Text

Initial Exam 2012-302 Final SRO Written Exam
	ML13018A352
Person / Time
Site:	Oconee
Issue date:	01/15/2013
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
References
	ES-401
	Download: ML13018A352 (60)
	v • d • e

ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet US. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: 12/13/2012 Facility/Unit: Oconee Region:

I E ii iii E IV E Reactor Type: WE CE E BW GEE Start Time:

Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own.

I have neither given nor received aid.

Applicants Signature Results RO/SRO-Only/Total Examination Values 75

/

25

/ 100 Points Applicants Scores

/

Points Applicants Grade

/

Percent

Oconee Nuclear Station ILT42 ONS SRO NRC Examination Question:

76 (1 point)

Given the following Unit 1 conditions:

Time = 0400 Reactor power = 100%

1 HP-410 closed with breaker tagged open for maintenance Time = 0405 Transient occurs 1 RC-67 opens 1 SA-1 8/A-i (Pressurizer Relief Valve Flow) actuated Time = 0425 SCM=0°F 1HP-26 failed closed LOSCM tab in progress 300 gpm EFDW flow established to each SG

1) As directed by the LOSCM Tab, BOTH SG5 will be (1).

2) The next action directed by the LOSCM tab will be to (2)

Which ONE of the following completes the statements above?

A.

1. fully depressurized

2. increase EFDW flow to maximum allowable rate per Rule 7 (SG Feed Control)

B.

1. fully depressurized

2. throttle EFDW flow to maintain RCS cooldown rates within limits C.

1. depressurized to not less than 250 psig

2. increase EFDW flow to maximum allowable rate per Rule 7 (SG Feed Control)

D.

1. depressurized to not less than 250 psig

2. throttle EFDW flow to maintain RCS cooldown rates within limits Page 76 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

77 (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 75%

AP!20 (Loss of Component Cooling) in progress Current conditions:

1A1 RCP Radial Bearing Temperature = 248°F stable In accordance with AP/20:

1) The 1A1 RCP _(1)_ required to be secured.

2)

If the RCP is required to be secured the reactor (2) be tripped first.

Which ONE of the following completes the statements above?

A.

1.is

2. will B.

1.15

2. will NOT C.

1. is NOT

2. will D.

1. is NOT

2. will NOT Page 77 of 100

Oconee Nuclear Station ILT42 ONS SRO NRC Examination Question:

78 (1 point)

Given the following Unit 2 conditions:

Refueling in progress FTC level = 22 feet stable No water additions are being made to the system 2A LPI train is operable and in service Current conditions:

Refueling SRO desires stopping the 2A LPI Pump to aid in inserting a fuel assembly 2A LPI pump has been in continuous operation for the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Which ONE of the following describes whether the 2A LPI pump may be stopped in accordance with OP!2/Al 502/007 (Operations Defueling /Refueling Responsibilities) and the bases for this action?

A.

2A LPI Pump may be stopped FTC provides adequate backup decay heat removal B.

2A LPI Pump may be stopped Spent Fuel Cooling system provides adequate backup decay heat removal C.

2A LPI Pump may NOT be stopped FTC does NOT provide adequate backup decay heat removal.

D.

2A LPI Pump may NOT be stopped Spent Fuel Cooling does NOT provide adequate backup decay heat removal Page 78 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

79 (1 point)

Given the following Unit 1 conditions:

Time = 0400 Reactor power = 100%

2SA-i 8/A-i 1 (Turbine BSMT Water Emergency High Level) actuates Time = 0402 BOTH Main FDW Pumps trip Time = 0407 Both SGs level = 30 inches XSUR stable In accordance with the TBF tab:

1) EFDWflowwill be (1)

2) Subsequently if, ALL EFDW is lost (2)

Which ONE of the following completes the statements above?

A.

1. adjusted to increase BOTH SG5 to 95% O.R.

2. HPI Forced Cooling will be initiated B.

1. adjusted to increase BOTH SG5 to 95% O.R.

2. SSF-ASW flow will be established to BOTH SGs C.

1. controlled in accordance with the guidance in Rule 7 (SG Feed Control),

Table 4 (SG Level Control Points)

2. HPI Forced Cooling will be initiated D.

1. controlled in accordance with the guidance in Rule 7 (SG Feed Control),

Table 4 (SG Level Control Points)

2. SSF-ASW flow will be established to BOTH SGs Page 79 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

80 (1 point)

Given the following Unit 1 conditions:

Time = 0400 Reactor power = 100%

TDEFDW pump OOS Time = 0445 Station blackout Reactor trip Control Rod Group 2 Rod 3 position = 90% withdrawn AP/25 (SSF EOP) initiated Time = 0550 1TC, 1TD, and 1 TE de-energized Standby Buses energized from CT-5 Feed to the SGs is established Time = 0600 CETCs = 545°F slowly decreasing

1) At 0550, the Blackout tab will direct using (1) to feed the SGs.

2) At 0600, the Blackout tab and its basis (2) allow cooling down to 450°F.

Which ONE of the following completes the statements above?

A.

1. SSFASW

2. will NOT B.

1. SSFASW

2. will C.

1. StationASW

2. will NOT D.

1. StationASW

2. will Page 80 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

81 (1 point)

In accordance with the Site Emergency Plan, which ONE of the following would require notifying the State and Counties of plant status?

A.

