP-450 Page 1 of 8 EFWA I
\
ggd6b y i
i EFWA REV 06 Date 12/06/85 AP-450 ACTIONS IMMEDIATE REMEDIAL
- 1. Depress EFW Actuation push buttons.
- 2. Ensure closed: Trip main Feedwater pumps.
o MBVs o LLBVs
- 3. Ensure both EFWPs start. Manually start both pumps.
- 4. Ensure open EFW block valves:
o EFV-11 o EFV-14 o EFV-32 o EFV-33
- 5. Ensure EFW control valves 1. Transfer valves to " hand" controlling.
- 2. position to provide proper EFV-55 EFV-56 flow.
EFV-57 EFV-58 NOTE: Expected valve control may not be observed until after control setpoint overshoot occurs. l
- 6. Verify adequate subcooling o Start HpI AED refer to margin. Ap-380.
o Stop all RCp's.
Ap-450 page 2 of 8 EFWA L
EFWA REV 06 Date 12/06/85 AP-450 FOLLOW-UP ACTIONS DETAILS
- 1. Start VP-580, Start Plant Safety Verification AHD Procedure.
l Notify SOTA.
- 2. Ensure required OTSG level set point is selected. STATUS LEVEL o RCP's running Lew Level l Limita l o NO RCPs running 5 0 '.
o Adequate (Refer subcooling margin to AP-530) o Less than 9 5 *.
adequate (Refer subcooling margin to i '
AP-380) o < 2 HPI !
pumps available 95*.
J
- 3. II NO EFW available, 1. Start FWP if not running.
- Refer to OP-605 THEN maintain FW flow to OTSG's. 2. Ensure open:
FWV-33 ("B" SUBV)
FWV-36 ("A" SUBV)
- 3. Throttle:
FWV-39 ("B" SUCV)
FWV-40 ("A" SUCV)
AP-450 Page 3 of 8 EFWA
EFWA REV 06 Date 12/06/85 AP-450 FOLLOW-UP (Cont'd)
ACTIONS DETAILS
THEN start HPI/PORV cooling.
- 5. Verify proper EFW flow. II either OTSG pressure is less than 600 psig, THEN refer to AP-460, Steam Generators Isolation Actuation.
IE OTSG level not maintaining ,
properly, ;
THEN Transfer EFW control valve to hand and control manually:
"A" OTSG "B" OTSG EFV 56 EFV 55 EFV 58 EFV 57
- 6. II only one OTSG is being fed, l AED RCPs are not operating THEN maintain full EFW flow until Natural Circulation starts, QB 95% level is established.
AP-450 Page 4 of 8 EFWA
_ . _m i
L EFWA REV 06 Date 12/06/85 AP-450 FOLLOW-UP (Cont'd) 1
- ACTIONS DETAILS i t
i CAUTION:
CST level < 28 ft. causes loss of suction to GWPs, which will affect condenser vacuum.
4 i
- 8. Ensure EFP-3 is running. Notify TB operator to verity '
operation of emergency feedwater chemical treatment.
i l i
! 9. Maintain hotwell levels 1. Close:
at 6-10 FT.
i o CDV-43 I
o CDV-44.
at -100 PSIG. .
I 3. Ensure re]ect valve l' (CDV-88) is open.
- 4. Maintain deareator level with CDV-242 28 i
CDV-239.
f I
i l
AP-450 Page 5 of 8 EFWA l
i i
- - . - _ . . . , _ , , - , . , __......--._,.._-__.,.,-_.m.,._._ , . , , , , _ , . _ . , , . . , . . . , - . . _ _ , , , . - . , . - , , , , , , .,,,,,--,,m_. - _ . -
EFWA REV 06 Date 12/06/85 AP-450 FOLLOW-UP (Cont'd)
ACTIONS DETAILS
- 10. II both OTSGs are being '
fed, RC SUBCOOLING THEN throttle EFW flow to PRESSURE MARGIN ensure:
PSIG 'F o Cooldown rate
< 100*F/HR > 1500 2 20 o Subcooling margin 1 1500 2 50
< 100*F.
