ML20205S729

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Rev 4 to Emergency Operating Procedure EOP-01-SRP-AEP, Auxiliary Electrical Power Sys Recovery
ML20205S729
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/08/1988
From: Bishop E
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20205K904 List: ... further results
References
EOP-01-SRP-AEP, EOP-1-SRP-AEP, NUDOCS 8811110152
Download: ML20205S729 (6)
v • d • e


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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIY 0 AUXILIARY ELECTRICAL POWER Sa* TEM RECOVERY IMERGENCY OPERATING PROCEDURE: E0P-01-SRP-AEP VOLUME VI Rev. 004 y k ,

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Approved By: ~

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Cejieral Manas r/

Manager-Opera)tions Page 1 of 6 U

8911110152 801025 PDR AD0;K 050g4 P

LIST OF EFFECTIVE PAGES E0P-01-SRP-AEP Page(s) Revision 1-2 4 3 2 4-5 3 6 4 BSEP/Vol. VI/EOP-01-SRP-AEP Page 2 of 6 Rev. 4

A. TITLE - Auxiliary Electrical Power System Recovery  !

l B. ENTRY CONDITION Auxiliary electrical power is E available to either 4 kV E buses from -

the SAT.

C. OPERATOR ACTIONS i 1

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1. VERIFY or MANUALLY START and TIE diesel generators to deenergized l 4 kV E buses (OP-50.1), i
2. VERIFY the "LOADED" light illuminated for any diesel that is

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carrying an E bus. This indicates proper frequency and voltage.

3. VERIFY proper diesel generator opetition locally (OP-39, I Section 5.2).

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4 IF the SAT was lost due to a loss of power on the CP&L system. THEN OPEN all transmission line PCBs and PLACE their automatic reclosures l -

in "0FF." '

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5. ESTABLISH communication with the system load dispatcher. ,
6. REMOVE control power fuses from circulating water intake pump 4 kV  ;

breakers. '

7. DEENERCIZE the Caswell Beach pumping station (OP-50).

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8. IF neither 4 kV E bus is energized. THEN CONTINUE in Section 1 on 4

page of this procedure.

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9. WHEN a transulssion line becomes available. THEN ENERCIZE the 230 kV i switchyard and the Plant Electrical System pe OP-50.
10. START any of the following systems that are NOT operating as load j permits (OP-50.1).

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a. Nuclear Service Water System l
b. RBCCW System i i
c. Dryvell Coolers I
d. 125 and 24 Vdc Battery Chargers
e. Reactor Building Ventilation System
f. Instrument / Service Air System
g. Control Building Ventilation System l
h. CRD Pumps I l

BSEP/Vol. VI/EOP-01-SRP-AEP Page 3 of 6 Rev. 2 l r

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Section 1 - Both 4 kV E beses are deenergized.

NOTE A list ef critical instrumentation available with a total loss of ac power is provided on page 6 of dits procedure.

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1. CHECK RTGB and local annunciators for diesel generators to determine cause of the malfunction.

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2. CHECK diesel generator output breakers for electrical protection devices and control power fuses.

CAUTION IF a LOCA signal is present, PREVENT injection from those systems NOT required to assure adequate core cooling when energizing E buses,

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3. WHEN diesel generators become available to deenergized buses THEN PLACE those diesels in service per OP-39.

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~~ WHEN a transmission line becomes available. THEN ENERGIZE the 230 kV switchyard and the Plant Electrical System per OP-50.

5. VMEN either E bus in energized THEN RETURN to Step C on page 3 of this procedure.

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6. WHEN RFPs, reactor recirculation MG sets and the main turbine have stopped rotating, THEN SECURE their respective de lubricating oil pumps, 7 VENT the generator easing as follovst
a. PLACE the Flow Directional Valve, G-01, to the "HYDROGEN" position.
b. OPEN the Hydrogen Purge Valve, C-03.
8. VHEN the generator gas pressure decreases to O psig, THEN PLACE the
  • EMERGENCY SEAL OIL PUMP control switch to "0TF."
9. MONITOR noninterruptible instrument air pressure locally as indicated by Pressure Gauge RNA-PI-3785 or RNA-PI-3786 at the Reactor Building's standby air compressors, i l __
10. It is desirable to cemmence a reactor cooldown at normal cooldown  !

I rates, as soon as possible, following a total loss of ac power to 1 l limit dryvell temperature increase.

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i BSEP/Vol. VI/EOP-01-SRP-AEP Page 4 of 6 Rev. 3 l I l

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NOTE A prolonged total loss of ac power could lead to an isolation of HPCI and RCIC on high steam line temperature. Since HPCI, RCIC, and the diesel fire pump are the only sources of injection available without ac power, the steam line temperature isolation may be bypassed.

CAUTION DO NOT BYPASS the HPCI or RCIC steam line temperature isolation L'NTIL steam line integrity has been verified.

11. BYPASS HPCI and/or RCIC stean line temperature isolations as follows:
a. To bypass HPCI stean line temperature isolation

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(1) On Panel P-6!4, PLACE the HPCI LOGIC A test switch to "TEST."

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(2) On Panel P-614 PLACE the HPCI LOGIC B test switch to "TEST."

b. To bypass RCIC steam tunrel temperature isolattent

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(1) On Panel P-614, PLACE the RCIC 10CIC A test switch to "TEST."

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(2) On Panel P-614, PLACF the RCIC LOGIC B test switch to "TEST."

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c. IF indications of a stean line break occur. THEN ISOLATE HPCI and RCIC.

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d. VMEN ac power is restored AND the HPCI and RCIC steam line temperature isolations are clear, THEN PLACE the following test i switches to "NORMAL."

l Ind. Ver.

/ (1) HPCI LOGIC A

/ (2) HPCI LOGIC B l / (3) RCIC LOGIC A l

/ (4) RCIC LOGIC B l

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BSEP/Vol. VI/EOP-01-SRP-AEP ' S of /, Rev. 3 l l

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INSTRUMENTATION AVAILABLE WITH TOTAL LOSS OF AC POWER Parameter Ins t rume :lt, Location Reactor Level C32-LI-R606A, B, C RTGB-P603 B21-LI-R610 RiGB-P601 Reactor Pressure C32-R605 RTGB-P603 C32-R608 RTGB-P603 Control Rod Position Pull Core Matrix and RTGB-P603 Process Computer I

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i BSEP/Vol. VI/EOP-01-SRP-AEP Page 6 of 6 Rev. 4 l t

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