ML20134A406
| ML20134A406 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/30/1985 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20134A361 | List: |
| References | |
| TAC-61487, NUDOCS 8511040397 | |
| Download: ML20134A406 (21) | |
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-' RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS ~
Limiting Conditions for Operation 3.4 STEAM AND POWER CONVERSION SYSTEM Applicability Applies.to the operability of the turbine cycle during normal operation and
- for the removal of decay heat.
Objective To specify minimum conditions of the turbine cycle equipment necessary to assure the required steam relief capacity during normal operation and the capability to remove decay heat from the reactor core. i ' Specification . 3.4.1 The reactor shall not remain aoove 280F with irradiated fuel in the pressure vessel unless the following conditions are met.
'107> .3.4.1.1 Capability to supply feedwater to at least one steam generator from 4 at least cae of the following means.
A. A condensate pump and a main feed pu:np, or - B.- A condensate pump or C. An auxiliary feedwater puy. . 107>< The required flow rate is 760 gpm at less than 120'F. [ 3.4.1.2 Two steam system safety valves are operable per steam generator. 3.4.1.3 The turbine bypass system to the condenser shall have one valve operable or the atmospheric dump systen shall have a minimum of I of 3 valves operable per steam generator. 3.4.1.4~ A minimum of 250,000 gallons of water shall be available in the condensate storage tank. 3.4.2 In aodition to the requirements of 3.4.1, the reactor shall not remain critical' unless the following conditions are met: 1 3.4.2.1 Seventeen of the eighteen main steam system safety valves are operable. I P, Proposed Amendment No. 107 3-23 8511040397 851030 PDR ADOCK 05000312 p PDil
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l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation l l When two independent 100% capacity auxiliary feedwater flow paths
- i. 3.4.2.2 are not available, the capacity shall be restored within 72 hours or the plant shall be placed in a cooling mode which does not rely on steam generators for cooling within the next 12 hours.
3.4.2.3 _ When at least one 100% capacity auxiliary feedwater flow path is not available, the reactor shall be made subcritical within four hours and the facility placed in a shutdown cooling mode which does not
- rely on steam generators for cooling within next 12 hours, c
I . The feedwater system and the ' turbine bypass system are normally used for decay. heat removal and cocidown above 280 F. Feedwater makeup is supplied by operation of a condensate pump and main feedwater pump. In the event of comple*.e loss of electrical power, feedwater is supplied by a turbine driven
- auxiliary- feedwater pump which takes suction from the condensate storage tank. Steam relief would be through the system's atmospheric relief valves.
If neither main feed pump is available, feedwater can be supplied to the . steam generators by an auxiliary feedwater pump and steam relief would be through the turbine bypass system to the condenser. , ,
- 107+. The auxiliary feedwater system is designed to provide sufficient flow on loss of main feedwater to match decay heat plus Reactor Coolant Pump heat input to
+ the RCS before solid pressurizer operation could occur. The' requirement for two steam system safety valves per steam generator provides a steam relief capability of over 10 percent per steam generator (1,341,938 lb/h). In
, addition, two turbine bypass valves to the condenser or two atmospheric dump valves will provide the necessary capacity. 107* The 250,000 gallons of water in the condensate storage tank is sufficient to remove decay I; eat (plus RC pump heat for two pumps)- for approximately 13 hours. This volume would also allow ~ hot shutdown for approximately 5.5 hours . + with cooldown to DHR system changeover at 50F/hr. (1) ! The minimum relief capacity of seventeen steam system safety valves is 13,329,163 lb/hr.(2) This is sufficient capacity to protect the steam system under the design overpower condition of 112 percent. (3) REFERENCES 1074 (1) B&W Document 32-1841727-00, " Heat Removal Capability of SMUD CST,"
- March 1984.
