L-PI-09-100, Supplement to License Amendment Request (LAR) to Apply Surveillance Requirement (SR) 3.0.2 Interval Extension to SR 3.8.1.8
| ML092670336 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/23/2009 |
| From: | Schimmel M Northern States Power Co, Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-PI-09-100, TAC ME0811, TAC ME0812 | |
| Download: ML092670336 (50) | |
Text
/@ Xcel Energym L-PI-09-100 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Supplement to License Amendment Request (LAR) to Applv Surveillance Requirement
/SR) 3.0.2 Interval Extension to SR 3.8.1.8 (TAC Nos. ME0811 and ME0812)
References:
- 1. Letter from Northern States Power Company, a Minnesota corporation (NSPM) to the Nuclear Regulatory Commission (NRC),
"License Amendment Request (LAR) to Apply Surveillance Requirement (SR) 3.0.2 Interval Extension to SR 3.8.1.8", dated March 5,2009, ADAMS Accession Number ML090641102.
- 2. Prairie Island Nuclear Generating Plant, Units 1 and 2 Request for Additional Information Related to License Amendment Request to Apply Surveillance Requirement (SR) 3.0.2 Interval Extension to SR 3.8.1.8 (TAC Nos. ME0811 and ME0812),
dated August 18,2009, ADAMS Accession Number ML092250428.
In Reference 1, NSPM, doing business as Xcel Energy, submitted an LAR for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, to revise Technical Specification (TS) 3.8.1, "AC Sources - Operating, SR 3.8.1.8 Frequency to allow use of the SR 3.0.2 interval extension. In Reference 2, NRC Staff requested additional information to support their review of Reference 1. The Enclosure 1 to this letter provides the responses to the NRC Staff requests for additional information. NSPM submits this supplement in accordance with the provisions of 10 CFR 50.90.
The supplemental information provided in this letter does not impact the conclusions of the Determination of No Significant Hazards Consideration and Environmental Assessment presented in the March 5, 2009 submittal as supplemented April 13, 2009.
1717 Wakonade Drive East .Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter to the designated State Official.
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1121.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments I declare under penait of rjury that the foregoing is true and correct.
Executed on SEP 3 Mark A. Schimmel Site Vice President Prairie Island Nuclear Generating Plant, Units 1 and 2 Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota
Enclosure 1 Nuclear Regulatory Commission (NRC) request for additional information (RAI) 1.)
According to Surveillance Requirement (SR) 3.8.1.8.c of the Prairie Island Nuclear Generating Plant (PINGP) Technical Specifications (TS), the ground fault trip is not bypassed on an actual or simulated safety injection signal, in Unit Ionly.
Explain the difference between Unit 1 and Unit 2 regarding this trip and provide the basis for not bypassing the ground fault trip for Unit 1.
Northern States Power Company, a Minnesota corporation (NSPM) response:
The emergency diesel generators (EDGs) for the two Prairie Island Nuclear Generating Plant (PINGP) units were installed at different times and manufactured by different companies to different specifications. The Unit 1 EDGs (Dl and D2) were installed as original plant equipment to support both Units 1 and 2 which became operational in December 1973 and December 1974, respectively. The Unit 1 EDG design was compared with the guidance of Safety Guide 9, issued in March 1971, which discussed overspeed protection, but does not provide specific guidance for critical trips. The original design of the Unit 1 EDGs provided protection from significant electrical failures during a safety injection event which included generator differential and ground fault protection as detected by a diesel output circuit breaker. Specific test requirements for the bypass relay were first introduced in the PINGP TS by license amendments (LA) 25 and 19, for Units 1 and 2 respectively, issued January 18, 1978. The surveillance requirement in this LA required verification that the engine overspeed and generator differential current are automatically bypassed. Subsequently in LAs 49 and 43, for Units 1 and 2 respectively, dated July 28, 1981, the NRC issued a revision of the EDG trip test "to include a trip of the diesel generator on occurrence of a ground fault, as well as engine overspeed and generator differential current in the list of trips that are not automatically bypassed on receipt of a safety injection signal. The proposed change clarifies the TS to be consistent with the previously existing diesel generator design."
The Unit 2 EDGs (D5 and D6) were installed in the early 1990s in response to the station blackout rule and became operational in 1992. These EDGs were designed to meet the requirements of Regulatory Guide (RG) 1.9, Revision 2. The critical trips on Unit 2 EDGs (D5 and D6) are based on the guidance in RG 1.9, Revision 2 which discusses trips of the diesel generators based on overspeed conditions or a generator differential in order to protect the EDGs from damage or degradation.
NRC RAI 2.) Submit for the NRC staffs review, the applicable portions of representative procedures for performing SR 3.8.1.8 and relevant representative drawings showing the relays that provide the function to bypass the emergency diesel generator non-critical automatic trips on an actual or simulated safety injection signal. Also, discuss whether critical trips are tested as part of SR 3.8.1.8 or some other plant procedure.
Page 1 of 2
NSPM NSPM response:
The procedures for performing SR 3.8.1.8 are SP-1150 (Dl), SP-1306 (D2), SP-2150 (D5), and SP-2306 (D6). SP-1150 and SP-2306 are attached for review as a representative procedure for each unit. Additionally, as requested, representative logic drawings for each unit showing how the MCA (Maximum Credible Accident) and SlMR (Safety Injection Master Relay) relays operate, and bypass the non-critical trips during a safety injection signal, are attached.
The critical trips (engine overspeed, generator differential current, and ground fault (Unit 1 only)) are not tested as a part of surveillance procedures SP-1150, SP-1306, SP-2150, and SP-2306.
The proper operation of the components that perform these critical trips are tested during routine maintenance. The generator differential current and ground fault (Unit 1 only) trips are tested as a part of the relay calibration procedures for each EDG. The diesel generator relay calibration and functional testing procedures test the generator differential relays and the ground fault relays (Unit 1 only) to verify that each will properly actuate the respective diesel generator lockout relays. These relay calibration procedures are performed on a four year frequency. The proper operation of the overspeed trip function is verified during the routine diesel generator inspection procedures which are performed on a two year frequency.
Attachments Page 2 of 2
Attachment 1 SP-I 150, D l Diesel Generator Relay Functional Test 14 pages follow
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR SP 1150 RELAY FUNCTIONAL TEST I Page 1 of 14 1 SYSTEMS: Dl, E l WO:
RESULTSICOMMENTS: I Work Request Initiated: YES NO - No.
Test Performance:
Performed By: Date:
(Signature or Initials)
Additional Requirements:
NONE
/I SP Completion:
Shift Supervisor: Date:
1 SP Surveillance Schedule Satisfied. YESINO Surv. Admin:
I Other Actions for Consideration:
System Engineer Review: Date:
PORC REVIEW DATE: OWNER: EFFECTIVE DATE L NR P. Zamarripa 4114108
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR RELAY FUNCTIONAL TEST I Page 2 of 14 1 1.0 PURPOSE AND GENERAL DISCUSSION COA1TfIVUOUS USE Continuous use of procedure required.
Read each step prior to performing.
Mark off steps as they are completed.
Procedure SHALL be at the work location.
1.1 This test fulfills T.S. SR 3.8.1.8 requirements that the diesel generator system trips are automatically bypassed on a safety injection signal (except, for engine overspeed, ground fault and generator differential current).
1.2 This test provides post-maintenance testing for relays T3A and TDR5 for maintenance performed in PM 3001-4-Dl. The D l Diesel Generator is isolated during this test, this prevents starting and stopping the diesel.
1.3 This test is to be performed every 24 months in conjunction with PM 3001-2-Dl and PM 3001-4-Dl.
1.4 Steps in this procedure that are not acceptance criteria (not asterisked) are to be observed and inconsistencies noted. If there is significant deviation or questions as to the operability, contact the Shift Supervisor or System Engineer for guidance.
1.5 Acceptance Criteria General In the event Acceptance Criteria (designated with an *) cannot be met, refer to Ops.
Manual Section G, Surveillance and Periodic Test Program, for additional guidance.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR RELAY FUNCTIONAL TEST I Page 3 of 14 1 1.6 Acceptance Criteria D l -
1.6.1 Verify that energizing the safety injection (MCA) Relay causes the following diesel trips to be blocked:
Low Lube oil pressure (Steps 7.11.2, 7.11.3)
High jacket coolant temperature (Steps 7.11.2, 7.11.3)
High crankcase pressure (Steps 7.11.2, 7.1 1.3)
Reverse current relay (67X) (Step 7.8.3) 1.6.2 Verify that the following conditions lock out the diesel:
Low lube oil pressure (Steps 7.14.4, 7.14.5)
High jacket coolant temperature (Steps 7.14.4, 7.14.5)
High crankcase pressure (Steps 7.14.4, 7.14.5) 1.6.3 Verify that energizing the EMERGENCY GEN 86 RELAY locks out the engine. (Step 7.17.4) 1.6.4 During the performance of this test, the D l Diesel Generator and the Bus 15 sequencer are in Technical Specification ConditionIAction Statements, therefore, if any part of the acceptance criteria is not met:
Notify the System Engineer Write a WO.
