ML19257D222
| ML19257D222 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/12/1979 |
| From: | Spencer B SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19257D211 | List: |
| References | |
| PROC-791012, NUDOCS 8002010545 | |
| Download: ML19257D222 (20) | |
Text
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4'.2 3211 SACRAMEf4TO f.tUtitCIPAL UTILITY DISTRICT C 6201 S Street. Dar 153r. Sacramento. California 95813; G16) c RANCHO SECO NUCLEAR GENERATING STATION UNIT NO.1 PROCEDURE CHAf1GE APPROVAL FORM Procedure Number A.51 Rev. 10 Title Auxiliary Feedt.a ter S. st ea Date Ori;inator 3,
27 q_9,,_7n Approved
/d--.- c d.
Date
/ c. - / - 7 c/
v croup supe,..w, Regmmend Approval by Plant Review Committee:
Yes Iv]
No [ }
\\
Requested Change Chance FV-30301 to SFV-30801 in the fo11ouin[4.?.11.
7.2.3, 7.3.5. 7.6. 5.3. 7.6. 5.4 and Enclosure 8.1 cagn 11.
C Rea cn for Changa C1nrificaci e 1857 106 Approved b,.vif / c T.-[%.[e
' Date
/ O - l 1 ~79 rani s,,,e. comm.ne.
Recommend Review by Mana;ement Safsty Re.iew Committee:
Yes [ ]
No [ W Approved L5 mA a r o n' Date 16 - i t.
7 1 t
Flant S.ge, ente cent
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Fcrward to Management Safety Review Committer:
Yes [ ]
No [<}
s' Date Revir.ved Mar agement Safety R eveeva Corr.,m t teo t) 02 010 gg SMUD-0366 12/74
A.51 AUXILIARY FEEDWATER SYSTEM 1.0 PURPOSE
.1 Provide procedures to accomplish the following operations:
.1 Fill auxiliary f eed system (section 4.1)................ A.51-2
.2 Place auxiliary feed system in standby (Section 4.2).... A.51-3
.3 No rma l op e rat ion (S ec tion 5.1).......................... A. 51-4
.4 Sy s tem shu tdown (Se c tion 6.1)........................... A. M.-5
.5 Remove P-319 from service (Sec tion 7.1)................. A.51-6
.6 Remove P-318 from service (Sec tion 7. 2 )................. A. 51-7
.7 Remove auxiliary feed system from service (Section 7.3). A.51-8 4
.8 Feed OTSG's with auxiliary feed system (Section 7.4)..... A.51-9,
.9 Supply auxiliary feed pumps from D/G (Section 7.5)...... A.51-10
.10 Turbine driven auxiliary feed pump overspeed trip
( S e c t i o n 7. 6 )........................................... A. 51 - l l
2.0 REFERENCES
.1 P&ID M-530, Rev. 15, H.P. & Auxiliary Turbine System
.2 P&ID M-532, Rev. 11, Steam Generator System.
4
.3 P&ID M-533, Rev. 11, High Pressure Feedwater System.
.4 P&ID M-536, Rev. 12, Condenser System.
.5 FSAR Paragraph 10.2.1, 10.2.2.
.6 System Specification H5.6, Auxiliary Feedwater Pumps and Related Equipment.
.7 Rancho Seco Technical Specification, Sections 3.4 and 4.8.
.8 Surveillance Test 210.01A/B.
4 L
.9 Surveillance Test SP 213.01.
1857 107
.10 Rancho Seco Unit I Chemistry Manual.
m 3.0 LIMITATIONS AND PRECAUTIONS
.1 Th6 reactor shall not rect in critical unless both auxiliary feed pumps are operable; however, one auxiliary feed pump may be out of service for maintenance purposes for a period not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
.2 The Reactor Coolant System shall not remain above 280*F unless a mini =um of 270,000 gallons of water is available ir. the con-densate storage tank, and the capability to supply feedwater to one OTSG at a process flow rate corresponding to decay heat of 4-1/2: full reactor power from at least one of the following means:
.1 A condensate pump and a main feed pump, or 4
.2 A condensate pump, or
.3 An auxiliary feed pump.
.3 Condensate storage tank water should meet chemistry specifications set forth in Rancho Seco Unit I Chemistry Manual for addition to OTSG's.
.4 Auxiliary feed system should be tested quarterly on recire.
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to condenser for a minimum of 15 minutes for each pump in aceqrd-ance with Surveillance Test, SP 210.01.