An RCS leak of4gpm B.

SG tube leakage of 19 gpm C.

An instrument failure results in ES Channels 1 2 actuation D.

A loss of heat transfer requires feeding the SG with the SSF ASW pump Page 81 of 100

Oconee Nuclear Station ILT42 ONS SRO NRC Examination Question:

82 (1 point)

Given the following Unit 1 conditions:

Initial Conditions:

Reactor power = 85% slowly increasing DeltaTcin HAND Current conditions:

ICS runback in progress Reactor power as indicated below ir 848 831 756 864 A

A A

A 125 460 125

+60 125 125

+60 100

+40 100

+40 103

÷40 100 +40 80

+20 80

+20 B)

+20 60 0

60 0

0 40 20 40 20 40 20 40 20 20 40 20 40 20 40 20 40 0

-60

60 0

6) 0 60 V

V V

V 000 000 000 000

% MB MB 1MB MB Which ONE of the following describes:

1) the reason for the ICS runback?

2) the consequences of operating the unit under the conditions described above?

A.

1. Dropped Control Rod

2. Allowable Thermal Power limits of Tech Spec 3.4.4 (RCS Loops MODES 1 and 2) could be exceeded B.

1. Dropped Control Rod

2. Maximum Linear Heat Rate could be exceeded C.

1. RCP trip

2. Allowable Thermal Power limits of Tech Spec 3.4.4 (RCS Loops MODES 1 and 2) could be exceeded D.

1. RCP trip

2. Minimum DNBR limits could be exceeded Page 82 of 100 POWER RANGE NIS

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

83 (1 point)

Given the following Unit 1 conditions:

Time = 0400 Reactor power = 70% decreasing Unit shut down in progress due to a 140 gpm RCS leak Time = 0420 CoreSCM=0°F RCS temperature = 550°F decreasing Reactor building pressure = 6 psig increasing 1RIA-58 = 15R!hr increasing Time = 0445 Reactor building pressure = 18 psig increasing Tremor felt in the control room Seismic trigger actuates Time = 0450 Reactor building pressure = 4 psig decreasing 1 RIA-58 = 55RIhr decreasing Little River Dam has failed

1) The Emergency Classification at 0420 is (1)

2) The Emergency Classification at 0450 is (2)

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A.

1. Alert

2. Site Area Emergency B.

1. Alert

2. General Emergency C.

1. Site Area Emergency

2. Site Area Emergency D.

1. Site Area Emergency

2. General Emergency Page 83 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

84 (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Time= 0400 Reactor power = 100%

1BHPIOOS Current conditions:

Time=0410 ES Channels 1 8 actuated CoreSCM=0°F EOP Enclosure 5.1 (ES Actuation) in progress Seal Inlet HDR Flow 25 gpm HPI Flow Train A flow = 456 gpm HPI Flow Train B flow = 482 gpm 1)

(1) exceeding the HPI pumps flow limits in accordance with Rule 6 (HPI Pump Throttling Limits).

2) The MINIMUM number of HPI trains required to mitigate this event is (2)

Which ONE of the following completes the statements above?

A.

1. BOTH HPI headers are

2. two B.

1. BOTH HPI headers are

2. one C.

1. ONLY the 1 B HPI header is

2. two D.

1. ONLY the 1BHPI headeris

2. one Page 84 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

85 (1 point)

Given the following Unit 1 conditions:

Time = 0400 Reactor has been tripped due to SGTR in the 1 A SG Time = 0430 Feedwater to the 1A SG is isolated 1A SG level = 273 inches XSUR increasing Time = 0500 1A SG level = 293 inches XSUR increasing Time = 0530 1A SG reaches the Water in Steam Line Level In accordance with the SGTR tab:

1) At 0500, EOP Enclosure 5.22 (SG Blowdown)

(1)_be used to reduce 1A SG level.

2) At 0530, (2) steaming the 1A SG.

Which ONE of the following completes the statements above?

A.

1. will NOT

2. continue B.

1. will NOT

2. stop C.

twill

2. continue D.

1. will

2. stop Page 85 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

86 (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 85%

Control rod group 7 = 93% withdrawn Makeup to LDST in progress Current conditions:

Reactor power = 85%

Control rod group 7 = 30% withdrawn 1)

In accordance with the bases of TS 3.2.1 (Regulating Rod Position Limits) continued operation in the current plant configuration is NOT allowed because (1) 2)

Restoring rods to within the acceptable region by (2) will satisfy the requirements of TS 3.2.1.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A.

1. SDM is not adequate and ejected rod worth is too high

2. boration ONLY B.

1. SDM is not adequate and ejected rod worth is too high

2. boration OR reducing reactor power C.

1. this configuration is in violation of the assumptions made in the safety analysis

2. boration ONLY D.

1. this configuration is in violation of the assumptions made in the safety analysis

2. boration OR reducing reactor power Page 86 of 100

Oconee Nuclear Station Question:

87 (1 point) 1LT42 ONS SRO NRC Examination Given the following Unit 1 conditions:

ci)>

ci)

-J BWST Level 1500

1) Referring to the chart of control room indicated BWST level above, the latest time that adequate NPSH for the LPI and RBS pumps after suction is swapped to the RBES is ensured is (1)

2) The minimum BWST level in accordance with the basis of TS 35.4 (2) also ensure the solution in the RB Emergency sump following a LOCA is within a specified pH range.