(2) FSAR paragraph 10.3.4 4 (3) FSAR Appendix 3A, Answer to Question 3A.5 1 Proposed Amendment No. 107 i- 3-24 L _ _.__.. _ _ _ _ ..._. _ _._._ . . _ . _ . _ . . . , . _ _ . _ _ _ . . _ _ _ ._ _ _ _ _ _ _
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RANCHO SECO UNIT 1 i TECHNICAL SPECIFICATIONS . Surveillance Standards 1 1 I 4.8 AUXILIARY FEEDWATER PUMP PERIODIC TESTING i Applicability Applies to the periodic testing of the turbine and motor driven auxiliary feedwater pumps. Objective To verify that the auxiliary feedwater pump and associated valves are operable. Specification 4.8.1 At least every 92 days on a staggered test basis at a time when the average reactor coolant system temperature is >305'F, the turbine / motor driven and motor driven auxiliarf feedwater pumps shall be operated on recirculation tc the condenser to verify proper operation. The 92-day test frequency requirement shall be brought current within 72 hourg after the average reactor coolant system temperature is 1305 F. ,
. Acceptable performance will be indicated if the pump starts and 107> . operates for fifteen minutes at the design flow of 760 gpm._ .
< 4.8.2 . At least ence per refueling interval: -
- 1. Verify that each automatic valve in the flow path actuates to its correct position upon receipt of each auxiliary feedwater actuation test signal.
- 2. , Verify that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwater actuation test signal.
4.8.3 All valves, including those that are locked, sealed, or otherwise secured in position, are to be inspected monthly to verify they are in the proper position. j- 4.8.4 Prior to startup following a refueling shutdown or any cold shutdown of longer than 30 days duration, conduct a test to demonstrate that the motor-driven AFW pumps can pump water from the CST to the steam get.erator. . Proposed Amendment No. 107 l 4-39
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. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Bases The quarterly test frequency will be sufficient to verify that the turbine / motor driven and motor driven auxiliary feedwater pumps are operable.
Verification of. correct operation will be made both from the control room 1 instrumentation and direct visual observation of the pumps. The OPERABILITY of the auxiliary feedwater system ensures that the Reactor
- Coolant- System can be. cooled down to less than 305 F from normal operating
- conditions in the event of a total loss of off-site power.
Each electric- driven auxiliary feedwater pump is capable of delivering a total
- 107>< feedwater flow of 760 gpm at a pressure of 1050 psig to the entrance of the steam generators. The steam driven suxiliary feedwater pump is capable of 1107>< delivering a total feedwater flow of 760 gpm at a pressure of 1050 psig to the entrance of the steam generators. This~ capacity is sufficient to ensure. that j adequate feedwater flow is available to remove decay heat and reduce the
- Reactor Coolant System temperature to less than 300 F when the Decay Heat-Removal System may be placed into operation.
107>, The' auxiliary feedwater pumps are tested to verify they automatically start as designed upon receipt of each auxiliary feedwater actuation test signal. At least once per refueling interval, the auxiliary feedwater' pumps are started on the loss of four Reactor Coolant Pumps s!gnal and also on SFAS initiation. The monthly surveillance test demonstrates proper auxiliary feedwater pump
< response to a low main feedwater pressure signal.
t L l' 1 Proposed Amendment No. 107 4-393 i;
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SAFET/ ANALYSIS FORMAT RANCHO SECO NUCLEAR GENERATING STATION UNIT NO.1 ECN A-3622 Rev 1 NCR Work Request DESCRIPTION:
' Add safety grade indication of auxiliary feedwater flow to each staam generator and provide AFW flow indication in the Control Room.
REASON FOR CHANGE: To meet the recuirements of Reg. Guide 1.97 (to monitor operation) and NUREG 0737, II.E.1.2.2.C (Safety Grade Flow Indication) ,, EVALUATION AND 8.15I5 FOR THE SAFET( FINDINGS : The change will provide dual flow rate indicators for each steam generator, thus a single failure will not eliminate indication for a AFW piping train. This change improves the capability for monitoring AFW flow. A technical specification change will be required and a post implementation rev.iew is required by NUREG 0737.
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@ The proposed change will not increase the probability of occur'rence or the '
consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR or create the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR or reduce the margin of safety as defined in the basis for any Technical Specification. - SAFETY FINDING: EThe proposed change does _npir involve a change in the Technical Sqecifications r :r .. . . . . * :" u d=**/ ; e . m . T e a . < I . , , , t .. . . ,. _ ..
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.v.4( WORK HAA J
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I o..n 7* BEEN COMPLETED ON JUL 151 B3 Licensing Engineer / 4 [a/ ,,
.HA%M(L/2d:/? w Review Engineer /d..b8*eImJol Date M - / r* 2.