._ q 11 WHEN MFP is available j l
AHH adequate subcooling j margin exists, j l
THEN: l
- a. Establish main a. Establish flow:
feedwater flow to OTSG(s) with normal (1) Refer to OP-605, feedwater nozzles Feedwater System, start MFP.
(2) Raise MFP discharge pressure 2 50 PSIG above OTSG PRESS.
(3) Open:
o FWV-36 ("A" SUBV) o FWV-33 ("B" SUBV)
- b. Maintain required OTSG b. Throttle:
levels o FWV-40 ("A" SUCV) o FWV-39 ("B" SUCV)
AP-450 Page 6 of 8 EFWA
7.=-- -
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3
-t . .
EFWA REV 06 Date 12/06/85 AP-450
, r-FOLLOW-UP (Cont'd) / ~
ACTIONS
(-..- . ,
DETAILS
- c. Restore emergency c. Restore EFW to standby: '
feedwater, system STBY.
(1) Transfer EFW control valves to " Hand" and close.
, (2) JI' ,EFIC parameters are in the Trip condition, ,
THEN select " Manual' Perm.issive*. ;'
(3) IT;EFIC parameters have r3 covered to normal condition, 'l I. lien select " TEST , ,
RE9*JLTS/ RESET" l ,
(4) S top "EFP- 1. ~lt (5) Close ASV-5 and Asv-204.!
(6) Transfer EFW control l valves to " Auto" l l
- 12. WHEN CST level 1 5 FT, a) Ensure condenser vacuum breake'rs open '
THEN establish suction from Hotwell. o ARV-48 i
l l o AR9-49 i I
b) Notify an auxillary operator t
to open: 5 -.,
o EFV-1 ,
l ,
, o EFV-2
'Close:
c) o EFV-3 l
l .... _
o' EFV-4 '
l l
- AP-450 Page 7 of 8 EFWA 1
l
.a
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,m , ,,.m .y, ,,.,,p - , , - - ,,_,-9.,,,, ,qmm,-,,_,y,,. ,_my- 7.gm -,.3-,c,. -
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i
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w[
t EFWA '
- REV 06 Date 12/06/85 AP-450 N
FOLLOW-UP (Cont'd)
..s .
r ACTIONS DETAILS 13., WHEN hotwell level .1 1 FT. Go to Engineered Safeguards System Actuation.
, THEN establish HPI-PORV cooling and go to AP-380.
- 14. WHP:4 VP-580 is complete AMD SAT, THEN notify SSOD.
.._.___q l
- 15. Notify SSOD that AP-450 is complete.
Er
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L i
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4 3
3 AP-4SO Page 8 of 8 EFWA
. - - - .w~ --e.,, rn- . . , _
m . . . . . _ _ .
9 4
6 NC REV 05 Date 10/03/86 AP-530 NATURAL CIRCULATION l ENTRY SYMPTOMS 1
- 1. Loss of ALL operating RCPs.
e
(
THIS PROCEDURE ADDRESSES SAFETY RELATED COMPONENTS l
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C. R. N.;c car l a I ct;;2micsxx n a x rm's 1Gcm.ooanc" Reviewed By PRC 0 Date 10/03/86 Mtg.# 86'-39 Approved By NPM , NON Date / f[f86 AP-530 Page 1 of 13 NC Y
91/0 ost
NC REV 05 Date 10/03/86 AP-530 A.CTIONS IMMEDIATE REMEDIAL
- 1. Verify adequate subcooling 1. Establish full HPI.
margin based on Incores:
- 2. Refer to AP-380, Engineered Safeguards Actuation.
RC SUBCOOLING PRESSURE MARGIN PSIG *F t 1500 2 20 1 1500 2 50
- 2. Refer to AP-450.
AP-530 Page 2 of 13 NC
NC REV 05 Date 10/03/86 AP-530 FOLLOW-UP ACTIONS DETAILS
- 1. Start VP-580 Start Plant Safety Verification Procedure.
AND notify SOTA.
CAUTION Cooldown of RC on Natural Circulation shall not exceed the following rates:
Tc (*F) RATE (*F/HR) 550 - 280* 10.0 280 - 150 5.0
< 150 2.5
- 2. Ensure correct OTSG level set point selected. CONDITION LEVEL Refer to AP-450 for EFW o Adequate operation. subcooling margin 65's o Less than adequate 95%
subcooling margin (refer to AP-380) o < 2 HPI pumps available 95S.