Which ONE of the following completes the statements above?

A.

1. 1300

2. will NOT B.

1. 1300

2. will C.

1. 1400

2. will NOT D.

1. 1400

2. will 1200 1300 1400 Time Page 87 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

88 (1 point)

Given the following Unit 1 conditions:

Reactor power = 100%

1 FDW-368 is discovered closed and will NOT open 1)

In accordance with TS 3.7.5 (Emergency Feedwater) basis the (1) is inoperable.

2)

If 1 FDW-368 remains inoperable, entering MODE 4 (2) required.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A.

1. TDEFDW pump

2. is B.

1. TDEFDW pump

2. is NOT C.

1. associated EFW flow path

2. is D.

1. associated EFW flow path

2. is NOT Page 88 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

89 (1 point)

Which ONE of the following sets of 125 VDC Vital I&C power panelboards are required for Unit 2 in accordance with TS 3.8.8 (Distribution Systems Operating) and why?

A.

lDIAandlDlB They provide power to SK and SL breakers B.

1DIAand1DIB They provide power to the Switchyard Isolation circuitry C.

lDlCandlDID They provide power to SK and SL breakers D.

1DICand1DID They provide power to the Switchyard Isolation circuitry Page 89 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

90 (1 point)

Given the following Unit 2 conditions:

Reactor power = 100%

1) The IA pressure setpoint which will cause the Diesel Air Compressors to automatically start is (1) psig.

2) The bases for 2AP/22 (Loss of IA) ensuring that the Diesel Air Compressors are operating if IA header pressure decreases below the setpoint is to (2)

Which ONE of the following completes the statements above?

A.

1.88

2. ensure operability of 2FDW-315/316 during a subsequent blackout B.

1.88

2. prevent exceeding RB design pressure during a subsequent MSLB/LOOP C.

1.90

2. ensure operability of 2FDW-315/316 during a subsequent blackout D.

1.90

2. prevent exceeding RB design pressure during a subsequent MSLB!LOOP Page 90 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

91 (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Unit is returning to power after a short maintenance outage Reactor power = 2.5% increasing 1A LPI Train piping insulation removal for weld inspection in progress Current conditions:

Power to the 1A LPI Train Flow gage disconnected Which ONE of the following states:

1) the equipment that must be declared inoperable in accordance with the basis of Tech Specs 3.5.3 (LPI) and 3.6.5 (RB Spray and Cooling Systems)?

2) if Unit 1 can continue with the power escalation to 100% in accordance with Tech Specs?

A.

1. 1ALPITrainONLY

2. can continue B.

1. 1ALPITra1nAND1ARBSTrain

2. can continue C.

1. 1ALPITrainONLY

2. can NOTcontinue D.

1. 1ALPITrainAND1ARBSTrain

2. can NOT continue Page 91 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

92 (1 point)

Given the following Unit 1 conditions:

De-fueling in progress Withdrawing assembly from core

1) The MINIMUM load cell reading that will result in the overload light illuminating is (1) lbs.

2)

In accordance with MP/0/Al 500/029 (Main Fuel Bridge Operation) the first action taken to resolve the overload conditions is to (2)

Which ONE of the following completes the statements above?

A.

1. 2000

2. jog the hoist in both directions B.

1. 2000

2. adjust the load cell set point up by 20 pounds C.

1. 2500

2. jog the hoist in both directions D.

1. 2500

2. adjust the load cell set point up by 20 pounds Page 92 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

93 (1 point)

Given the following Unit 1 conditions:

Time = 0400 SFP level = (-) 1.7 feet decreasing 1 SA-9/A-5 (Spent Fuel Pool Level High/Low) actuated ALL SF Cooling Pumps have tripped OFF ALL SF Cooling Pump switches green lights are illuminated Time = 0405 NEC reports actual SFP level is low

1) At 0400, has the LOW SFP Level interlock functioned as designed?

2) At 0405 and in accordance with AP/35 (Loss of SFP Cooling and/or Level) which ONE of the following enclosures will be performed t?

Which ONE of the following completes the questions above?

A.

1. yes

2. Enclosure 5.5 (SFP Makeup from Ui or U2 BWST)

B.

1. yes

2. Enclosure 5.4 (Unit 1-2 SEP Time to Reach 180°F, 200°F)

C.

i.no

2. Enclosure 5.1 (SFP Makeup from 1A B HUT)

D.

1.no

2. Enclosure 5.12 (Jumpering SFP Low Level Interlock)

Page 93 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

94 (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Time0400 LOCA CD tab in progress ALL SCM = 5°F stable RCS pressure = 870 psig slowly decreasing RB pressure peaked at 2.4 psig and is now decreasing HPI aligned for piggyback operation LPI suction source is the RBES 1LP-15 failed CLOSED Current conditions:

Time= 0405 RCS pressure = 855 psig stable 1SA-07/E-6 (ES LPI BYP PERMIT) actuates

1) At 0405, the LPI ES channels_ (1) allowed to be manually bypassed in accordance with the LOCA CD tab.

2) The MAXI MUM allowed HPI flow is (2) gpm.

Which ONE of the following completes the statements above?

A.

1. are

2. 750 B.

1. areNOT

2. 750 C.

1. are

2. 500 D.