2.0 REFERENCES
2.1 SR 3.8.1.8, Perform every 24 months 2.2 T.S.3.8.1, AC Sources-Operating 2.3 T.S.3.8.2, AC Sources-Shutdown 2.4 T.S.3.3.4, 4kV Safeguards Bus Voltage Instrumentation
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR SP 1150 1 RELAY FUNCTIONAL TEST I REV: 24 1 I Page 4 of 14 1 2.5 Preventive Maintenance Procedure:
2.5.1 PM 3001-2-Dl, D l Diesel Generator 18 Month Inspection. ( D l is logged out for this PM) 2.5.2 PM 3001-4-Dl, D l Diesel Generator Electrical Inspection. (Dl Relays are tested for this PM) 2.6 Wiring Diagram: XH-28-46, Connection Diagram D l Power Unit 2.7 Tech Manual: XH-28-44! Diesel Generator Set 2.8 Electrical Schematics:
2.8.1 NE-40006 SH 41 & 81, Diesel Generator Voltage, Frequency Detection and Undervoltage 2.8.2 NF-40009 SH 72, 73, 74, 75 & 79 D l Emergency Generator 2.8.3 NF-40253 SH 1 & 2, Wiring Diagram D-I Emergency Generator Control Panel 2.9 Logic Diagrams:
2.9.1 NF-40325-1, -2, D l Diesel Generator Control Logic 2.9.2 NF-40019-7, D l Emergency 2.10 Operations Procedures: C20.5-1, 4.16KV Breaker Rack OutIRack In 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Plan activities in advance to prevent relays and solenoids from being energized for an extended period of time.
3.2 This procedure SHALL NOT be performed in Mode 5, Cold Shutdown or Mode 6, Refueling, when the Bus 15 Load sequencer is credited for compliance with T.S. LC0 3.8.2.
3.3 Treat all terminal block and relay terminals as energized at 120VAC or 125VDC.
3.4 Bus 15 is most likely energized at 4KV.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE I I NUMBER:
D l DIESEL GENERATOR RELAY FUNCTIONAL TEST Page 5 of 14 4.0 PERSONNEL AND SPECIAL EQUIPMENT REQUIREMENTS 4.1 Suggested Personnel 4.1.1 One (1) Control Room Operator - to record data and do manual operations.
4.1.2 Two (2) Electrical Maintenance Personnel - to perform electrical manipulations 4.2 Special Equipment 4.2.1 One (1) Voltmeter 4.2.2 Bypass jumpers with banana plug ends.
5.0 SPECIAL CONSIDERATIONS 5.1 Load Sequencer must be taken out of service for this inspection. The bus is placed in an analyzed condition per this WO for SI block loading prior to the load sequencer being placed in "MANUAL." This ensures the bus is in an operable condition.
5.2 All Train B required features supported by 0 2 Diesel Generator are required to be operable while in this test. IF any required Train B features become inoperable, THEN evaluation per 5AWI 3.15.8, Safety Function Determination Program SHALL be performed.
5.3 If voltage is lost to BUS 15, operator action is required to restore power to BUS 15 1 per 1C20.5 AOP1.
5.4 Banana plug bypass jumpers should be used to minimize the risk of shorting adjacent terminals during connection. (Reference T-Track item RCE 52.) Test equipment leads with banana plug connectors should be used whenever banana jacks are available.
6.0 PREREQUISITES AND INITIAL CONDITIONS 6.1 D l Diesel Generator is tagged out per PM-3001-4-Dl (except for BKR 15-2 ground truck and CS-46935).
OPS 6.2 D l Diesel Generator is logged out per PM-3001-2-Dl OPS
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE I 1 NUMBER: I D l DIESEL GENERATOR RELAY FUNCTIONAL TEST Page 6 of 14 6.3 D l local annunciator, ENGINE OVERSPEED, is LIT (indicating the fuel racks are tripped).
6.4 BUS 15 and BUS 16 must be powered from separate offsite sources. Verify one of the following and NA the other:
IF BUS 15 is being powered from BKR 15-3 (Reserve Aux Xfmr), THEN BUS 16 must be powered from BKR 16-8 (Cooling Tower Xfmr).
OPS IF BUS 15 is being powered from BKR 15-7 (Cooling Tower Xfmr), THEN BUS 16 must be powered from BKR 16-2 (Reserve Aux Xfmr).
OPS 6.5 Verify Grid Voltage alarm limits are appropriate for the electrical configuration (refer to C20.3).
OPS 6.6 Verify that the following control switches in "SLOW."
CS-46018, 11 CNTMT FAN COlL UNlT OPS CS-46019, 13 CNTMT FAN COlL UNlT OPS 6.7 Verify one of the following and NA the other:
CS-49010, 121 AIR COMPR PRFRDII STBYl2STBY in "PREFERRED" OPS CS-46096, 121 AIR COMPR STARTISTOP, in "PULLOUT" OPS 6.8 MCC I T 1 is powered from BUS 112, THEN verify 121 Control Room Water Chiller is running.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR SP RELAY FUNCTIONAL TEST Page 7 of 14 7.0 PROCEDURE All steps are to be performed by electricians unless NOTE: otherwise noted.
7.1 Conduct a pre-job briefing per PlNGP 1112.
7.2 Take BUS 15 Load Sequencer out of service.
Standby, and Mode 4, Hot Shutdown T.S.3.3.4,4 Safeguards Bus Voltage Instrumentation, Condition C is entered, in Mode 5, Cold Shutdown, and Mode 6, Refueling, T.S.3.3.4, Condition E is entered, due to Bus 15 Load 7.2.1 IF in Mode 1, Power Operation, Mode 2, Startup, Mode 3, Hot Standby or Mode 4, Hot Shutdown, THEN notify the Shift Supervisor T.S. LC0 3.3.4 is NOT met and enter CONDITION C.
Entered CONDITION C at:
time Add Four (4) Hours + 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> I
-IF LC0 3.3.4 Condition C for Bus 15 Load Sequencer is NOT exited by entry time + 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, THEN SP 1095 Bus 16 Load Sequencer Test SHALL be performed starting at: -
hours 7.2.2 Hang Caution tag per Clearance Order for the SS on CS-46932, BUS 15 VOLTAGE RESTORATION SEL SW.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR SP RELAY FUNCTIONAL TEST Page 8 of 14 7.2.3 Inside BUS 15 Load Sequencer cabinet, place BUS 15 Load Sequencer switch SW8 in "TEST."
7.2.4 Verify indicating light, LT2, BLOCKING RELAYS ENERGIZED, is ON.
The following steps, unless othetwise noted, are performed NOTE: at the Local Relay Panel on D l Skid.
7.3 Lift wire 2M at Relay 62TD2 to prevent 62TD2 from picking up 62XTD2 (Terminal 6 of 62TD2lD1 - Dwg XH-28-46 & NE-40009-74).
7.4 Manually pick up and hold MCA Relay (Clark Relay) located in D l EMER GEN Relay Cabinet in D l Room for the next step.
7.5 Depress CS-55021, D l DSL GEN ALM AND SHTDN RESET PB, at D l Diesel Gauge Panel to verify SDR Relay is reset.
7.6 Release MCA Relay and verify it remains energized.
7.7 Place CS-46935, D l DIESEL GENERATOR, in "NEUTRAL" on G I Panel OPS 7.8 Perform the following:
7.8.1 Verify EMERGENCY GEN LOCKOUT RELAY 86 is reset at D l EMER GEN Relay Cabinet in D l Room (red flag not visible).
7.8.2 Install a jumper from wire 67X-P22 (NF-40172, TB on right side of cabinet) to wire Dl-RT1 (below 67X-P22 on TB) to bypass the 67XlGGP relay (NE-40006-81).
- 7.8.3 Verify relay 861D1, D l Emergency Generator Lockout, does NOT actuate (red flag not visible).
7.8.4 Remove jumper from wire 67X-P22 (NF-40172, TB on right side of cabinet) to wire Dl-RT1 (below 67X-P22 on TB).
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR SP 1150 SP RELAY FUNCTIONAL TEST REV: 24 Page 9 of 14 7.9 Verify local Annunciator 55300-0104, LUBE OIL PRESSURE LOW, is Not ON.
NOTE: The following step may cause several alarms to come in.
7.10 Place a jumper between wire 2C (TB-B10) and wire D l 1P (TB-62) to energize T3A (enables Raw Water Press Low Local Annun. and shutdown circuitry), located in generator relay box D l - 3 (Dwg XH-28-46 & NE-40009-73). (Will be removed in Step 7.18.)
7.11 Verify MCA Relay is preventing engine shutdown from low lube oil pressure.
7.11 .I In the D l Relay Cabinet, connect a voltmeter between wires D l - 1P (TB-62) and 2H (Terminal 2 of Relay 5A) to monitor signals to the governor shutdown solenoid (Dw~ XH-28-46 & NE-40009-74).