.5 Flow through auxiliary feed nozzle to OTSG shall never exceed 500 gpm (except during emergency actuation).
.6 Minimum water temperature to OTSC's through the auxiliary feed-water nozzles shall always be maintained >40*F.
.7 Except in emergency conditions, water fed to the OTSG's through the auxiliary feed nozzles must be within 50*F of the RCS and OTSG average shell temperatures.
4.0 SYSTEM STARTUP s
i
.1 Filling Auxiliary Feed Systen I
l Initial Conditions i
.1 Condensate storage tank has been filled and lined up in accordance with Operating Procedure A.47.
.2 Auxiliary feed pu=ps racked out.
f,
.3 Both auxiliary feed pump bearing lube oil reservoirs have been filled, level bulbs full.
7
.4 Auxiliary feed system is drained.
1857 108 t
A.51-2 Rev. 4 j
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4.0 SYSTEM STARTUP (Continued)
.1 Filling Auxiliary Feed Svsten (Continued)
Procedure
.5 Valve lineup in accordance with Enclosure 8.1, with exception, condensate storage tank outlet valves MCM-058, MCM-057 are closed.
.6 Fill the system frem the condensate storage tank by cpening valves MCM-058, MCM-057.
.7 Vent both auxiliary feed pump casings.
.8 Vent high points in system located at valves FWS-061 and FUS-062.
.2 Placing Auxiliary Feedwater System in a Standby Condition NOTE:
Aux FWS is not in standby condition 7
until steps 4.2.1 through 4.2.11 have been completed.
e Initial Conditions
.1 Condensate storage tank has a minimum of 270,000 gallo'ns of water, as indicated on LI-35803 in the Control Room.
with all valves lined up in accordance with OP A.47.1.
.2 Both auxiliary feed pump bearing oil reservoirs have been filled, level bulbs full.
.3 Auxiliary feed system is filled and vented as per Section 4.1 of this procedure.
Procedure
.4 Valve linup in accordance with Enclosure 8.1.
CAUTION:
Perform the following steps in 10G7 1))
sequence to prevent inadvertant iUJI I
starting of the auxiliary feed pumps.
f'
.5 Check both " auxiliary motor driven feed pump diesel loading bypass key switches" are in the normal position at HISS panel and keys removed.
A.51-3 Rev. 7
4.0 SYSTDI STARTUP (Continued)
(Continued.,)
.2 Placing Auxiliary Feedwater Systen in a Standbv Condition NOTE:
To ensure that the auxiliary feed punp controls are in manual, the green stop buttons cust be depressed and held in, for P-319 and P-318, respectively, while performing the following steps.
.6 Rcck in breaker 52-4A06 for cotor driven a" :lliary feed pump P-319 and energize the DC control power.
Verify
" Normal-Isolate" switch in Normal position.
.7 Close breaker 72-B03 for FV-30S01, steau supply control valve for turbine driven auxiliary feed pump.
Verify "Nomal-Isolate" switch in Nornal position.
.8 Rack in breaker 52-4B10 for P-318 motor and energize DC control power.
Verify. "Nor=al-Isolate" switch in normal position.
.9 Place steam trap XCV-30802 and XCV-30806 in service for the tuebine drive.
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MOTE:
The following steps to be
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s perforced when designated by OPOP B.2.
.10 With at least 2 reactor cool nt pucps running,'both main feedwater pumps running, and feedwater discharge header pressure greater than 900 psig in both feedwater headers, both auxiliary feed pumps can be placed in automatic by pushing the ALTO pushbutton for each pu=p on the HISS panel.
Check acber lights indicating auto circuit.
Pl' ce auxiliary feedwater flou control valves, FV-20527,
.11 a
FV-2052S in automatic and clo' sed.
Check red lights are on at Bailey Controllers, Place STV-20577, SFV-20578, and SW-30S01 closed and in AUTO.
Insure BLEP's for FV-20527 l
1 and 28 are in AUTO. -
5.0 NORMAL OPERATION
.1 Auxiliarv Feed System in a Standby Condition Initial Conditions
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.1 Both auxiliary feed pumps are shut down with controls in automatic,'and valves lined up as per Enclosure 8.1.
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A.51-4 Rev. 10
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5.0 NORMAL OPERATION (Continued)
.1 Auxiliary Feed System in a Standby Condition (Continued)
Procedure
.2 Maintain condensate storage tank above 270,000 gallon level, as indicated on LI-35803 in the Control Room, with all valves lined up in accordance with S0P A.47, with.1.