1. are NOT

2. 500 Page 94 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

95 (1 point)

In accordance with NSD 301 (Engineering Change Program):

1) An on-line temporary design change is required to have a plan that specifies removal of the change within (1) _from installation.

2) The Operational Control Group (Operations)

(2) responsible for maintaining a log of installed changes.

Which ONE of the following completes the statements above?

A.

1. thirty days

2. is B.

1. thirty days

2. is NOT C.

1. oneyear

2. is D.

1. oneyear

2. is NOT Page 95 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

96 (1 point)

Given the following conditions on Unit 1:

Reactor Power = 100%

1A MDEFWP was declared inoperable at 13:00 on 05/01 1 B MDEFWP was declared inoperable at 14:00 on 05/06 1A MDEFWP was returned to service at 01:00 on 05/07 Which ONE of the following describes when the 1 B MDEFWP is required to be returned to service?

REFERENCE PROVIDED A.

13:00 on 05/08 B.

13:00 on 05/09 C.

13:00 on 05/11 D.

14:00 on 05/13 Page 96 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

97 (1 point)

Given the following plant conditions:

Time = 0400 Reactor power = 100%

1A GWD tank release in progress at 1/3 Station Limit Time = 0415 3B GWD tank release initiated at 1/3 Station Limit Time = 0430 Loss of power to RM-80 skid of 1 RIA-45 (Norm Vent Gas) 1SA8/B-9 RM PROCESS MONITOR RADIATION HIGH in alarm 15A8/B-10 RM PROCESS MONITOR FAULT in alarm 1)

In accordance with OP/3/Al 104/018 (GWD System) the release at 0415 is required to be approved by the (1)

2) At 0430 and in accordance with the ARGs, an RO will (2)

Which ONE of the following completes the statements above?

A.

1. Unit3 CRS

2. manually close GWD-4 B.

1. Unit3CRS

2. verify GWD-4 has automatically closed C.

1. OSM only

2. manually close GWD-4 D.

1. OSMonly

2. verify GWD-4 has automatically closed Page 97 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

98 (1 point)

Given the following Unit 1 conditions:

Time = 0410 Reactor power = 100%

1 RIA-59 = 0.1 gpm 1RIA-60=35 gpm Emergency classification declared Time = 0430 Reactor power = 38%

lAMSLBoccurs Time = 0500 Cooldown is initiated using the 1A SG

1) At 0410, in accordance with the bases of TS 3.4.13, RCS Pressure Boundary LEAKAGE (1) _occurring.

2) At 0500, an Emergency Classification upgrade (2) required (Do NOT use Emergency Coordinators judgment).

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A.

1.is

2. is B.

1.is

2. is NOT C.

1. is NOT

2. is D.

1. is NOT

2. is NOT Page 98 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question:

99 (1 point)

Given the following Unit 1 conditions:

Initial conditions:

All 3 Units reactor power = 100%

1 SA-3/B6 (Fl RE ALARM) actuated NECs dispatched to the Turbine Building 3 rd Floor (1TA and 1TB area)

Current conditions:

NEC reports the fire on 1TB with heavy smoke and rolling flames Fire Brigade is dispatched 1)

In accordance with the Fire Plan a water fog (1) be used on the switchgear to fight the fire.

2)

In accordance with SLC 16.13.1 (Minimum Station Staffing Requirements), an SRO (2) required to serve as the fire brigade leader.

Which ONE of the following completes the statements above?

A.

1.can

2. is B.

1.can

2. is NOT C.

1. can NOT

2. is D.

1. can NOT

2. is NOT Page 99 of 100

Oconee Nuclear Station 1LT42 ONS SRO NRC Examination Question: 100 (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 68% decreasing RCS leak rate = 50 gpm AP/2 (Excessive Leakage) in progress Current conditions:

1TA and 1TB lockout Subsequent Actions tab in progress RCSleakrate= 125 gpm Station has determined that a natural circulation cooldown is desired

1) The (1) tab will be used to cool down the RCS.

2)

In accordance with the above EOP tab, the MAXIMUM allowable cooldown rate is (2).

Which ONE of the following completes the statements above?

A.

1. Forced Coo ldown

2. <25°F/

1

/2hr B.

1. Forced Cooldown

2. <50°F/

1

/2hr C.

1.LOCACooldown

2. 25°F!

1

/2hr D.

1. LOCACooldown

2. 50°F/

1

/2hr Page 100 of 100

FOR REVIEW ONLY

- DO NOT DISTRIBUTE Reference Listfor:

1LT42 ONS SRO NRC Examinati Question Reference List Number 16 AP/34EncI..5.1 48 TS 3.8.3 50 AP/1 1 End. 5.1A Page 5 of 5 83 RP/1000/001 EncL 4.1

- 4.9 86 TS3.2.1 Unit 1 COLR 88 TS3.7.5 96 TS 3.7.5 98 RP/1000/O01 Printed 11/29/2012 2:34:15 PM Page 1 of!

900 800 700 600 500 400 300 200 100 0

100 200

300 400 500 600 700.1 Generator Capability Curve CURVE AB LIMITED BY FIELD HEATING CURVE BC LIMITED BY ARMATURE HEATING CURVE CD LIMITED BY ARMATURE CORE END HEATING AP/l/A/1 700/03 4 Page 1 of3

4 3/2

DC Sources Operating 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 DC Sources Operating LCO 3.8.3 DC Sources shall be OPERABLE as follows:

a.