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DESIGI BASIS REPORT EC A-3 652 REV I !CR ' /? UORK REQU::ST__ 104130 I & c DATE 2/24/e2 DISCIPLI:!E I. pun 90sr or nesrc:: c u a::c r : The purpose of this design change is to implement the requirements of I;UREC 0737, item II.E.1.2.2, auxiliary feeduster flow indication ano negulatory Guide 1.97 Table 2, . Type D, Auxiliary or Omergency Feedvatar Flow. This is further defined in f: URICauxiliary 0737 II.E.1.2 f Part 2 by eedwate r flow grade stating that safety indication is required to meet the 10CFR part 50, Appendix A Criterion 13.
- 1. Safety-grade indicaten of auxiliary feeduacer f1cu to each steam generator shall be provided in the Concrol Room i
- 2. The auxiliary feedvater flow instrument channels shall be powered from the emergency buses consistent with satisfying the emergency power divercity requirements of
' the auxiliary feedvacer system set forth in Auxiliary Sytems 3 ranch Technical Position 10-1 cf the Standard Revieu Plan, Section 10.4.9."
1 II. crsrc:: carTrnrA usin: !
- 1. The flow transmitters shall be Class I and shall meet seismic, the requirements with respect to separation, and environmental qualificacions. . l I
. 2. The power supply and isolation cabinet shall be Class IE respect to and shall meet the requirements with
- separation, seismic, anc environmental qualification.
- 3. SignalctoCentrolRotsforindicajienwillnotbeIEin interi:.. mocification curing thed ,- . c 10 ':2 outago, therefore, the indication in the Centrol Room is not Class *I: and chall utili::e existing non IE indicators and the computer for displaying the information.
Conformance to :.CCEC 0727 uill be achieved wisen major control room modifications are implemented. " ,u.4 6 WORK HAS BEEN COMPLETED . C ON .ittL 141. 33
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- 4. The f ollowing codoc c.nu 'scandards are applicable, except l
as indicated in II.3 aove, :o ficu traas:..itccr purcha.e ! and installacien, power supply and distribution cabince purchase and in: calla:iun .nd ca le and virc routing to the IE portion of the system: seenser "ue er subjecE IEEE 279 Criteria for Ucclear Pouer Generating S tation protection systems. IEEE 323 Qualifying Class IE equipment for Nuclear Pouer Generating Stations. IEEE 344 Recommended practices for seismic qualificacion of Class IE equip:aent for Nuclear Power Generacing Stations. , IEEE 384 Criteria of separation of Class IE l equipment and circuits. IEEE 379 Trail Use Guide for Application of Single railure Ucclear Power i Generating S tation Protective
~- Syste=n.
? , .v III. cAtct1LATici:s A'!D orsicit Ittron" Acro:::
- 1. Installation.' of the flou transmitters and the power supply / isolation cabinet meet the requirements of Class
. IE safety grade.
,2. Conduit and cable trays from the transmitter and power source to the power supply /isolacion cabinet meet the requirements of Class IE safety grade.
- 3. Each Nf the auxiliary feedwater piping train will have redundant flow measuring anc indication devices to _ meet the single failure criterion. , _m.4 6 WORK HAS BEEN COMPLETED IV. FAILURE Moor: ON JUL15DN An electrical failure of any channel ( $ w &C :'a ilu r e short circuit or open circuit) vill ESIE03WCVhQT ,QLlow i rate indication f or each au::iliary Giiedwater piping train.