.3 Quarterly check beat ng lube oil level for *ooth pumps in accordance with SP 210.01A/B.
4
.4 Maintain condensate storage tank chemistry in accordance with specifications set forth in Rancho Seco Unit I Chemistry Manual.
System Actuation
.5 laue following conditions will cause auxiliary feed system actuation from the standby condition:
.1 P-319 motor will start on
.1 Loss of power to all 4 RCP's.
4
.2 850 psig in both feed headers.
.2 P-318 turbine stop opens on
.1 Loss of power to all 4 RCP's.
4
.2 850 psig in both feed headers.
.3 Initiation of SFAS channels 2A or 2B.
6.0 SHUTDOWN
.1 Auxiliary Feedwater System Initial Conditions
.1 Auxiliary feed system is in a standby condition as per Section 4.2 of this procedure.
.2 The RCS is in a hot shutdown condition and plant cool-down is to take place.
1857 IiI A.51-5 Rev. 4
s E
6.0 SHUTDomi (Continued)
.1 Auxiliary Feedwater System (Continued)
CAUTION:
Prior to shutdown of the last reactor coolant pump, and before the main feed pump discharge pressure decreases to 900 psie, the auxiliary feed system must b removed freu AUTO to prevent inadvertant actuation.
Procedure
.3 Place auxiliary feedwater flow control valves FV-20527 FV-20528 in manual with valves closed. Verify SFV-20577 and SFV-20578 are closed.
4
.4 Push STOP pushbuttons for both auxiliary feed pumps at HISS panel to remove automatic start functions.
(Verify green STOP buttons lit, amber AUTO buttons extinguished.)
.5 When the RCS is cooled down to <200*F, rack out both auxiliary feedwater pu=ps and close the condensate storage tank outlet valves MCM-057 and MCM-058.
s.
NOTE:
The Condensate Storage Tank Outlet valves must be closed to prevent filling the hot-well from the condensate storage tank when the condensate system is shut down.
7.0 ABNORMAL OPERATIONS
.1 Removing Motor Driven Auxiliary Feed Pump from Service for Maintenance Initial Conditions
.1 Auxiliary feed system is in a standby condition as per Section 4.2 of this procedure.
NOTE:
The reactor shall not remain criti-cal unless both auxiliary feed pumps are operable; however, one auxiliary feed pump may be out of service for
}@}/ })2 maintenance purposes for a period not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
A.51-6 Rev. 4
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7.0 AB:iORMAL OPERATIOiS (Continued)
.1 Removinr, Motor ' Driven Auxiliarv Feed Pump from Service for
({}
Maintenance (Continued)
Procedure
.2 Push STOP pushbutton for motor driven auxiliary feed pump P-319 at HISS panel.
.3 Open D.C. control power for motor driven pump Breaker 52-4A06 and rack out breaker.
.4 Close pump discharge valve FWS-054.
.5 Close pump recirc valve FUS-052.
.6 Close pump suction valve FWS-046.
.7 Open pump casing vent and drain valves.
.2 Removing Turbine Driven Auxiliary Feed Pump from Service for Maint' nance e
Initial Conditions
.1 Auxiliary feed system is in a standby condition as per
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Section 4.2 of this procedure.
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NOTE:
The reactor shall not remain criti-cal unless both auxiliary feed pumps arc operable, but one auxiliary feed pump may be out of ser' ice for mainte-v nance purposes for a period not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Procedure
.2 Push STOP pushbutton for turbine driven auxiliary feed pump.at HISS panel.
.3 Open Breaker 72-B03, steam supply valve to turbine driven auxiliary feed pump SF','-30S01.
, 10
.4 Open DC control power and rack out breaker 52-4B10 for F-318 motor.
1857 113
.5 Deleted.
.6 Close auxiliary steam supply to turbine driven pump MSS-006.
O A.51-7 Rev. 10
........._.._.. u..._.__
7.0 AENORMAL OPERATIONS (Continued)
.2 Renoving Turbine Driven Auxiliary Feed Punn from Service for Maintenance (Continued)
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.7 Close main steam to turbine driven auxiliary feed pump
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MSS-050, MSS-049.
,8 Close pump discharge valve FWS-053.
.9 Close pump recire, valve FWS-051.