Three of four 125 VDC Vital l&C power sources for each unit as

follows, Unit 1

- 1CA, lOB, 2CA, 2CB Unit 2

- 2CA, 2CB, 3CA, 3CB Unit 3-3CA, 3CB, 1CA, 1CB; and each aligned to at least one panelboard provided that a power source is not the only source for two or more of the Units panelboards.

b.

Two additional 125 VDC Vital l&C power sources when any other Unit is in MODES 1, 2, 3, or 4; c.

One additional 125 VDC Vital l&C power source when no other Unit is in MODES 1, 2, 3, or 4; d.

Two 230 kV Switchyard 125 VDC power sources.

NOTES 1.

For Units 2 and 3, a 125 VDC Vital l&C power source shall not be the only source for panelboards 1 DIC and 1 DID required by LCO 3.8.8.

2.

Each additional 125 VDC Vital l&C source required by LCO 3.8.3 part b or part c shall be connected to at least one pane Iboard associated with the unit where the source is physically located.

3.

The additional 125 VDC Vital I&C power source required by LCO 3.8.3 part c shall not be a 125 VDC Vital l&C power source that is available to meet the three of four requirement of LCO 3.8.3 part a.

APPLICABILITY:

MODES 1, 2, 3, and 4.

OCONEE UNITS 1, 2, & 3 3.8.3-1 Amendment Nos. 300, 300, & 300

DC Sources Operating 3.8.3 ACTIONS NOTE The Completion Times for Required Actions A through D are reduced when in Condition L of LCO 3.8.1.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One required 125 VDC A.1 NOTE Vital I&C power source Not applicable for up to inoperable.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to perform equalization charge after completion of a performance or service test.

Restore required power 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months source to OPERABLE status.

B.

One required 125 VDC B.1 Align sources such that 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Vital l&C power source one power source is the only source for two not the only source for or more of the Units two or more of the panelboards.

Units panelboards.

C.

NOTE C.1 Align sources such that 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Only applicable to Units one power source is 2 and 3.

not the only source to 1DIC and 1DID.

One 125 VDC Vital l&C power source the only source for panelboards 1DIC and 1DID.

(continued)

OCONEE UNITS 1, 2, & 3 3.8.3-2 Amendment Nos. 300, 300, & 300

DC Sources Operating 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

One 230 kV switchyard D.1 NOTES 125 VDC power source 1.

Not applicable for inoperable, up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to perform equalization charge after completion of a performance or service test.

2.

Not applicable for upto 10 days to replace entire battery bank and perform required tests to restore operability.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Restore power source to OPERABLE status.

E.

Required Action and E.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time not met.

AND E.2 Be in MODE 5.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months 000NEE UNITS 1,2, &3 3.8.3-3 Amendment Nos. 370, 372, & 371

DC Sources Operating 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify correct breaker alignments and voltage 7 days availability from required distribution centers to isolating transfer diodes.

SR 3.8.3.2 Verify battery terminal voltage is 1 25V on 7 days float charge.

SR 3.8.3.3 Verify battery cells, cell plates, and racks 12 months show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.

SR 3.8.3.4 Verify battery cell to cell and terminal 12 months connections are clean and tight, and are coated with anti-corrosion material.

SR 3.8.3.5 Verify battery capacity is adequate to supply, 12 months and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

SR 3.8.3.6 Verify battery capacity is in accordance with In accordance with the the Battery Discharge Testing Program.

Battery Discharge Testing Program OCONEE UNITS 1, 2, & 3 3.8.3-4 Amendment Nos. 300, 300, & 300

.1A CT-4 Overload Limits{O}

AP/l/A/1700/01 1 Page 5 of 5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.

Maintain CT-4 within the limits of Figure 1.

FIGURE 1{20}

CT-4 MEGAWATTS 24 23 22 21 20 19 18 17 16 15 14 13 12 11 10 9

8 7

1 T II 100% 1

--+

+

Ilizz:

7

Jmit wit SK brea ionlyone

<er

Acceptable Region with cooling available 112%

z

z Limit with NO I Forced Cooling

(0I (3uJ 6

5 4

3 2

1 0

1 Accepi ab a egion witi No Cooling available F

\\

i

0 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 2021 22 23 CT-4 Mvar Mwat. Rev. 2

4/12/05 rtr 3.

WHEN directed by CR SRO, THEN EXIT this enclosure.

... END...

.1 Fission Product Barrier Matrix DETERMINE THE APPROPRIATE CLASSIFICATION USING THE TABLE BELOW:

RP/0/B/ 1000/001 Page 1 of I ADD POINTS TO ClASSIFY.

SEE NOTE BELOW RCS BARRIERS (RD 5-7)

FUEL CLAD BARRIERS (RI) 8-9)

CONTAINMENT BARRIERS (BD 10-13)

Potential Loss (4 Points)

Loss (5 Points)

Potential Loss (4 Points)

Loss (5 Points)

Potential Loss (1 Point)

Loss (3 Points)

RCS LeakrateE 160 gpm RCS Leak rate thai results in a loss Average of the 5 highest Average of the 5 highest CETC CETC 1200 F 15 minutes Rapid unexplained containment of subcooling.