AP-530 Page 3 of 13 NC t
NC REV 05 Date 10/03/86 AP-530 FOLLOW-UP (Cont'd)
ACTIONS DETAILS l
NOTE Rapid and possibly erratic increase in PZR level without change in RC make up, RC letdown, OTSG feed rate or OTSG steaming rate is indication of steam voids in the RCS.
- 3. II steam voids are Reduce RC void volume:
indicated, THEN:
- a. Reduce RC void volume a. Stop depressurization
- b. Maintain RC TEMP and b. Stabilize RC temperature PRESS until void indication does HQI c. Raise RC PRESS exist.
- d. Observe PZR level for decrease and stability.
- 4. II subcooling margin < 0 o Observe subcooling margin meter selected to incore THEN go to EP-290, thermoccuples.
Inadequate Core Cooling.
DH o Determine:
AVG of 5 highest incore thermocouples.
RC PRESS Steam tables.
AP-530 Page 4 of 13 NC
NC REV 05 Date 10/03/86 AP-530 FOLLOW-UP (Cont'd)
ACTIONS DETAILS
- 5. IIadequatesubcool[cqmargin Establish HPI:
does n21 exist, THEN-
- a. Establish HPI a. Open:
o MUV-73 o MUV-58
- c. Refer to AP-380, c. Open:
Engineered Safeguards .
Actuation. o MUV-23 o MUV-25 o MUV-24 o MUV-26 Required OTSG Levels W/O RCP CONDITIONS LEVEL o Adequate Subcooling 65*.
Marcin o Less Than Adequate 95*. refer Subcoolino Marcin to AP-380 o L2 HPI Pumps 9 5 *.
Available a
- 6. II natural circulation is Verify natural circulation by verified, observing:
THEN go to Follow-up step o Tc =TSAT of OTSG.
17.
o AT (incores - Tcold) develops and stabilizes o The average of the 5 highest incores follows TH within 10*F.
o TH, T c, and Incores lower when OTSG pressure is lowered.
AP-530 Page 5 of 13 NC
NC REV 05 Date 10/03/86 Ap-530 Z,OLLow-UP (Cont'd)
ACTIONS DETAILS
OTSG TSAT is 40 - 60* below o Turbine Bypa.ns Valves AVG of 5 lowest incore thermocouples. o Atmospheric Dump Valves
- 8. Il natural circulation is Verify natural circulation by verified, observing:
THEN go to Follow-up Step o Tc =TSAT of OTSG.
17.
o 4C0 (incores - Tcold) develops and stabilizes o The average of the 5 highest incores follows TH within 10*F.
o TH, Tc, and Incores lower when OTSG pressure is lowered.
Ap-530 page 6 of 13 NC
NC y REV 05 Date 10/03/86 AP-530 FOLLOW-UP (Cont'd)
ACTIONS DETAILS l
NOTE RCPs are available for " Bumping" when the following conditions are met:
o Pump start permissives .
o Power available
60*F below average of 5 THEN " BUMP" 1 RCP for lowest incores.
10 SEC.
- 3. WHEN RC pressure has stabilized after pump, bump Iwithin 20 PSIG),
THEN determine if natural circulation is established.
IE HO RCPs are available, THEN go to Follow-up Step 16.
AP-530 Page 7 of 13 NC
NC REV 05 Date 10/03/86 AP-530 FOLLOW-UP (Cont'd)
ACTIONS DETAILS
- 10. II natural circulation is Verify natural circulation by verified, observing:
THEN go to Follow-up Step o Tc =TSAT of OTSG.
17.
o AT (incores'- Tcold) develops and stabilizes o The average of the 5 highest incores follows TH within 10*F.
o TH, Tc, and Incores lower when OTSG pressure is lowered.
NOTE An RCP " Bump" is of 10 second duration.