.10 Close pump suction valve FW3-045.
.11 Open pump casing vent and drain valves.
.3 Removing Auxiliary Feed System from Service Initial Conditions
.1 Auxiliary feed pumps running.
.2 Another method of reactor core heat removal has been
. established.
Procedure
[s.
.3 Place auxiliary feeduater flow control valves FV-20527, FV-20528 in manual with valves closed.
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.4 Push STOP pushbutton for both auxiliary feed pumps at' HlSS panel.
.5 Open breaker 72-B03, steam supply valve to turbine driven auxiliary feed pump SFV-30801.
l10 o
.6 Open DC control power and rack out breaker 52-4A06 for P-319 motor.
.7 Open DC control power and rack out breaker 52-4B10 for P-318 motor.
.8 Close both auxiliary f eed pum,p recire valves FWS-051, FWS-052.
NOTt:
Auxiliary feed pump recirc valves must be closed to prevent filling the hotwell from the condensate storage tank when the co.,densate system is shut down.
C 1857 ]14
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A.51-8 Rev. 10
7.0 ABNORMAL OPERATIONS (Continued) 4 Feeding OTSG A (B) From the Auxiliary Feedwater System
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Initial Conditions
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.1 Condensate storage tank lined up and filled per OP A.47.
.2 Condensate storage tank water chemistry is in Specification per the Rancho Seco Unit 1 Water Chemistry Manaal and is acceptable for feeding the OTSG's.
.3 RCS in a hot or cold shutdown ccndition (Reactor not critical).
.4 The auxiliary feedwater syste= is lined up per Section 4.2 and valve lineup Enclosure 8.1.
Procedure l
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.5 Verify crosstie valves K7-31826 and HV-31827 are open, and that the auxiliary feedwater pu=p mini flow valve is open to the EP condenser (FWS-051 for P-318 and FWS-052 for P-319 and MCM-91 or MCM-92 or MCM-93 or MCM-94 is open).
NOTE:
Insure that the OTSG drain booster pumps are isolated frem the higher pressure Aux. FDW Systec at FWS-086 (FWS-087) or at FWS-128 (FL'S-127).
3
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.6 Start the auxiliary feedwater pe=p (P-318 1r P-319) and throttle open FV-20527 (FV-20528) to establish feed flow to OTSG A(B).
NOTE:
1.
Observe limits of 3.6 and 3.7 of this procedure.
If feeding and bleeding an OTSG balance flow rates to caintain a continuous flow thus avoiding unnecessary thermal cycles on the auxiliary feedwater nozzles.
2.
Do not exceed 500 gpm fill rate. Monitor OTSG wide range level instru=entation LI-20501 (LI-20502)
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to determine fill rate. OTSG secondary side voluce equals 42 gals / inch, 500 gps equals 11.9 inches per minute level increase.
.7 When the desired OTSG A(B) level is obtained, close FV-20527 (FV-20528).
Stop tSe auxiliary feedwater pump.
C 1857 11D t
A.51-9 Rev. 3 N
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7.0 ABNORMAL OPERATIONS (Continued)
Diesel Power
.5 Operation of Auxiliary Feedwater System With Auxiliary Initial Conditions
.1 One or both Nuclear Service buses 4A/4B supplied by their respective auxiliary diesel generators and all Block Load lights off.
.2 Condensate storage tank lined up and filled per OP A.47.
.3 The Auxiliary Feedwater System is lined up per Section 4.2 and valve lineup Enclosure 8.1.
.4 Auxiliary feedwater flow via motor driven pu=ps is required.
.5 Condensate storage tank water chemistry meets the require-ments of Rancho Seco Unit 1 Water Chemistry Manual for feeding the OTSG's.
Procedure
.6 Motor Driven Pump P-319.
.1 Check the load on the Nuclear Service bus 4A is
-[7
<1900 KW.
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.2 Push STOP pushbutton for P-319 and verify green STOP light on and amber AUTO light off at HISS panel.
.3 Utilizing the bypass key under Shift Supervisor Control, bypass the Auxiliary FFP/ Diesel Output Breaker interlock at HlSS panel.
(Bypass switch will capture the key.)
.4 Push START pushbutton for P-319.
Verify red RUN light on, green STOP light off and motor amps normal.
.5 Verify Aux!liary Diesel-A load <2750 KW.
Gheck redundant equipment operating znd stop upper dome 7
circulators and/or Reactor Building Coolers as required to limit load.