CETC I 200 F OR pressure decrease after increase 700 F (ETC 700 F 15 minutes with a ia/itl RVLS reading 0 containment pressure or sump level not consistent with LOCA SGTR 160 gpm Valid RVLS reading of 0 Coolant activity 300 l.tCi/ml DEl RB pressure 59 psig Failure of secondary side of SG OR results in a direct opening to the RB pressure 10 psig and no environment with SG Tube Leak RBCU or RBS tO gpm in the SG NOTE: RVLS is NOT valid if one or more RCPs are running OR if Entry into the PTS (Pressurized I RIA 57 or 58 reading 1.0 RJhr LPI pump(s) arc Hours RIA 57 OR RIA 58 Hours RIA 57 OR RIA 58 SG Tube Leak F 10 gpm exists in Thermal Shock) Operation Since SD RJbr RJhr Since SD R/hr RIhr one SG.

finning AND taking NOTE: PTS is entered under 2 RIA 57 reading F 1.6 R/hr suction from the LPI the other SG has secondary side either of the following:

2 RIA 58 reading F 1.0 R/hr drop line.

0

- <0.5 F 300 F 150 0

tt.5 F 1800 F 860 failure that results in a direct A cooldown below 400F opening to the environment AND

> l00F/hr. has occurred.

3RIA 57 or 58 reading 1.0 Rihr 0.5

- < 2.0 F 80 F 40 0.5

- < 2.0 F 400 F 195 is being fed from the affected unit HPI has operated in the 2.0- 80 F 32 F

16 2.0- 8.0 F 280 F 130 injection mode while NO RCPs were operating.

HPI Forced Cooling RCS pressure spike F 2750 psig Hydrogen concentration 9%

Containment isolation is incomplete and a release path to the environment exists Emergency Coordinator/EOF Emergency Coordinator/EOF Emergency Coordinator/EOF Emergency Coordinator/EOF Director Emergency Coordinator/EOF Emergency Coordinator/EOF Director judgment Director judgment Director judgment judgment Director judgment Director judgment UNUSUAL EVENT (1-3 Total Points)

ALERT (4-6 Total Points)

SITE AREA EMERGENCY (7-10 Total Points)

GENERAL EMERGENCY (11-13 Total Points)

OPERATING MODE:

1.2,3,4 OPERATING MODE:

1,2,3.4 OPERATING MODE:

1.2,3.4 OPERATING MODE:

1,2.3,4 4.1.U. I Any potential loss of Containment 4.1 A. 1 Any potential loss or loss of the RCS 4

I S I

Loss of any two barriers 4.1.G. I Loss of any two barriers and potential loss of the third barrier 4.l.U.2 Any loss of containment 4.I.A.2 Any potential loss or loss of the Fuel 4

I S 2 Loss of one barrier and potential loss of either Clad 4.1.G.2 Loss of all three harriers RCS or Fuel Clad Barriers 4.1.S.3 Potential loss of both the RCS and Fuel (tad Barriers NOTE:

An event with multiple events could occur which would result in the conclusion that exceeding the loss or potential loss threshold is IMMINENT (i.e., within

-3 hours).

In this IMMINENT LOSS situation, use judgment and classify as if the thresholds arc exceeded.

7

.2 System Malfunctions RP/0/B/ 1000/001 Page 1 of2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I.

RCS LEAKAGE (BD 15)

OPERATING MODE:

C 2.3,4 A.

Unidentified leakage 10 gpm B.

Pressure boundary leakage 10 gpm C.

Identified leakage 25 gpni Includes SG tube leakage 2.

UNPLANNED LOSS OF MOST OR ALL SAFETY SYSTEM ANNUNCIATION!

INDiCATION IN CONTROL ROOM FOR> 15 MINUTES(BD 16)

OPERATING MODE:

1,2,3,4 A.

Unplanned loss of> 50% of the following annunciators on one unit for> 15 minutes:

Units I & 3 I SAl, 2.3,4,5,6.7.8.9. 14, 15, 16, & 18 3 SAl, 2,3,4,5,6.7,8,9, 14, 15, 16, & 18 Unit 2 2 SAl. 2,3.4,5.6.7.8,9. 14, 15, & 16 Loss of annunciators or indicators requires additional personnel (beyond normal shift complement) to satbly operate the unit UNPLANNED LOSS OF MOST OR ALL SAFETY SYSTEM ANNUNCIATION!

INDICATION IN CONTROL ROOM (BD 20)

OPERATING MODE:

1,2,3,4 A.

Unplanned loss of> 50% of the following annunciators on one unit for> 15 minutes:

Units I & 3 1 SAl, 2,3,4.5.6,7,8.9. 14. 15, 16, & 18 3 SAl. 2, 3, 4, 5, 6, 7, 8, 9. 14, 15, 16, & 18 Unit 2 2 SAl, 2,3,4,5.6,7,8,9, 14, 15, & 16 Loss of annunciators or indicators requires additional personnel (beyond normal shift complement) to safely operate the unit 1.

INABILITY TO MONITOR A SIGNIFiCANT TRANSIENT IN PROGRESS (BD 22)

OPERATING MODE:

1,2,3,4 A.

Unplanned loss of> 50% of the following annunciators on one unit for> 15 minutes:

Units I & 3 1 SAI,2,3,4,5.6,7,8,9, 14.15, 16.& 18 3 SAl, 2, 3, 4. 5. 6, 7. 8, 9, 14, 15, 16, & 18 Unit 2 2 SAl. 2,3,4.5,6,7.8.9, 14, 15, & 16

!nuhi/iti to direct/i monitor any one of the following functions:

I.