- 7.1 1.2 Verify OPEN circuit voltage on meter (approx. 130VDC).
- 7.1 1.3 Verify local Annunciator 55300-0104, LUBE OIL PRESSURE LOW, is ON.
7.1 1.4 Lift wire 2V (TB-10) to disable the engine low lube oil pressure trip (Dwg XH-28-46 & NE-40009-74). (Will be reterminated in Step 7.17) 7.1 1.5 Verify 55300-0104, LUBE OIL PRESSURE LOW alarm is Not ON.
7.12 Reset MCA Relay from G I Panel using CS-46967, D l DSL GEN SI MCA RESET.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE I
NUMBER:
D l DIESEL GENERATOR SP 1150 RELAY FUNCTIONAL TEST Page 10 of 14 7.13 In BUS 15 Room, place BKR 15-2, BUS 15 SOURCE FROM D l DSL GEN, in "TEST" as follows:
7.13.1 Remove BKR 15-2, from the cubicle and install shutter barrier.
7.13.2 Put BKR 15-2 back in the cubicle.
7.13.3 Place "Barrier Installed" tags on the racking mechanism of BKR 15-2.
7.13.4 Rack BKR 15-2 to "TEST" per C20.5-1.
7.13.5 CLOSE DC knife switch for BKR 15-2.
7.13.6 Place CS-46950, BUS 15 SOURCE FROM D l DSL GEN, in "NORMAL."
OPS 7.14 Verify the following condition locks out the engine and trips BKR 15-2, BUS 15 SOURCE FROM D l DSL GEN.
7.14.1 CLOSE BKR 15-2 using the CLOSE pushbutton on the breaker face inside cabinet above manual closure lever.
7.14.2 Momentarily (1 to 3 seconds) place a jumper between wire 3E and 2T (TB-B10) to energize relay CCR (simulate high crankcase pressure) in Gen Relay Box D l -3 (XH-28-46 & NE-40009-74).
7.14.3 Remove jumper between wire 3E and 2T (TB-BIO) to de-energize relay CCR.
- 7.14.4 Reset SDR relay by depressing CS-55021, D l DSL GEN ALM AND SHTDN RESET PB, at D l Diesel Gauge Panel.
- 7.14.5 Verify EMERGENCY GEN LOCKOUT RELAY 86 is TRIPPED at D l EMER GEN Relay Cabinet in D l Room (red flag visible).
7.14.6 Reset EMERGENCY GEN LOCKOUT RELAY 86 at D l EMER GEN Relay Cabinet in D l Room (red flag not visible).
7.14.7 At BKR 15-2 cubicle, verify BKR 15-2 is OPEN.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR RELAY FUNCTIONAL TEST Page 11 of 14 7.15 In BUS 15 Room, place BKR 15-2, in "DISCONNECT" as follows:
7.15.1 Place CS-46950, BUS 15 SOURCE FROM D l DSL GEN, in "PULLOUT."
OPS 7.15.2 OPEN DC knife switch for BKR 15-2.
7.15.3 Rack BKR 15-2, to "DISCONNECT1'per C20.5-1.
7.15.4 Remove BKR 15-2, from the cubicle.
7.15.5 Remove shutter barrier from cubicle.
7.15.6 Place BKR 15-2, to locked "DISCONNECT.
7.15.7 Remove "Barrier Installed" tag from the racking mechanism of BKR 15-2.
7.16 Return BUS 15 Load Sequencer to Service as follows:
7.16.1 Remove Secure Tag per Tag Section hung in Step 7.2.2.
Tag Section OPS 7.16.2 Place CS-46932, BUS 15 VOLTAGE RESTORATION SEL SW, in "AUTO."
OPS 7.16.3 Inside the BUS 15 Load Sequencer cabinet, place BUS 15 Load Sequencer switch SW8 to "NORM."
7.16.4 Verify Annunciator 47024-1001, BUS 15 SEQUENCER NOT IN SERVICE, is Not ON.
OPS 7.16.5 Notify the Shift Supervisor to exit T.S. LC0 3.3.4 CONDITION C or E entered in Step 7.2.1.
Time of LC0 Exit:
time Exited CONDITION C at:
time
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR SP RELAY FUNCTIONAL TEST Page 12 of 14 7.16.6 Return the following 480V loads to a status as directed by Shift Supervisor:
A. 121 Air compressor B. 11 CFCU C. 13 CFCU D. 121 Control Room Chiller OPS NOTE: The following step may cause several alarms to come in.
7.17 Verify the following conditions lockout the engine:
7.17.1 Momentarily (1 to 3 seconds) place a jumper between wires 3C and 2T (TB-B10) to energize relay CTH (simulate high jacket coolant temperature) in Gen Relay BOXD l - 3 ( D w ~XH-28-46 & NE-40009-74).
7.17.2 Remove jumper between wires 3C and 2T (TB-B10) to de-energize relay CTH.
7.17.3 Reset SDR Relay by depressing CS-55021, D l DSL GEN ALM AND SHTDN RESET PB, at D l Diesel Gauge Panel.
- 7.17.4 Verify EMERGENCY GEN LOCKOUT RELAY 86 is TRIPPED at D l EMER GEN Relay Cabinet in D l Room (red flag is visible).
7.17.5 Reset EMERGENCY GEN LOCKOUT RELAY 86 at D l EMER GEN Relay Cabinet in D l Room (red flag not visible).
7.17.6 Reterminate wire 2V (TB-BIO), that was lifted in Step 7.11.4, to enable low oil pressure to trip the engine (Dw~ XH-28-46).
7.17.7 Perform Independent Verification that wire 2V (TB-610) is reterminated.
IV 7.17.8 Verify EMERGENCY GEN LOCKOUT RELAY 86 is TRIPPED at D l EMER GEN Relay Cabinet in D l Room (red flag is visible).
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE 1 I I NUMBER: I D l DIESEL GENERATOR I SP1150/
RELAY FUNCTIONAL TEST I REV: 24 1 Pane 13 of 14 7.18 Remove jumper, that was placed in Step 7.10, between wires 2C (TB-B10) and D l 1P (TB-B2) to de-energize T3A (Dwg XH-28-46) in Gen Relay Box Dl-3.
7.19 Reset SDR Relay by depressing CS-55021, D l DSL GEN ALM AND SHTDN RESET PB, at D l Diesel Gauge Panel.
After approximately four (4) minutes, verify CLOSED circuit voltage on meter (approx. OVDC).
Reset EMERGENCY GEN LOCKOUT RELAY 86 at D l EMER GEN Relay Cabinet in D l Room (red flag not visible).
Verify OPEN circuit voltage on meter after about 3 minutes (approx. 125VDC).
Remove meter leads connected from 2H to D l 1P -
( D w XH-28-46).
~
Reterminate wire 2M to relay 62/TD2 (terminal 6 of 62/TD2D1 -
D w XH-28-46).
~
Perform Independent Verification wire 2M to relay 62/TD2 is reterminated.
Place CS-46935, D l DIESEL GENERATOR, in "PULLOUT" on G I Panel..
OPS Notify the Control Room that the test has been completed.
Complete a Calibrated Tool Usage Form and attach.
ELECT Return to PM 3001-4-Dl.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:
D l DIESEL GENERATOR SP 1150 RELAY FUNCTIONAL TEST REV: 24 1 I Page 14 of 14 1 8.0 ADDITIONAL REQUIREMENTS NONE 9.0 ATTACHMENTS NONE
Attachment 2 SP-2306, D6 Diesel Generator Relay Functional Test 24 pages follow
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST REV: 11 Page 1 of 24 SYSTEMS: D6 WO:
RESULTSICOMMENTS: 1 Test Performance:
Performed By: Date:
(Signature or Initials)
Additional Requirements:
NONE SP Completion:
Shift Supervisor: Date:
SP Surveillance Schedule Satisfied. YESINO Supv. Admin:
Other Actions for Consideration:
System Engineer Review: Date:
PORC REVIEW DATE: OWNER: EFFECTIVE DATE NR P. Zamarripa 10115107
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES r NUMBER:
D6 DIESEL GENERATOR SP 2306 RELAY FUNCTIONAL TEST REV: 11 Page 2 of 24 1.0 PURPOSE AND GENERAL DISCUSSION CONT1NUOU.S USE Continuous use of procedure required.
Read each step prior to performing.
I Mark off steps as they are completed. I Procedure SHALL be at the work location.
1.1 Purpose 1.I.I This procedure is performed every 24 months to meet the requirements of T.S. SR 3.8.1.8.
1.I.2 This functional test verifies that the D6 Diesel Generator System trips, except for those for engine overspeed, and the generator differential current trip are automatically bypassed with a safety injection signal.