.6 Verify OTSG levels are maintained at desired levels by automatic or manual control of auxiliary feedwater control valves.
Loss of FWP's at Low Level Limit (%24" on startup range or 410% on Operate range.).
Loss of RCP's at 50% of Operate Range (or N130" on
{'
Startup range) j 1857 116 A.51-10 Rev. 7
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7.0 ABNORMAL OPERATIONS (Continued)
.5 Operation of Auxiliaru Feedwater System Uith Auxiliary Diesel Power
.6
.7 With auxiliary feedwater pumps supplying the OTSG's, break condenser vacuum when CST level reaches Lo-Lo level alarm point (29'3").
Shift Auxiliary feedwater 7
pump suction to site supply system when CST level reaches Lo-Lo-Lo level (3').
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P-318, Open PCW-076, then close MCM-057 P-319, Open PCW-079, then close MCM-058
.7 Dual Drive Pump P-318
.1 Check the load on the Nuclear Service Bus 4B 21900 KV.
l7
.2 Stop P-318 by:
SFAS Signal
.1 At H2SFA panel take manual control of SFV-30801.
.2 At H2SFB panel take manual control of SFV-30801 and push the CLOSE button.
(Blue AUTO light off,
[
amber FUCRJ/U, light on, green CLOSED light on
(
if no FWP/RCP signal to STV-30801.)
.3 At HISS panel, push CLOSE/ AUTO RESET button for SFV-30801 (Amber AUTO light off, green CLOSED /
AUTO RESET light on).
No SFAS Signal
.4 At HlSS panel, push CLOSE/ AUTO RESET button for SFV-30801.
(Amber AUTO light off, green CLOSED / AUTO RESET light on.)
.3 Utilizing the bypass key under Shif t Supervisor Control, bypass the Auxiliary FWF/ Diesel Output Breaker interlock at HlSS panel.
(Bypass switch will capture the key.)
.4 Push START pushbutton for P-318 motor. Verify red RUN light on, green STOP light off and motor amps normal.
.5 Verify Auxiliary Diesal-a load <2750 KW.
Check redundant equipment operating and step upper dome circulators and/or 7
Reactor Building Coolers as required to limit load, f:
1857 117 A.51-ll Rev. 7 e
7.0 ABNORMAL OPEPATIONS (Continued)
)
.5 Operation of Auxiliary Feedwater Svstem with Auxiliary Diesel Power (Continued)
.7
.6 Verify OTSC levels are maintained a desired level by automatic or manual control of auxiliary feedwater flow control valves.
Loss of FWP's at Low Level Limit (N24" on Startup range or %10% on Operate range.)
Loss of RCP's at 50% on Operate Range (or %130" on Startup range) 7
.7 With auxiliary feedwater pumps supplying the OTSG's, break condenser vacuum when CST level reaches Lo-Lo level alarm point (29'3").
Shift auxiliary feedwater pugp suction to site supply system when CST level reaches Lo-Lo-Lo level (3').
P-318, Open PCW-076, then close MCM-057 P-318, Open PCW-079, then close MCM-058.
NOTE:
(
If it is desirable to use one auxiliary s
FWP to feed one OTSG, the cross connection valves HV 31826 or HV 31827 =ust be closed at H2YS panel.
.6 Turbine Driven Auxiliary Feed Pumo P-318 Overspeed Trip Initial Conditions
.1 P-318 steam inlet control valve SFV(FV)-30801 indicates open.
.2 Auxiliary feed valves FV-20527 or SEV-20577 for OTSG "A" and/or FV-20528 or SFV-20578 for OTSG "B" indicate open.
.3 OTSG 1evel change indicates no feed flow to the OTSG's.
, Procedure
.4 Visually check P-3]f' turbine overspeed latch mechanism to verify trip.
1857 118
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A.51-12,Rev. 7
7.0 ABSOR.'IAL OPERATIONS (Continued) e
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Turbine Driven Auxiliary Feed Pump P-318 overspeed Trip (Continued)
.6
.5 From the Control Room, drive FV-30801 to the closed position as follows:
SFAS is initiated
.1 At panel H2SFA, take manual control of SFV-30801.
.2 At panel H2SFB, take manual control of SFV-30801 and push the close button.
.3 At panel HISS, push the CLOSE/ AUTO RESET button for SFV-30301.