The Control Room util co acle to ascertain the actual performance of each AFiS train at all times. A tubing failure vill result in the loss of flow rate indication of the damaged auxiliary :'ecduater piping train. 2
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,V . COMMENTS: ,
The design meets the requirements of 10 CFR Part 50 Appendix A, criterion 13 and is in compliance with the requirements . of NUREG 0737 and Regulatory Guide.1.97. e Design Engineer - Date 3" ~ OE- [ o. ra u m s
, Review Engineer /d Ih,d w i h Da't e TM A7-i
. ".n 6 YlORK HAS BEEN COMPLETED ON JUL 151993 RANCHO SEGO M. DOCUMENT CONTROLg O
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'* O .R Log No. 335 g_ SAFETY ANALYSIS FORMAT RANCHO SECO NUCLEAR GENERAT.ING STATION UNIT NO. 1 ECN A-3094 Rev. 2 NCR Work Request DESCRIPTION:
Install flanges and orifice places on lines 31821-6"-DB2 and 31823-6"-DB2. Relocate the Auxiliary Feedveter (AFW) pump test line. ECN A-3621 will install the flow transmitter and controls. REASON FOR CHANGE: To improve the reliability of the Auxiliary Feedwater system as comitted in our December 17, 1979 submittal to the NRC and to 11rplement the requirements of . NUREG 0737, itas II.E.1.2.2. EVALUATION AND BASIS FOR THE SAFETY FINDINGS: This change will provide safety grade indication of AFW flow to each steam generator. The changes are quality and Joismic Class I. PLANTwonx HAs sten COMPLETED ON Aus - 11l185 RANCHO SECO SITE DOCUMENT CONTROL
@ The proposed change will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR or create the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR or reduce the margin of safety as defined in the basis for any Technical Specification.
SAFETY FINDING: OThe proposed change does.a+4 involve a charige in the Technical Specifications m ' " ':03 ; ~ .:.m. R T'M bg du%M .oM? - Licensing Engineer 2Fulle___ Oate //4a/ev
- k. Review Engineer MN w Oate /
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. m DESIGN BASIS REPORT +
ECN A-3094 NCR N/A Work Request 10!.30 Discipline Mechanical Date U*
- I. PURPOSE OF DESIGN C11ANGE:
The purpose of this design change is to 1:nplement the requirements of NUREG 0737, ices II.E.1.2.2, auxiliary flow indication. II. DESIGN CRITERIA USED: ,
- 1. Material to be Quality Class I, compatible with existing boundary material.
- 2. Design configuration shall be analyzed to satisfactorily withstand a Seismic Category I event.
- 3. Flow resistance resulting frcaflow orifice installation shall be analyzed to show no adverse effect on abili v to supply auxiliary feedwater to the OTSG's at the required fios and pressure.
4 Piping will be installed to SMUD drawing M-870 and ASME Section XI, class 3. III. CALCULATIONS AND' DESIGN INFORMATION:
- 1. Dead weight, thermal and seismic analysis is acceptable '(see attached).
- 2. The addition of the flow orifice will result in 157.6 inches of H,0 pressure differential across the orifice at a flow race of 1,000 2pm (see attached calculation). This converts to a 13.13' TDH/5.7 psi loss across the orifice.
B & W Doc. ID No. 15-1120580-02
Title:
System Description Auxiliary
.Teodwater System requires a minimum flow of 780 gpm to one or both OTSG at a OTSG pressure of 1050 psig.
The (attached) AIW system resistance curve indicates a line resistance of 75 ft. at 780 gym. The flow orifice resistance at 780 gym = d P2=AP( t ) AP2 " 13 3 (1 00)* ' PLAwrwenn HAs AP2 = 7.98 f t TDH ON Ayg - } ggg (- L RANCHO SECO SITE OCCUMENT CONTROL
r
* 'O .m - ,. Total resistance = 75 + T.98 = 83.0 ft TDH 3 780 gym.
The minimum available TDH @ 780 gym is 2700 f t. TDH from P-318 (see accached pump curves). 2700' - 83.0' = 2617.0' TDH available for delivery. , 2617.0' TDH = 1130.0 psig Therefore, the line can supply 780 gpa to the OTSG at 1133 psig. This is greater than the minimum required. This calculation is
, conservative because the (attached) curve indicates that a flow orifice with a S of 0.76029 will result in a 42T loss of the actual dif f erential.
IV. FAI1URE MODE:
- 1. The configuration has been analyzed to withstand a Seismic Category I event. (See attached report).
V. COMMENTS:
- 1. Installation will be done in accordance with applicable approved procedures.
- 2. SP-210.01 A and 3 must reflect incrgased pressure drop.
Design Enginee MD h. Date '7 '
/ cv-xevie. ..ineer 2d Id o-a /c -* 3 2-
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. BEEN COMPLETED ON Aug -1 gg$
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