1.I.3 This diesel generator test consists of:
A. Verification that energizing the SlMR Relay blocks a diesel trip from the following conditions:
HT Cooling Water High-High Temperature Lube Oil High-High Temperature Low Oil Pressure High Crankcase Pressure HT Cooling Water Low Pressure LT Cooling Water Low Pressure Voltage Restrained Overcurrent Loss of Excitation Overvoltage
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST REV: 11 Page 3 of 24 Overcurrent Generator Bearing High Temperature Electronic Governor Fuel Rack RDD Failure B. Verification that energizing the SlMR Relay blocks trip of Breaker 26-16 on a Reverse Current signal.
Acceptance Criteria General 1.2.1 General In the event Acceptance Criteria cannot be met, refer to Ops. Manual Section G, "SURVEILLANCE AND PERIODIC TEST PROGRAM" for additional guidance.
1.2.2 Diesel Generator Trips A. The energized SlMR Relay blocks a diesel trip from the following conditions:
HT Cooling Water High-High temperature Lube Oil High-High Temperature Low Oil Pressure High Crankcase Pressure HT Cooling Water Low Pressure LT Cooling Water Low Pressure Voltage Restrained Overcurrent Loss of Excitation Overvoltage Overcurrent Generator Bearing High Temperature Electronic Governor Fuel Rack RDD Failure
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP 2306 RELAY FUNCTIONAL TEST Page 4 of 24 B. The energized SlMR Relay blocks a trip of Breaker 26-16 on a Reverse Current signal.
C. the energized SlMR Relay does not block any of the above signals THEN:
- 1. Notify the System Engineer
- 2. Write a Work Request.
1.3 General Discussion 1.3.1 Every step identified by an asterisk (*) must be acceptable for this test to be acceptable. any acceptance step is not met, THEN the Shift Supervisor SHALL be notified immediately.
1.3.2 Steps in this procedure that are not acceptance criteria (not asterisked) are to be observed and inconsistencies noted. If there is significant deviation or questions as to the operability, contact the Shift Supervisor or System Engineer for guidance.
1.3.3 Several steps of this procedure are required to be performed by Operations Personnel outside the Control Room, the steps SHALL be identified by a "pound sign" (#).
2.0 REFERENCES
2.1 Electrical Drawings:
2.1 . I NE-116786-30 "D6 Emergency Generator Bus 26 Cubicle 16" 2.1.2 NE-116757-2 through NE-116757-35 "D6 Emergency Generator Schematic Diagrams1' 2.1.3 NE-120693-1 through NE-120693-3 "External Wiring Diagram D6 Diesel Gen. Vertical Panel" 2.1.4 NR-156981 Series, Internal Wiring Diagram D6 DG Vertical Panels 2.1.5 XH-2713-10 Series, Load Sequencer
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST REV: 11 Page 5 of 24 2.2 Tech Specs:
2.2.1 T.S. SR 3.8.1.8 2.2.2 T.S.3.8.1, AC Sources-Operating 2.2.3 T.S.3.8.2, AC Sources-Shutdown 2.2.4 T.S.3.3.4, 4kV Safeguards Bus Voltage Instrumentation N 2.3 Generic Letter 96-01, Testing of Safety Related Logic Circuits 2.4 Implementing Procedures:
2.4.1 C20.5-1, 4KV Breaker Rack InIRack Out Procedure 2.4.2 Safety Card Stock Isolation SP 2306 2.4.3 5AWI 8.7.0, Foreign Material Exclusion Program Description 3.0 PRECAUTIONS AND LIMITATIONS 3.1 When resetting the 86 D6 GEN LOCKOUT do not leave the switch in the reset position any longer than needed to avoid burning out the coil. Plan activities well in advance to prevent keeping relays and solenoids energized for an extended period of time.
3.2 This procedure SHALL NOT be performed in Mode 5, Cold Shutdown or Mode 6, Refueling, when the Bus 26 Load Sequencer is credited for compliance with T.S. L C 0 3.8.2.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES D6 DIESEL GENERATOR RELAY FUNCTIONAL TEST 4.0 PERSONNEL AND SPECIAL EQUIPMENT REQUIREMENTS 4.1 Suggested Personnel 4.1.1 One (1) Control Room Operator - to record data and do manual operations 4.1.2 Two (2) Electrical Maintenance Personnel - to perform electrical manipulations 4.1.3 Two (2) I&C Personnel - to perform Engine Pressure Trip Testing 4.2 Special Equipment 4.2.1 Key Hook No. 204, D5 or D6 MNTCEINORM MOD SEL SW 4.2.2 Voltmeter 4.2.3 I&C valved air harness for D5lD6 Engine Pressure Trip Testing 4.2.4 Test jumpers with banana plug ends.
5.0 SPECIAL CONSIDERATIONS 5.1 Load sequencer must be taken out of service for this inspection. The bus is placed in an analyzed condition per this WR for SI block loading prior to the load sequencer being placed in manual. This ensures the bus is in an operable condition.
5.2 All Train A required features supported by D5 Diesel Generator are required to be operable while in this test. any required Train A features become inoperable, THEN evaluation per 5AWI 3.15.8, Safety Function Determination Program, SHALL be performed.
5.3 T.S.3.3.4, 4kV Safeguards Bus Voltage Instrumentation, specifies the Required Actions that must be completed when removing the load sequencer from service.
5.4 Voltage is lost to Bus 26, THEN operator action is required to restore power to the Bus 26 per 2C20.5 AOP2.
5.5 Steps preparing to take Bus 26 Sequencer OOS and installation of a shutter barrier in cubicle 26-16 may be done prior to pre-job brief.
5.6 For steps noting a wire number, it is acceptable to verify the wire number is physically connected where specified by tracing jumperslwires internal to the associated panel. For example, IF an external wire is connected to terminal 1 terminal 1 is jumpered to terminal 10 AND terminal 10 is jumpered to terminal 15, THEN the external wire is considered to be connected to terminals 1, 10 and 15.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST REV: 11 Page 7 of 24 5.7 Banana plug bypass jumpers should be used to minimize the risk of shorting adjacent terminals during connection. (Reference T-Track item RCE 52). Test equipment leads with banana plug connectors should be used whenever banana jacks are available.
5.8 Alligator clip end on bypass jumper must be used for times when banana plug connection is not available at a terminal block.
5.9 The following annunciators are expected during this test:
47524-0604 BUS 26 BKR 16 SOURCE FROM D6 EMERGENCY GEN CLOSED 47524-0605 D6 EMERGENCY GENERATOR SI SIGNAL EMERGENCY START 47524-0706 D6 EMERGENCY GENERATOR LOCKED OUT 47524-0804 BUS 26 SEQUENCER IN TROUBLE 47524-0806 D6 EMERGENCY GENERATOR SHUT DOWN 47524-0905 D6 EMERGENCY GENERATOR REVERSE POWER BKR TRIP 47524-1004 BUS 26 SEQUENCER NOT IN SERVICE 47524-1005 D6 EMERGENCY GENERATOR TRIP ERCS:
2Y8092D D6 ENGI FUEL OIL FEED PRESS LOW 2Y8093D D6 ENG2 FUEL OIL FEED PRESS LOW Other ERCS alarms will be received for tested function.
6.0 PREREQUISITES AND INITIAL CONDITIONS 6.1 Attach completed white copy of Form 17-4048, Calibrated Tool Usage, to this procedure and place the yellow copy in the out basket.
6.2 D6 OOS for maintenance and logged OOS per LC0 3.8.1 OR L C 0 3.8.2, as applicable.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST REV: 11 Page 8 of 24 6.3 D6 Diesel Generator is isolated appropriately - Electrical (Exceptions allowed for ground truck in 26-16, BKR 26-16, BKR 81MID6).
OPS 6.4 Generate Stock Isolation SP 2306 D6 Diesel Generator Relay Functional Test.
OPS 7.0 PROCEDURE 7.1 Conduct a pre-job brief using PlNGP 1112.
The following steps, unless otherwise noted, are performed NOTE: at D6 Vertical Panel.
All steps are to be performed by electricians unless NOTE: otherwise noted.
7.2 Verify a temporary lift has been performed as required for BKR 26-16, CS-46944, and DC control power to D6 Generator control circuits (BKR 81MID6). (NA if not required).
Temp Lift No.:
PLANT ENG
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST REV: 11 Page 9 of 24 7.3 Take Bus 26 Load Sequencer Out of Service Bus 25 and Bus 26 must be powered from separate offsite sources.
7.3.1 Verify one of the following (NA the unused step):
A. Bus 25 is being powered from BKR 25-16, THEN Bus 26 must be powered from BKR 26-13.
OPS B. Bus 25 is being powered from BKR 25-5, THEN Bus 26 must be powered from BKR 26-2.
- 7.3.2 Bus 27 is powered from Bus 26, THEN perform 2C20.5 Section 5.18, to transfer Bus 27 to Bus 25 from Bus 26.
OPS 7.3.3 Verify Grid Voltage alarm limits are appropriate for the electrical configuration (refer to C20.3).
OPS 7.3.4 Verify the following control switches are in "SLOW:"
CS-46551, 22 CONTAINMENT FAN COlL SEL SW OPS CS-46552, 24 CONTAINMENT FAN COlL SEL SW OPS 7.3.5 MCC I T 2 is powered from Bus 222, THEN verify 122 Control Room Water Chiller is running.