{10 No SFAS Signal
.4 At panel HlSS, push the CLOSE/ AUTO RESET button for SFy-30301.
l19
.6 Locally at P-318 turbine, engage the overspeed latch pall and yoke.
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.7 Operation of the Auxiliary Feeduater System Independent of ICS
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Controls Initial Conditions
.1 Condensate storage tank lined up and filled pe. OP A.47.
.2 Condensate storage tank water chemistry is in Specification per the Rancho Seco Unit 1 Water Chemistry Manual and is acceptable for feeding the OTSC's.
.3 RCS in a hot or cold shutdown condition (Reactor not critical).
.4 The auxiliary feedwater system is lined up per Section 4.2 and valve lineup Enclosure 8.1.
.5 ICS control is either unavailable or undesirabic.
Procedure
.6 If auxiliary feedwater ICS control valves are open, either close them from the Bailey control stations on H1RC in the Control Room or hand-jack them closed locally.
.7 Start auxiliary feedwater p. ump P-318 and/or P-319 at HISS in
(
the Control Room.
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A.51-12a Rev. 10 1857 119
7.0 ABNORMAL OPERATIONS (Continued
.7 Operations of the Auxiliary Feedwater System Independent of ICS
)
Controls (Continued)
.8 Control auxiliary feel flow to ar.d level in OTSG "A" ("B")
by adjusting the position of safety features controlled bypass vrlve SFV-20577 (SFV-20578) at panel H2SFB (H2SFA) in the Control Room.
Verify Aux FW flow on FI-31801 and FI-31901 at H2PSA.
Loss of FWP's at Low Level Limit (%24" on Startup range or %10% on Operate range.)
Loss of RCF's at 50% on Operate Range (or %130" on Startup range)
CAUTION 7
SFV-20577(SFV-20578) stroke full open on SFAS initiation.
Modulation of these valves during an SEAS condition requires defeat of SFAS signal (depress MANUAL pushbutton).
This removes these valves from SFAS control until the SFAS has been reset.
.9 With auxiliary feedwater pumps supplying the CTSG's, break condenser vacuum when CST level reaches Lo-Lo level C
alarm point (29'3").
Shif t Auxiliary feedwater pump suction l
to site supply system when CST level reaches Lo-Lo-Lo level (3').
P-318, Open PCW-076, then close MCM-057 P-319, Open PCW-079, then close MCM-058
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J 1857 120 A.51-12b Rev. 7 t
8.0 ENCLOSTRES 8.1 Turbine Driven Auxiliary Feed Pump
(
NOTE:
This valve lineup MUST be performed by 2 operators sequentially, each independent of the other.
1st/2nd OP OP VALVE ?:0.
VALVE NAME POSITION INITIAL MCM-057 Condensate Storage Tank Outlet to Turbine Driven Auxiliary Feed _ Pump............. Locked Open
/
FWS-045 Turbine Driven Auxiliary Feed Pump Suction Valve.......................... Locked Open
/
PI-31803 Pump P-318 Suction Pressure............In Service
/
PI-31801 Pump P-318 Discharge Pressure Isolation..............................In Service
/
WS-053 Pump Discharge Valve................'... Locked Open
/
FUS-493 WS-0 5 3 Bypa s s......................... Clo s e d
/
FWS-051 Pump Recire.
Valve....................-Locked Open
/
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FWS-055 Pump Flow Tes t Valve................... Locked Closed
/
FWS-492 FWS,--0 5 5 By pa s s.........................Lo ck e d Clos ed
/
STV 30S01 Auxiliary Feed Pump Turbine Steam Inlet Control Valve.................... Closed
/
! II Turbine Casing Drain Valve............. Closed
/
Control Valve Steam Leakoff............Open
/
Lube Oil Cooling Water Outlet Isolations from pump bearing coolers (2).........
0 pen
/
Pump Casing Vents (2).................. Closed
/
Motor Driven Auxiliarv Feed Pump MCM-05S Condensate Storage Tank Outlet to Motor Driven Auxiliary Feed Pump............. Locked Open
/
1857 121
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A.51-13 Rev. 10
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ENCLOSURE 8.1 (Continued) 1st/2nd
)
E OP /0P VALVE NO.
"ALVE NAME POSITION INITIAL FWS-046 Motor Driven Auxiliary Feed Pump Suction Va1ve................................