- 11. " Bump" remaining RCPs at o If less than 4 RCPs are 15 MIN intervals until available for bumping, the four bumps have been same pump may be bumped more performed. than once to obtain four bumps. Alternate bumps among all operable pumps.
l l
Ap-530 Page 8 of 13 NC l
t l
l l
NC REV 05 Date 10/03/86 AP-530 FOLLOW-UP (Cont'd)
ACTIONS DETAILS
- 12. IE natural circulation is Verify natural circulation by verified, observing:
THEN go to Follow-up Step o Tc =TSAT of OTSG.
17.
o AT (incores'- Tcold) develops and stabilizes o The average of the 5 highest incores follows TH within 10*F.
o TH, T c, and Incores lower when OTSG pressure is lowered.
- 13. Lower OTSG TSAT to a. Open TBVs or ADVs and lower 90-100*F below incore OTSG pressure until OTSG temperature and TSAT is 90-100*F below maintain, average of 5 highest incore temperatures.
i Ap-530 page 9 of 13 NC
NC REV 05 Date 10/03/86 AP-530 FOLLOW-UP (Cont'd)
ACTIONS DETAILS
- 14. II natural circulation is Verify natural circulation by verified, observing:
THEN go to Follow-up Step o Tc =TSAT of OTSG.
17.
o AT (incores'- Tcold) develops and stabilizes.
o The average of the 5 highest incores follows TH within 10*F.
o TH, Tc, and Incores lower when OTSG pressure is lowered.
- 15. WHEN 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more has RCPs are available when the elapsed since reactor trip, following conditions are met:
AHD primary to secondary o Pump start permissives heat transfer (OTSGs) is n21 established, o Power available THEN if an RCP is avail- o RC Press and temperature are able, start 1 RCP and keep above RCP curve, Enclosure 1, running. when below 900 psig RC pressure.
AP-530 Page 10 of 13 NC
NC REV 05 Date 10/03/86 AP-530 FOLLOW-UP (Cont'd)
ACTIONS DETAILS
- 16. Maintain HPI cooling until -
HPI may be STOPPED when HPI flow requirements change. o Subcooling margin restored AED Refer to AP-380 for long PZR level is 2 50" term HPI operation. AMD OTSG heat removal is available DE o LPI flow > 1000 GPM in each train for > 20 min.
HPI May be THROTTLED when o Adequate subcooling margin is restored.
HPI Must be THROTTLED when o Subcooling margin approaches 100*F AE2 No RCPs running.
- 17. WHEN cooldown required o Reduce OTSG pressure by steaming:
THEN START cooldown at
< 10*F/hr. while on -
Turbine Bypass Valves natural circulation.
DB Atmospheric Dump Valves NOTE Following inadequate core cooling and hydrogen production, only the pressurizer vent may be used for RCS depressurization.
AP-530 Page 11 of 13 NC
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NC REV 05 Date 10/03/86 AP-530 FOLLOW-UP (Cont'd)
ACTIONS' DETAILS l
NOTE RCPs are available when the following conditions are met:
o Pump start permissives .
o Power available, o RC Press and temp are above RCP curve Enclosure 1 when below 900 PSIG RC Press
- 18. MHIH RCPs are available Refer to OP-302, RC Pump Operation AER adequate subcooling margin exists, NOTE AND at least 1 OTSG is Ensure PORV closed before providing cooling, starting pump.
IHIH start:
NOTE
i THEN refer to OP-209.
1 i
- 20. WHEN VP-580 is complete, AHD SAT,
' THEN notify SSOD.
I AP-530 Page 12 of 13 NC f
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NC REV 05 Date 10/03/86 AP-530 ENCLOSURE 1 RCP CURVES 1000 i i , i i , , ,
900 - I I-- -- d! - --
800 l- -
-l- l- bl-l
-J g 700
-I - - -
jipcp-I - - -
m l OPERATION l
$ 600 - -
TTf 0,T/972 kl\ -
500 -- -
E o 400 -
j l I
'[ -
I 300 -
( -
/7l .
I M /l l 200 -- -.
l l SAT 2l RC P ~~
geAgN 10 0 -
/ UN}
' ' I ' '
O O 100 200 300 400 500 RC TEMP TjC( F)-
l f AP-530 Page 13 of 13 NC l
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