OPS AND Verify 122 Control Room Air Supply Fan is running, CS-46075.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP 2306 RELAY FUNCTIONAL TEST 7.3.6 Secure either 21 or 23 Charging Pump:
A. the pump to be secured is running, THEN swap pumps per 2C12.1.
OPS B. Place Control Switch for the pump to be secured in PULLOUT:
CS-49550,21 CHARGING PUMP OPS OR CS-49552, 23 CHARGING PUMP OPS In Modes 1, Power Operation, Mode2, Startup, Mode 3, Hot Standby, and Mode 4, Hot Shutdown T.S.3.3.4,4kV Safeguards Bus Voltage Instrumentation, Condition C is NOTE: entered, in Mode 5, Cold Shutdown, and Mode 6, Refueling, T.S.3.3.4, Condition E is entered, due to Bus 26 Load Sequencer out of service.
7.3.7 IF in Mode 1, Power Operation, Mode2, Startup, Mode 3, Hot Standby, or Mode 4, Hot Shutdown, THEN notify the Shift Supervisor T.S. LC0 3.3.4 is NOT met and enter CONDITION C.
Entered CONDITION C at:
time 7.3.8 Place CS-46931, BUS 26 VOLTAGE RESTORATION SEL SW, in "MANUAL."
OPS 7.3.9 Hang a Secure Tag per Tag Section 2-D6 SP2306-SS SP 2306, D6 DIESEL GENERATOR FUNCTIONAL TEST, for the SS. (Reference Master Tagout 2-D6 SP2306-SS)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES I NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST Page 11 of 24 The following status lights and alarm will energize on the next step:
44324-0103, SEQUENCER IN TEST NOTE: 44324-0104,2RY SOURCE TROUBLE 44324-0105, CT12 SOURCE TROUBLE 44324-0106, D6 SOURCE TROUBLE 47524-0804,26 SEQUENCER TROUBLE ALARM 7.3.10 In the Bus 26 Load Sequencer Cabinet, place Bus 26 Load Sequencer switch SW8, Blocking Relays, in "TEST."
7.3.11 Check LT17, BLOCKING RELAYS ENERGIZED, light is LIT (inside sequencer cabinet).
7.3.12 Check LT2, BLOCKING RELAYS ENERGIZED, light is LIT.
7.4 Simulate an Emergency Start Signal
- # 7.4.1 Verify the following switch positions to provide a current path to the SlMR Relay:
A. CS-60208, D6 DSL GEN CONTROL MODE SEL SW, in "NORMAL" OPS B. CS-60210, D6 ENG IIENG 2 START SEL SW, in "ENGINE 1 & 2" OPS C. CS-60215, D6 DSL GEN VOLTAGE REGULATOR MODE SEL SW, in "AUTO" OPS 7.4.2 Place BKR 26-16 in "TEST as follows:
A. Remove BKR 26-16 from the cubicle and install shutter barrier.
B. Install the breaker back in the cubicle and place "Barrier Installed" tags on the racking mechanism on BKR 26-16.
C. Place BKR 26-16 in "TEST" per C20.5-1.
D. CLOSE the DC knife switch for BKR 26-16.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP RELAY FUNCTIONAL TEST Page 12 of 24 7.4.3 Place CS-46944, BUS 26 SOURCE FROM D6, in "NORMAL."
OPS 7.4.4 On left side of Vertical Panel 4 lift lead at contact terminal 10 on SFR (wire SFR-10) Start Failure Relay to prevent picking up the ESR (Emergency Start Relays) when the SI start is simulated. (NE-116757 SH.2, NF-156981 Sh.3) 7.4.5 On left side of Vertical Panel 4 connect one end of jumper to terminal 16 of VP2-I (wire D6-SIM2, goes to SIMR).
(NE-116757-2 and NF-156981-3) 7.4.6 Connect remaining lead to terminal 18 of VP2-I to energize SlMR (wire D6-ESI). (NE-116757-2 and NF-156981-3)
- 7.4.7 Verify 86 D6 GEN LOCKOUT is NOT TRIPPED or reset 86 D6 GEN LOCKOUT.
- 7.4.8 Verify EMERG START ACTUATED red light on CS-46958, D6 DSL GEN EMERG START & EMERG START RESET, is LIT at G2 Panel.
OPS Due to circuit configuration, the SlMR block of the 86 NOTE: LORID6 relay only has to be tested from one blocked trip source.
7.5 Verify the SlMR Relay blocks a diesel trip from the following conditions:
7.5.1 Verify Annunciator 60001-0303, HT CLG WTR TEMP HI-HI TRIP, is NOT LIT.
7.5.2 In Panel 3, place jumper between terminals II(wire D6-WCSI P) & 14 (wire D6-WCS16) on terminal strip VP3-L to energize HTWTSIEI (NE-116757 Sh.23 &
NF-156981 Sh.5).
- 7.5.3 Verify Annunciator 60001-0303, HT CLG WTR TEMP HI-HI TRIP is LIT.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER: I 1 SP - 1 D6 DIESEL GENERATOR RELAY FUNCTIONAL TEST Page 13 of 24
- 7.5.4 Verify 86 D6 GEN LOCKOUT relay is NOT TRIPPED.
7.5.5 Remove Jumper between terminals 11 & 14 on terminal strip VP3-L to de-energize HTWTSIEI.
7.6 Verify the SIMR Relay blocks a trip of BKR 26-16 on a Reverse Current Signal.
7.6.1 CLOSE BKR 26-16 using Test Close pushbutton on breaker.
N 7.6.2 Verify Annunciator 60002-0203, GENERATOR REVERSE POWER BREAKER TRIP, is NOT LIT.
N 7.6.3 Place a jumper between terminals 12 & 13 on Relay 32 to simulate a Reverse Current (Back of relay located in Panel 5 NE-116757, Sh.27 & NF-156981, Sh.15).
- 7.6.4 Verify Annunciator 60002-0203, GENERATOR REVERSE POWER BREAKER TRIP, is LIT.
- 7.6.5 Verify BKR 26-1 6 is NOT TRIPPED.
7.6.6 Remove jumper between terminals 12 & 13 on Relay 32.
7.7 Clear the Simulated Emergency Start Signal 7.7.1 In Panel 4, remove jumper from terminal 18 of VP2-I to de-energize SIMR.
7.7.2 Remove jumper from terminal 16 of VP2-I.
7.7.3 Reset the EMERG START signal by placing CS-46958, D6 DSL GEN EMERG START & EMERG START RESET, in "EMERG START RESET at G2 Panel.
OPS 7.7.4 Verify EMERG START ACTUATED red light is NOT LIT on CS-46958 at G2 Panel.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES I NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST REV: 11 Page 14 of 24 7.8 Verify BKR 26-16 trips on Reverse Current.
7.8.1 Verify Annunciator 60002-0203, GENERATOR REVERSE POWER BREAKER TRIP, is NOT LIT.
7.8.2 Place a jumper between terminals 12 & 13 on Relay 32 to simulate a Reverse Current (Back of relay located in Panel 5 NE-116757, Sh.27 & NF-156981, Sh.15).
- 7.8.3 Verify Annunciator 60002-0203, GENERATOR REVERSE POWER BREAKER TRIP, is LIT.
7.8.4 Remove jumper between terminals 12 & 13 on Relay 32.
- 7.8.5 Verify BKR 26-16 is OPEN.
7.8.6 Place CS-46944, BUS 26 SOURCE FROM D6 DSL GEN, in "PULLOUT."
OPS 7.8.7 Place BKR 26-16 in "DISCONNECT1'the following:
A. OPEN DC knife switch for BKR 26-16.
B. Remove BKR 26-16 from the cubicle.
C. Remove Shutter Barrier from cubicle.
D. Place BKR 26-16 to locked in "DISCONNECT per C20.5-1.
E. Remove "Barrier Installed" tag from the BKR 26-16 racking mechanism.
7.8.8 If applicable, restore from the Temp Lift established in Step 7.2.
Temp Lift No.:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES
/ NUMBER: I D6 DIESEL GENERATOR RELAY FUNCTIONAL TEST Page 15 of 24 7.9 Return Bus 26 Load Sequencer to service as follows:
7.9.1 Remove Secure Tag hung by clearing Tag Section 2-D6 SP2306-SS SP 2306, D6 DIESEL GENERATOR RELAY FUNCTION TEST, for the SS." I OPS 7.9.2 Place CS-46931, BUS 26 VOLTAGE RESTORATION I SEL SW, IN "AUTO".
OPS 7.9.3 In the Bus 26 Load Sequencer Cabinet, place Bus 26 Load Sequencer switch SW8, in "NORM."
7.9.4 Verify Annunciator 47524-1004, BUS 26 SEQUENCER NOT IN SERVICE, is NOT LIT.
OPS 7.9.5 Notify the Shift Supervisor to exit T.S. LC0 3.3.4 CONDITION C or E, entered in Step 7.3.6.