Loc'ked Open
/
PI-31903 Pump P-319 Suction Pressure..................In Service
/
PI-31901 Pu=p P-319 Discharge Pressure................ In Service
/
FWS-054 Pump Dis charge Valve................. Locked Open
/
FWS-559 FWS-054 Bypass............................... Closed
/
FWS-052 Pu=p Recire Valve..................... Locked Open *
/
Pump Lube Oil Cooling Water Outlet Isolation from Pump Bearing Coolers (2)................Open
/
Pump Casing Ven ts (2)........................ Closed
/
19 Auxiliary Feed Water System
)
PWC-079 Folsom South Canal Water to Suction Motor Driven Auxiliary Feed Pu=p............ Locked Closed
/
4 WS-063 Auxiliary Feedwater to "A" Steam Generator Manual Isolation...................... Locked Open
/
FWS-554 FUS-063 Bypass.............................., Closed
/
FWS-064 Auxiliary Feedwater to "B" Steam Generator Manual Isolation...................... Locked Open
/
FWS-551 FWS-064 Bypass............................... Closed
/
FV-20527 Auxiliary Feedwater to "A" Steam Generator Automatic Isolation.......................... Closed
/
(Bailey in auto / manual and hand jack in neutral.)
FV-20528 Auxiliary Feedwater to "B" Steam Generator Automatic Isolation.......................... Closed
/
(Bailey in auto / manual and hand iack in neutral.)
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A.51 14 Rev. 9
d
[I ENCLOSURE 8.1 (Continued) 1st/2nd 7
Op /Op VALVE NO.
VALVE NAME POSITION IMITIAL HV-31826 Auxiliary Feed Header Cross Connect Isolation....................................Open
/
HV-31827 Auxiliary Feed Header Cross Connect Isolation....................................Open
/
FWS-079 Auxiliary Feedwater to Nuclear Service Cooling Water Surge Tank.....................Open
/
FWS-112 Auxiliary Feedwater to "B" Nuclear Service Cooling Water Surge Tank..................... Closed
/
FWS-lli Auxiliary Feedwater to "B" Nuclear Service Cooling Water Surge Tank..................... Closed
./
s 1HS-ll4 Auxiliary Feedwater to "A" Nuclear Service Cooling Water Surge Tank..................... Closed
/
FWS-113 Auxiliary Feedwater to "A" Nuclear Service Cooling Wa t er S urg e Tank..................... Closed
/
PCW-076 Folsom South Canal Water to Suction Turbine Driven Auxiliary Feed Pump............ Locked Closed
/
f" 1857 123
(
A.51-15
"*" 7
ENCLOSURE 8.1 (Continued)
(
1st/2nd I
Op /Op VALVE NO.
VALVE NAME POSITION INITIAL W
Steam Supolv to Auxiliary Feedwater Svstem MSS-006 Isolation Valve from Auxiliary Steam to Feed Pu7 Turbine K-308...................... Closed
/
HV-20569 Valve from Main Steam Line "A" to F.P.
T urb in e K-3 0 8................................ O p e n
/
MSS-050 Valve from Main Steam Line "A" to F.P.
Turb in e............................... Lo cked O p en
/
MSS-523 MSS-050 Bypass............................... Closed HV-20596 Valve from Mai'n Steam Line "B" to F.P.
T u rb in e..................................... 0 p e n
/
MSS-049 Valve from Main Steam Line "B" to F.P.
/
T urb in e............................... Lo cke d Ocen MSS-522 MSS-049 Bypass............................... Closed
/
PI-30803 Auxiliary F.P. Turbine Steam Supply Header Pressure.....................................In Service
/
TI-30804 Auxiliary F.P. Turbine Steam Supply Header
,l Temperature..................................In Service
/
s SFV-20577 Auxiliary Feedwater To 0TSGA................. Closed
/
SFV-20578 Auxiliary Feedwa ter to 0TSGB................. Closed
/
R1S-120 Auxiliary Feedwater From P-318 Isolation to OTS CA.,.,............................. Loc k e d O p en
/
MIS-562 M15-120 Bypass............................... Closed
/
W9-lla Auxiliary Feedwater From P-319. Isolation t o 0TSG B..............................Lo c ke d O p en
/
R1S-560 RIS-119 Bypass.
................... Closed
/
(,
ENCLOSURE 8.1 (Continued)
I lst/2nd op /Op VALVE NO.