Suheriticality 2.

Core tooling 3

Heat Sink 4

R(S Integrity 5.

Containment Integrii ft.

RCS Inventory (END)

AND AND AND (CONTINUED)

AND AND AND A,slgni/Icant transient is in progress Loss of the OAC and ALL PAM indications SignifIcant p/on! transient in progress OR Loss of the ( )AC and ALL PAM indications (END) 8

.2 RP/O/B/1000/OOl System Malfunctions Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 3.

INABILITY TO REACH REQUIRED SHUTDOWN WITHIN LIMITS (BD 17)

OPERATING MODE:

1.2, 3,4 A.

Required operating mode not reached within TS LCO action statement time 4.

UNPLANNED LOSS OF ALL ONSITE OR OFFSITE COMMUNICATIONS (BD 18)

OPERATING MODE: All A.

Loss of all onsite communications capability (Plant phone system, PA system.

Pager system, Onsite Radio system) affecting ability to perform Routine operations B.

Loss of all onsitc communications capability (Selective Signaling, NRC ETS lines, Offsite Radio System, AT&T line) affecting ability to communicate with offsite authorities.

5.

FUEL CLAD DEGRADATION (BD 19)

OPERATING MODE: A]l:

A, DEI->5l.tCi/ml (END) 9

.3 Abnormal Rad Levels/Radiological Effluent RP/0/B/ 1000/001 Page 1 of2 ANY UNPLANNED RELEASE OF GASEOUS OR LIQUID RADIOACTIVITY TO THE ENVIRONMENT THAT EXCEEDS TWO TIMES THE SLC LIMITS FOR 60 MINUTES OR LONGER (HD 25)

OPERATING MODE: All A.

Valid indication on radiation monitor RIA 33 of 4.06E+06 cpm for> 60 minutes (See Note I) 13.

Va/k! indication on radiation monitor RIA 45 of? 9.35E+05 cpm for> 60 minutes (See Note I)

C.

Liquid effluent being released exceeds two timeS SLC 16.11.1 for> 60 minutes as determined by Chemistry Procedure D.

Gaseous effluent being released exceeds two times SLC 16.11.2 for> 60 minutes as determined by RP Procedure I.

ANY UNPLANNED RELEASE OF GASEOUS OR LIQUID RADIOACTIVITY TO THE ENVIRONMENT THAT EXCEEDS 200 TIMES RADIOLOGICAL TECHNICAL SPECIFICATIONS FOR 15 MINUTES OR LONGER (BD 30)

A.

Valid indication on RL 46 of? 2.09E04 cpm for>l5 minutes (See Note I)

B RIA 33 HIGH Alarm AND Liquid effluent being released exceeds 200 times the level of SLC 1 6. II.1 for>

1 5 minutes as determined by Chemistry Procedure Gaseous effluent being released exceeds 200 times the level of SLC 16.11.2 for >15 minutes at determined by RP Procedure BOUNDARY DOSE RESULTING FROM ACTUAL/IMMINENT RELEASE OF GASEOUS ACTIVITY (RD 35)

OPERATING MODE: All A.

Valid reading on RIA 46 of 2.09E+05 cpm for >15 minutes (See Note 2)

B.

Valid reading on R]A 57 or 58 as shown on.8 (See Note 2)

C.

Dose calculations result in a dose projection at the site boundary of:

? 100 mRem TEDE or 500 mRem CDE adult thyroid D.

Field survey results indicate cite boundary dose rates exceeding lOO mRadJhr expected to continue for more than one hour OR Analyses of field stirs ey samples indicate adult thyroid dose commitment of ? 500 rnRem CDE (3.84 E7 i/mI) for one hour of inhalation NOTE 2: If actual Dose Assessment cannot be completed within 15 minutes, then the ca/id radiation monitor reading should be used for emergency classification.

I.

BOUNDARY DOSE RESULTiNG FROM ACTUAL! IMMINENT RELEASE OF GASEOUS ACTIViTY (BD 39)

OPERATING MODE: All A.

Valid reading on RIA 46 of? 2.09E+06 cpm for l5 minutes (See Note 3)

B.

Valid reading on RIA 57 or 58 as shown on.8 (See Note 3)

C.

Dose calculations result in a dose projection at the site houndart of:

OR

? 5000 mRem CDE adult thyroid D.

Field survey results indicate sire boundary dose rates exceeding? 1000 mRad/hr expected to continue for more than one hour OR Analyses of field survey samples indicate adult thyroid dose commitment of? 5000 mRem CDE for one hour of inhalation NOTE 3: If actual Dose Assessment cannot be completed within 15 minutes. then the va/id radiation monitor reading should be used fir emergency classification.

1 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY OPERATING MODE: All C.

NOTE I: Ifrnonitor reading is sustained for the time period indicated in the EAL the required assessments (procedure calculations) cannot be completed within this period, declaration mutt be made on the valid Radiation Monitor reading.