Exited CONDITION C at:
time 7.9.6 Return the 480V loads per this SP to a status directed by the Shift Supervisor.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
1 1 SP -
D6 DIESEL GENERATOR RELAY FUNCTIONALTEST Page 16 of 24 7.10 Verify that the diesel locks out from the following conditions:
N 7.10.1 In Panel 3, momentarily place jumper between terminals 11 (wire D6-WCSIP) and 14 (wire D6-WCS16) on terminal strip VP3-L to energize HTWTSIEI (H.T. Cooling Water Temperature High-High) (NE-116757-23 and NF-156981-5).
7.10.2 Remove jumper between terminals 11 and 14 on terminal strip VP3-L to de-energize HTWTSIEI.
- 7.10.3 Check 86 D6 GEN LOCKOUT is TRIPPED.
7.10.4 Reset 86 D6 GEN LOCKOUT.
7.10.5 In Panel 3, momentarily place jumper between terminals 20 (wire D6-LOSI P) and 21 (wire D6-ELO19) on terminal strip VP3-J to energize LOTRlEl (Lube Oil Temp.
High-High) (NE-116757-21 and NF-156981-5).
7.10.6 Remove jumper between terminals 20 and 21 on terminal strip VP3-J to de-energize LOTRIEI.
7.10.7 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.8 Reset 86 D6 GEN LOCKOUT.
The following step will actuate Annunciator 60002-0402, NOTE: DIESEL GEN SEL SW IN MAIN."
7.10.9 Using Key Hook 204, place CS-60210, D6 ENG I/ENG 2 START SEL SW, in "ENGINE 1" to separate engine 1 and engine 2 pressure trips.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR
- RELAY FUNCTIONAL TEST Page 17 of 24 7.10.10 Simultaneously - apply
. . - pressure
. above setpoints to remove trip signals from the following Engine 1 devices.
Device Name Setpoint Number 6174 Lube Oil Pressure 1 LowIEl 43.5 6175 Lube Oil Pressure 2 LowIEl 43.5 6176 Lube Oil Pressure 3 LowIEl 43.5 6254 L.T. Cooling Water Pressure LowIEl 30.8 6202 H.T. Cooling Water Pressure LowIEl 30.8 The contacts of TEOSl act as permissive for various NOTE: pressure trips and various alarms.
7.10.11 In Panel 4, apply a jumper between terminal D of relay TEOSI (wire TEOS-1-D) and terminal 1 of VP2-J (wire D6-MP) to energize TEOSI (NE-116757-3 &
NF-156981-3).
I NOTE: The following steps test the Lube Oil Pressure "Low-Low" 213 logic.
7.10.12 Reduce pressure below setpoint to simulate Lube Oil Pressure 1 LowIEl (6174) which energizes LOPIIEI .
I&C 7.10.13 Reduce pressure below setpoint to simulate Lube Oil Pressure 2 LowIEl (6175) which energize LOP2IE1.
I&C 7.10.14 Verify with Control Room that ERCS point 2Y8038D indicates Lube Oil Pressure Low Low is in alarm.
7.1 0.1 5 Verify local Annunciator 60001-0105 is LIT.
7.10.16 Apply pressure above setpoint to Lube Oil Pressure 2 LowIEl (6175) to de-energize LOP2IE1.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
SP 2306 1
D6 DIESEL GENERATOR SP RELAY FUNCTIONAL TEST REV: 11 Page 18 of 24 7.10.17 Verify with Control Room that ERCS point 2Y8038D clears.
7.1 0.1 8 Verify local Annunciator 60001-0105 is NOT LIT.
7.10.19 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.20 Reset 86 D6 GEN LOCKOUT.
7.10.21 Reduce Dressure below set~ointto simulate Lube Oil pressure 3 LowIEl (6176) hhich energizes LOP3lE1.
I&C 7.1 0.22 Apply pressure above setpoint to Lube Oil Pressure 1 LowIEl (6174) to de-energize LOPIIEI .
I&C Verify 86 D6 GEN LOCKOUT is TRIPPED.
Reset 86 D6 GEN LOCKOUT.
Reduce pressure below setpoint to simulate Lube Oil Pressure 2 LowIEl (6175) which energizes LOP2IEl Apply pressure above setpoint to Lube Oil Pressure 2 LowIEl (6175) to de-energize LOPZIEI .
Apply pressure above setpoint to Lube Oil Pressure 3 LowIEl (6176) to de-energize LOP31E1.
Verify 86 D6 GEN LOCKOUT is TRIPPED.
Reset 86 D6 GEN LOCKOUT Reduce pressure below setpoint to simulate H.T. Cooling Water Pressure Low1 (6202) which energizes HTWRIEI.
Apply pressure above setpoint to H.T. Cooling Water Pressure Low (6202) to de-energize HTWRIEI.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES I NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST Page 19 of 24 7.10.32 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.33 Reset 86 D6 GEN LOCKOUT 7.10.34 Reduce pressure below setpoint to simulate L.T. Cooling Water Pressure Low (6254) which energizes LTWWEI.
7.10.35 Apply pressure above setpoint to L.T. Cooling Water Pressure Low (6254) to de-energize LTWWEI .
7.10.36 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.37 Reset 86 D6 GEN LOCKOUT.
7.10.38 In Panel 3, momentarily place jumper between terminals 10 (wire D6-EL01 1) and 11 (wire D6-EL013) on terminal strip VP3-J to energize CPWEI (Crankcase Pressure High) (NE-116757-21 & NF-156981-5).
7.10.39 Remove jumper from terminals 10 and IIon terminal strip VP3-J to de-energize CPWEI.
7.10.40 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.41 Remove equipment from Engine 1 pressure switches.
7.10.42 INDEPENDENTLY VERIFY the following Engine 1 pressure switches are returned to service. The pressure switches isolation valves SHALL be OPEN and the test tee cap installed.
A. 6174 Lube Oil Pressure 1 Low
- 6. 6175 Lube Oil Pressure 2 Low C. 6176 Lube Oil Pressure 3 Low D. 6254 L.T. Cooling Water Pressure Low E. 6202 H.T. Cooling Water Pressure Low
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP 2306 SP RELAY FUNCTIONAL TEST REV: 11 Page 20 of 24 7.10.43 I&C simultaneously simulate adequate pressure to remove trip signals from the following Engine 2 devices:
I&C Device # Name Setpoint 6674 Lube Oil Pressure 1 LowIE2 43.5 6675 Lube Oil Pressure 2 LowIE2 43.5 6676 Lube Oil Pressure 3 LowIE2 43.5 6754 L.T. Cooling Water Pressure LowIE2 30.8 6702 H.T. Cooling Water Pressure LowIE2 30.8 7.10.44 Place CS-60210, D6 ENGllENG2 START SEL SW, in "ENGINE 2" to separate engine 2 from engine 1 pressure trips.
7.10.45 Reset 86 D6 GEN LOCKOUT.
The following steps test the Lube Oil Pressure Low Low 213 NOTE: logic.
7.10.46 Reduce pressure below setpoint to simulate Lube Oil Pressure 1 LowIE2 (6674) which energizes LOPlIE2.
I&C 7.10.47 Reduce pressure below setpoint to simulate Lube Oil Pressure 2 LowIE2 (6675) which energizes LOP21E2.
I&C 7.10.48 Verify with Control Room that ERCS point 2Y8039D indicates Lube Oil Pressure Low Low is in alarm.
7.10.49 Verify local Annunciator 60003-0106 is LIT.
7.10.50 Apply pressure above setpoint to Lube Oil Pressure 2 LowIE2 (6675) to de-energize LOP2lE2.
I&C 7.10.51 Verify with Control Room that ERCS point 2Y8039D clears.
7.10.52 Verify local Annunciator 60003-0106 is NOT LIT
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
SP D6 DIESEL GENERATOR RELAY FUNCTIONAL TEST Page 21 of 24 7.10.53 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.54 Reset 86 D6 GEN LOCKOUT.
7.10.55 Reduce pressure below setpoint to simulate Lube Oil Pressure 3 LowIE2 (6676) which energizes LOP3lE2.
I&C 7.10.56 Apply pressure above setpoint to Lube Oil Pressure 1 LowIE2 (6674) to de-energize LOPIIE2.
I&C 7.10.57 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.58 Reset 86 D6 GEN LOCKOUT.
7.10.59 Reduce pressure below setpoint to simulate Lube Oil Pressure 2 LowIE2 (6675) which energizes LOP2lE2.
I&C 7.10.60 Apply pressure above setpoint to Lube Oil Pressure 2 LowIE2 (6675) to de-energize LOP21E2.
I&C 7.10.61 Apply pressure above setpoint to Lube Oil Pressure 3 LowIE2 (6676) to de-energize LOP3lE2.
I&C 7.10.62 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.63 Reset 86 D6 GEN LOCKOUT.