VALVE NAME POSITION INITIAL WS126 OTSG "A" Chemical Recire, to Auxiliary WS128 Feed Isolation................................ Clo sed
/
9 WS125 OTSG "B" Chemical Recire. to Auxiliary WS127 Feed Isolation................................ Closed
/
DATE:
TI'!E STARTED:
TIME CO'IPLETED:
1ST OPERATOR:
2ND OPERATOR:
REMARKS:
\\.
A.51-17 Rev. 9 (F
1857 125
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fpn **%q'o, UNITED STATES
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NUC1. EAR REGULATORY COMMISS!CN
,7-I WASHWGTON, D. C. 20555
\\,bY June 27, 1979 Docket No. 50 312 Mr. J. J. Mattimae Assistant General Manager and Chief Engineer Sacramento Municipal Utlity District.
6201 S Street P. O. Box 15830 Sacramento, Califor fa 95813
Dear Mr. Mattimee:
By Order of May 7,1979, the Commission confimed your under.aking a seri.es of actions, both immediate and long tem, to increase the capability and reliability of the Rancho Seco Nuclear Generating Station to respond to various transient events.
In addition, the Order confirmed that you would shut dcwn Rancho Seco on April 28, 1979, and maintain the plant in a shut-dcwn condition until the folicwing actions had been satisfactorily coupleted:
(a) Upgrade the timeliness and reliability of delivery fran the Auxiliary Feedwater System by carrying out actions as identified in Enclosure 1 of your letter of April 27,1979.
(b) Develop and implement operating precedures for initiating and controlling auxiliary feedwater independent of Integrated Control System control.
(c)
Implement a hard-wired control-grade reactor trip that would be actuated on loss of main feedwater and/or turbine trip.
(d)
Ccmplete analyses for potential small breaks and develop and
~
implement operating instructions to define operator action.
(e)
Provide for one Senior Licensed Operator assigned to the control roon who has had Three Mile Island Unit No. 2 (TMI-2) training on the B&W simulator.
By submittal of May 14, 1979, as supplemented by seven letters dated May 22, 24,29,30(3) and June 6, 1979, you have documented the actions taken in response to the May 7 Order.
We have reviewed this submittal, and are satisfied that, with respect to Rancho Seco, you have satisfactorily canpleted the actions 1857 126 u$
o."
Edfddl A O h
9 0 2G 1L} U
o e
^
Mr. J. J. Mattimoe.
prescribed in items (a) through (e) of paragraph (1) of Section IV of the Order, the specified analyses are acceptable, and the specified implementing procedures are appropriate. The bases for these conclusions are set forth in the enclosed Safety Evaluation.
As noted on page 13 of the Safety Evaluation, you w'll be required to conduct a test during power operation to demonstrate operato capability to '.ssume mahJal Control of the Auxiliary Feedwater System independent of the Inte-grated Control System.
Appropriate Technical Specifications for Limiting Conditions for Operation and for suryefilance requirements should be developed as soon as practicable and provided to the staff within seven days with regard to the design and procedural changes which have been completed in compliance with the provisions of the May 7,1979 Commission Order.
The revise (Technical Specifications should cover:
(1) Addition of flow indication to the Auxiliary Feedwater System; (2) Addition of the Anticipatory Reactor Trips; and (3) Changes in set points for high pressure reactor trip and PORV actuation.
Within 30 days of receipt of this letter, you should provide us with your
- schedule for completion of the long tem modifications described in Section II of the May 7 Order,and you should submit for staff review the model used in the analysis for potential small breaks referenced in your letter of May 14, 1979.
My finding of satisfactory compliance with the requirements of items (a) through (e) of paragraph (1) of Section IV of the Order will pennit resumption of operation in accordance with the tems of the Commission's Order; it in no way affects your duty to continue in effect all of the above provisions of the Order pending your submission and approval by the Commission of the Technical Specifi-cation changes necessary for each of the required modifications.
Sincerely, G.
Harold R. De ton, Director Office of Nuclear Reactor Regulation 1857 127 Encl osures:
1.
Safety Evaluation 2.
Notice cc w/ enclosures:
See next page
~
e' EVALUATION OF LICENSEE'S COMPLIANCE WITH THE NRC ORDER DATED MAY 7, 1979 SACRAMENTO MUNICIPAL UTILITY DISTRICT f
s.,,
RANCHO SECO NUCLEAR GENERATING STATION DOCKET NO. 50-312 DUPIICATE DOCUMENT Entire document previously entered into system under:
hh ANO No. of pages:
.