7.10.64 Reduce pressure below setpoint to simulate H.T. Cooling Water Pressure LowIE2 (6702) which energizes HTWWE2.
I&C 7.10.65 Apply pressure above setpoint to H.T. Cooling Water Pressure LowIE2 (6702) to de-energize HTWWE2.
I&C 7.10.66 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.67 Reset 86 D6 GEN LOCKOUT.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR SP RELAY FUNCTIONAL TEST Page 22 of 24 7.10.68 Reduce pressure below setpoint to simulate L.T. Cooling Water pressure Low (6754) which energize LTWWEZ.
I&C 7.10.69 Apply pressure above setpoint to L.T. Cooling Water Pressure Low (6754) to de-energize LTWWEZ.
I&C 7.10.70 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.71 Reset 86 D6 GEN LOCKOUT.
7.10.72 In Panel 3, momentarily place jumper between terminals 10 (wire D6-EL021) and 11 (wire D6-EL023) on terminal strip VP3-K to energize CPWEZ (Crankcase pressure High) (NE-I 16757-22 & NF-156981-5).
7.10.73 Remove jumper from terminals 10 and 11 on terminal strip VP3-K to de-energize CPWEZ.
7.10.74 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.75 Reset 86 D6 GEN LOCKOUT.
7.10.76 In Panel 4, remove jumper from between terminal D of TEOSI and terminal 1 of VPZ-J to de-energize TEOSI.
7.10.77 Remove equipment from Engine 2 pressure switches.
I&C 7.10.78 INDEPENDENTLY VERIFY the following Engine 2 pressure switches are returned to service. The pressure switches isolation valves SHALL be OPEN and the test tee cap installed.
A. 6674 Lube Oil Pressure 1 Low I&C B. 6675 Lube Oil Pressure 2 Low C. 6676 Lube Oil Pressure 3 Low I&C
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES 1 NUMBER: 1 D6 DIESEL GENERATOR SP 2306 RELAY FUNCTIONAL TEST Pane 23 of 24 D. 6654 L.T. Cooling Water Pressure Low E. 6602 H.T. Cooling Water Pressure Low 7.10.79 Place CS-60210, D6 ENGllENG2 START SEL SW, in "ENGINEllENGINE2."
7.10.80 Reset 86 D6 GEN LOCKOUT or NA if not required.
7.10.81 In Panel 3, momentarily place jumper between terminals 19 (wire D6-WCS2P) and 20 (wire D6-WCS26) on terminal strip VP3-L to energize HTWTSIE2 (H.T. Cooling Water Temperature High-High) (NE-116757-24 &
NF-156981-5).
7.10.82 Remove jumper from terminals 19 and 20 on terminal strip VP3-L to de-energize HTWTSIEZ.
7.10.83 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.84 Reset 86 D6 GEN LOCKOUT.
7.10.85 In Panel 3, momentarily place jumper between terminals 20 (wire D6-LOS2P) and 21 (wire D6-EL029) on terminal strip VP3-K to energize LOTRIE2 (Lube Oil High-High)
(NE-116757-22 & NF-156981-5).
7.10.86 Remove jumper from terminals 20 and 21 on terminal strip VP3-K to de-energize LOTRIEZ.
7.10.87 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.88 Reset 86 D6 GEN LOCKOUT.
7.10.89 In Panel 4, momentarily place jumper between terminals 24 (wire D6-GP) and 25 (wire D6-GBTI) of terminal strip VP3-A to energize GBTIR (Engine 1 Generator Bearing Temp) (NE-I 16757-30 & NF-I 56981-4).
7.10.90 Remove jumper from terminals 24 and 25 of terminal strip VP3-A to de-energize GBTI R.
7.10.91 Verify 86 D6 GEN LOCKOUT is TRIPPED.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURES NUMBER:
D6 DIESEL GENERATOR RELAY FUNCTIONAL TEST I REV: 11 1 Page 24 of 24 7.10.92 Reset 86 D6 GEN LOCKOUT.
7.10.93 In Panel 4, momentarily place jumper between terminals 24 (wire D6-GP) and 26 (wire D6-GBT2) of terminal strip VP3-A to energize GBT2R (Engine 2 Generator Bearing Temp).
7.10.94 Remove jumper from terminals 24 and 26 of terminal strip VP3-A to de-energize GBTZR.
7.10.95 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.96 Reset 86 D6 GEN LOCKOUT.
7.10.97 In Panel 5, momentarily place a jumper between terminals 3 and 7 of RDDX-1, D5 DSL GEN GOVERNOR PACK DIFFERENTIAL AUX RELAY.
7.10.98 Remove jumper from terminals 3 and 7 of RDDX-1.
7.10.99 Verify 86 D6 GEN LOCKOUT is TRIPPED.
7.10.100 Reset 86 D6 GEN LOCKOUT.
7.11 Reterminate lead lifted in Step 7.4.4, on contact terminal 10 (wire SFR-10) on Relay SFR.
7.12 Perform FME checks in all cabinets entered during performance of this SP per 5AWI 8.7.0.
7.13 Return D6 to operable status.
8.0 ADDITIONAL REQUIREMENTS NONE 9.0 ATTACHMENTS NONE
Attachment 3 NF-40325-1, Interlock Logic Diagram Diesel Generator System Unit 1 & 2 1 page follows
P- I ADDED ANN. ADD-D I DIESEL GLN ERATOK
-. _CoWTRC2L LOGIC
- SEQ. OF EVENTS-POINT NO.
FOR CONSTRUCTION D I DIESEL w. --
CLEAN F. 0. RETURN PEE- LUBL OIL m!YP eUMP mTOR*lllK-40
Attachment 4 NF-118850, D5lD6 System Logics Shutdown Due to Faults 1 page follows
REVISIONS A4-0 INCORPORATED ECR 89Y974-597 AND NSP COMMENTS PER ESU-2930 & ESU-3064 SHUTDOWN DUE TO FAULTS ISSUED FOR CONSTRUCTION.
( REF. TABLE 1 ) FILMED: 12-4-92 A AS BUILT-INCORPORATE DRAWING INTO NSP DRAWING SYSTEM PER NDR PI-935 DWN: WHS 8-18-93 NF-118851 CHKD: GPD 8-19-93 MOD: 89Y974 NE-116756-27 DIESEL ENGINE DIESEL ENGINE DIESEL ENGINE NF-116770-1 FILMED: 9-10-93 SELECTOR SW SELECTOR SW SELECTOR SW REVERSE POWER NF-118855 NF-118853 NF-116770-1 NF-116770-1 B ENGINE 1&2 NF-118848 NF-118848 NF-118848 START SIGNAL NF-116770-1 NF-116770-1 NF-118853 NF-118858 NF-118854 PUSHBUTTON REMOVED ENGINE 1 & 2 EMERGENCY FIELD FLASH ENGINE 2 ACTIVATED START SIGNAL ENGINE 1 LUBE OIL SUMP LEVEL LOW WATER PRESS WATER PRESS WATER PRESS WATER PRESS OVERVOLTAGE OVERCURRENT OVERCURRENT DIFFERENTIAL GENERATOR GENERATOR GEN BEARING GEN BEARING "B"
LT COOLING LT COOLING HT COOLING WATER TEMP HT COOLING WATER TEMP HT COOLING HT COOLING EXCITATION GENERATOR TIME DELAY GENERATOR RESTRAINED OVERSPEED GENERATOR PROTECTION TRIP CONTACT TO LOCAL ENGINE 2 ENGINE 2 LOSS OF ENG 1 SIDE TEMP HIGH ENG 2 SIDE TEMP HIGH EMERGENCY RUNNING ENGINE 1 HIGH-HIGH HIGH-HIGH ENGINE 1 ELEC GOV ALARM. ISSUED FOR CONST SIGNAL ENGINE 2 END OF ENGINE 1 DIESEL STOP LOW LOW VOLTAGE FAILURE ENGINE
[59]
[32X] [87]
[51] [51V]
2CS 2CS-50210 SI 50066 DWN: LAB 3-27-96 CHKD: WF 3-27-96 MOD.: 96D501 REVD:
APPD & CERT:
NF-118846 NF-118846 G. SUNDBERG 3-27-96 PE# 11840 TEMP HI-HI ENGINE 2 TEMP HI-HI 2/3 LOGIC OIL PRESS 2/3 LOGIC OIL PRESS ENGINE 2 CRANKCASE PRESSURE CRANKCASE PRESSURE AS BUILT-ENGINE 1 LUBE OIL LUBE OIL ENGINE 2 LOW-LOW ENGINE 1 LOW-LOW ENGINE 1 INCORPORATED A/ES REV. B PER TEOS1 DRR PI-97-67 HIGH HIGH (2-30 SEC) CERTIFIED REV. B SET @ TRANSFERRED TO 10 SEC RECORD TRACING DWN: BMS 6-12-97 CHKD: PAS 6-24-97 MOD#: 96D501 FILMED 7-97 AN NF-118862 A MCR ALARM 50002
-0303 AN A
AN AN 50002 NF-118862 A
-0201 A NF-118862 50002 NF-118862 MCR ALARM
-0302 50002 MCR ALARM MCR ALARM
-0203 AN NF-120101 NF-118862 A MONITORING SYSTEM MCR ALARM 50002
-0204 NF-120101 MONITORING SYSTEM AN A NF-118862 NF-120101 50002-0202 MCR ALARM MONITORING SYSTEM NF-118849 SET MAIN BREAKER TRIP SIGNAL LOCKOUT RELAY
[86]
TRIP SIGNAL AN NF-118857 NF-118857 NF-118849 A NF-118862 MCR SI READY LOGIC SHUTDOWN LOGIC DG MAIN BKR LOGIC 50002-0106 MCR ALARM TABLE 1: SHUTDOWN DUE TO FAULTS EMERGENCY ENGINE SENSOR GENERATOR GENERATOR GENERATOR ALARM RTU INPUT DSL ENGINE STOP INTERLOCK PROT. DEVICE REVRS PWR SET REFERENCES REFERENCE SEL SW PUSHBUTTON REFERENCE REFERENCE REFERENCE D5 2CS-50066 NF-118862 NF-116770-1 NF-120101 CS-50210 NE-116756-27 NF-118846 NF-118848 D6 2CS-60066 NF-118864 NF-116770-2 NF-118843 CS-60210 NE-116757-27 TABLE 2: SHUTDOWN DUE TO FAULTS ALARMS NOTES:
118850 GENERATOR GEN. VOLTAGE GEN.
GENERATOR GEN. DIFF. GEN. REVERSE LOSS OF LOCKOUT OVER RESTRAINED OVERCURRENT SET PROTECTION POWER EXCITATION RELAY VOLTAGE OVERCURRENT 1. LOGIC IS SHOWN FOR D5 ONLY AND IS TYPICAL FOR D6.
D5 50002-0201 50002-0202 50002-0203 50002-0204 50002-0302 50002-0303 50002-0106 2. ALL SYSTEMS AND THEIR COMPONENTS ARE NUCLEAR SAFETY RELATED (QAI) UNLESS SPECIFIED NON-SAFETY RELATED ON THE FLOW DIAGRAM.
D6 60002-0201 60002-0202 60002-0203 60002-0204 60002-0302 60002-0303 60002-0106 NF Designed By FLUOR DANIEL PROJ. NO. 834473 ACT. NO. 000379 Chicago, Illinois 6O6O6 DWN. R.S. DATE 11,30,92 SIGNIFICANT NUMBER 8630 410 2 3600 1 3000 CHECKED A.G. 12-1-92 GROUP 1 2 3 4 5 CL 6 REVIEWED A.G. 12-2-92 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT 1 & 2 - RED WING, MINNESOTA PROJ. NO. E89Y974 APPD & CERT.
I hereby certify that this plan, specification or report was prepared by me or under my direct G.A.OLSON PE#21014 D5/D6 SYSTEM LOGICS 12-2-92 supervision and that I Professional am a duly Registered Engineer under the laws of the FILMED SHUTDOWN DUE TO FAULTS State of Minnesota.
NORTHERN STATES POWER COMPANY SCALE NONE REV. B G.A.OLSON ENGINEERING DEPARTMENT Date 12-2-92 Reg. No. 21014 MINNEAPOLIS NF 118850 118850.DGN NSP GENERATION CAD
Attachment 5 NF-118858, D5lD6 System Logics EmergencyIFailure Start 1 page follows
REVISIONS A4-0 INCORPORATED ECR 89Y974-597 AND NSP COMMENTS PER ESU-2930 & ESU-3064 ISSUED FOR CONSTRUCTION.
FILMED: 12-4-92 A AS BUILT-INCORPORATE DRAWING INTO NSP DRAWING SYSTEM PER NDR PI-935 DWN: WHS 7-13-93 CHKD: GPD 8-19-93 AUTOMATIC OR MANUAL EMERGENCY START STARTING FAILURE SIGNAL/EMERGENCY START SIGNALS MOD: 89Y974 FILMED: 9-10-93 NOTE 3 EMER START/RESET EMER START/RESET AUTO START RESET CS VERTICAL PANEL CS VERTICAL PANEL START FAIL RESET NF-118856 NF-118851 NF-118847 NF-118856 DIESEL ENGINE VOLT REG CONT PB BENCH BOARD PB BENCH BOARD GEN CONTROL MODE SEL SW SELECTOR SW MODE SEL SW AUTO MNTND REMOTE MNTND NF-116497 EMER START EMER START LOCAL MNTND MODE SEL SW MODE SEL SW ENGINE 1&2 CS CRM CS CRM NF-159023 GEN CONTROL GEN CONTROL NF-118857 NF-116497 NF-118856 NF-118855 EMERGENCY SIGNAL (SDR) EMERGENCY UNDERVOLT EMER START MAINTENANCE START SIGNAL NORMAL SHUTDOWN START OR TEST REMOTE START LOCAL (SPSR) END OF DIESEL RUNNING (EOSR)
PERMISSIVE 2CS 2CS 2CS 2CS 2CS 2CS-50208 2CS-50210 2CS-50215 SI 50067 50070 2CS-50068 46957 50217 46957 NF-118857 MCR SI READY STATUS R (NOT MECHANICAL NF-118856 LATCHING)
SI EMER START (SIMR)
ALARM AN AN NF-118862 50002 A
A -0102 MCR ALARM 50002 NF-118862
-0101 (2-30 SEC)
SET 5 SEC (ESRX) NF-118857 NF-118850 NF-116497 MCR SI READY FAULT LOAD SEQUENCER STATUS SHUTDOWN LOGIC R (NOT MECHANICAL LATCHING)
STARTING FAILURE SIGNAL (SFR)
R AN R
50002 A
-0104 IL 46957-01 EMERGENCY NF-118856 NF-118862 FAST START SIGNAL (ESR-A, B, C) MAINTENANCE/TEST SEE TABLE 2 START LOGIC TABLE 1: STARTING FAILURE & EMERGENCY START/AUTOMATIC OR MANUAL EMERGENCY START TABLE 2 EMERGENCY PUSHBUTTONS ALARMS GENERATOR START/FAIL VOLT REG LOAD GENERATOR DSL ENGINE GEN CONT MCR ALARM CONTROL RESET CONT MODE INDICATING SI EMEG. UNDER VOLT STARTING SEQUENCER LOGIC DRAWING SET SEL SW MODE SEL SW START RESET REFERENCES TITLE/DESCRIPTION MODE SEL SW PUSHBUTTON SEL SW LIGHT START EMERG. START FAILURE REFERENCES REFERENCES NF-118845 FUEL OIL SYSTEM D5 2CS-50208 2CS-50067 2CS-50215 2CS-50210 2CS-50068 2CS-50070 2CS-46957 2CS-46957 46957-01 50002-0101 50002-0102 50002-0104 NF-118862 NF-116497 NF-118846 PRELUBE SYSTEM NF-118847 VOLTAGE REGULATOR D6 2CS-60208 2CS-60067 2CS-60215 2CS-60210 2CS-60068 2CS-60070 2CS-46958 2CS-46958 46958-01 60002-0101 60002-0102 60002-0104 NF-118864 NF-159023 NF-118861 CLG FAN SYSTEM LOGIC NF-118851 AIR START VALVES NF-118854 SPEED GOVERNOR NF-118855 SLOW START LOGIC NF-118856 MAINTENANCE/TEST START LOGIC NF-118857 SHUTDOWN SEQUENCE LOGIC NF-120101 MONITORING SYSTEM COUNTERS 118858 NOTES:
- 1. LOGIC IS SHOWN FOR D5 ONLY AND IS TYPICAL FOR D6.
- 2. ALL SYSTEMS AND THEIR COMPONENTS ARE NUCLEAR SAFETY RELATED (QAI) UNLESS SPECIFIED NF NON-SAFETY RELATED ON THE FLOW DIAGRAM.
- 3. APPENDIX-R ISOLATION SWITCH IS APPLICABLE ONLT TO D5.
Designed By FLUOR DANIEL PROJ. NO. 834473 ACT. NO. 000379 Chicago, Illinois 6O6O6 DWN. R.S. DATE 11,30,92 SIGNIFICANT NUMBER 8630 410 2 1 2140 3600 CHECKED A.G. 12-1-92 GROUP 1 2 3 4 5 CL 6 REVIEWED A.G. 12-2-92 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT 1 & 2 - RED WING, MINNESOTA PROJ. NO. E89Y974 APPD & CERT.
I hereby certify that this plan, specification or report was prepared by me or under my direct G.A.OLSON PE#21014 D5/D6 SYSTEM LOGICS 12-2-92 supervision and that I Professional am a duly Registered Engineer under the laws of the FILMED EMERGENCY/FAILURE START State of Minnesota.
NORTHERN STATES POWER COMPANY SCALE NONE REV. A G.A.OLSON ENGINEERING DEPARTMENT Date 12-2-92 Reg. No. 21014 MINNEAPOLIS NF 118858