1000 mRem TEDE (CONTINUED)

((:ONTIN L ED)

(CONtiNUED)

(END)

I 0

.3 Abnormal Rad Leves/Radiological Effluent RP/0/B/ 1000/001 Page 2 of 2 2

UNEXPECTED INCREASE IN PLANT RADIATION OR AIRBORNE CONCENTRATION (BD 27)

OPERATING MODE: All A,

Li 5 reading 14 and decreasing with makeup not keeping up with leakage 33fl fuel in the core B.

Valid indication of nnconovlled water decrease in the SFP or fuel transfer canal with all fuel assemblies remaining covered by waler AND Unplanned t 7

alid RIA 3. 6 or Portable Area Monitor readings increase.

C.

I RJhr radiation reading at one foot away from a damaged storage cask located at the ISFS1 D.

Valid area monitor readings exceeds limits stated in Enclosure 4.9.

NOTE: This Initiating Condition is also located in Enclosure 4.4., (Loss of Shutdown Functions).

I-ugh radiation levels will also be seen with this condition.

2.

RELEASE OF RADIOACTIVE MATERIAL OR INCREASES IN RADIATION LEVELS THAT IMPEDES OPERATION OF SYSTEMS REQUIRED TO MAINTAIN SAFE OPERATiON OR TO ESTABLISH OR MAINTAIN COLD SHUTDOWN (BD 32)

OPERATING MODE: All A.

Va/id radiation reading l5 mRad/hr in CR.

CAS, or Radwaste CR B.

Unp/anned/unexpected sa/icl area monitor readings exceed limits stated in Enclosure 4.9 3.

MAJOR DAMAGE TO IRRADIATED FUEL OR LOSS OF VATER LEVEL THAT HAS OR WILL RESULT IN THE UNCOVERING OF IRRADIATED FUEL OUTSIDE THE REACTOR VESSEL (BD 33)

OPERATING MODE: All A.

ValidRlA3*, 6,41, OR 49* HIGH Alarm

- Applies to Mode 6 and No Mode Only B.

HIGH Alarm for portable area monitors on the main bridge or SFP bridge C

Report of visual observation of irradiated fuel uncovered D.

Operators detcnninc water level drop in either the SFP or fuel transfer canal will exceed makeup capacity such that irradiated fuel n ill be uncovered NOTE: This Initiating Condition is also located in Enclosure 4.4.. (Loss of Shutdown Functions).

I ligh radiation levels will also he seen with ihts condition.

(I D) 2.

LOSS OF WATER LEVEL IN THE REACTOR VESSEL THAT HAS OR WILL UNCOVER FUEL IN THE REACTOR VESSEL (BD 38)

OPERATING MODE:

5,6 A.

Failure of heat sink causes loss of Mode 5 (Cold Shutdown) condition AND LT 5 indicates 0 inches after initiation of RCS makeup B.

Failure of heat sink causes loss of ModeS (Cold Shutdown) condition AND Either train ultrasonic level indication less than o inches and decreasing after initiation of RCS makeup NOTE: This Initiating Condition is also located in Enclosure 4.4., (Loss of Shutdown Functions). High radiation levels will also be seen with this condition.

UNUSUAL EVENT ALERT

[

SITE AREA EMERGENCY 1

GENERAL EMERGENCY (END)

(END))

11

.4 RP/O/B/1000/OO1 Loss of Shutdown Functions Page 1 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY FAILURE OF RPS TO COMPLETE OR I.

FAILURE OF RPS TO COMPLETE OR I.

FAILURE OF RPS TO COMPLETE INITIATE A Rx SCRAM (BD 44)

INITIATE A Rx SCRAM (BD 50)

AUTOMATIC SCRAM AND MANUAL SCRAM NOT SUCCESSFUL WITH OPERATING MODE 1,2,3 OPERATING MODE:

1.2 INDICATION OF CORE DAMAGE (CONTINUE TO NEXT PAGE)

(BD 53)

A.

Valid reactor trip signal received or required A.

Valid reactor trip signal received or required WITHOUT automatic scram WITHOUT automatic scram OPERATING MODE: 1,2 AND A.

ulid Rx trip signal received or required DSS has inserted Control Rods WITHOUT automatic scram R

DSS has NOT inserted Control Rods AND Manual trip from the Control Room is successful and reactor power is less AND Manual trip from the Control Room was NOT than 5% and decreasing

successful in reducing reactor power 10< 5%

and decreasing Manual tnp from the Control Room was NOT successful in reducing reactor power to less than 5% and decreasing Average of the 5 highest CETCs l 2000 Fan ICCM 2.

INABILITY TO MAINTAIN PLANJ IN 2.

COMPLETE LOSS OF FUNCTION MODES (COLD SHUTDOWN)

(BD 46)

NEEDED TO ACHIEVE OR MAINTAIN (END)

MODE 4 (HOT SHUTDOWN)

(BD 51)

OPERATING MODE:

5,6 OPERATING MODE:

1,2, 3,4 A.

Loss of LPI and/or LPSW AND A.

Average of the 5 highest CETCs t200° F

shown on ICCM Inability to maintain RCS temperature B.

Unable to maintain reactor subcritical below 2000 F as indicated by either of the followmg.

C.

FOP directs fueding SG from SSF ASWP or station ASWP R( S temperature at the 1101 Pump Suction (CONTINUED)

Average of the 5 highest CETCs as indicated by ICCM display OR

\\ isual observation (CONTINUED)

=

12

.4 RP/O/B/1000/OO1 Loss of Shutdown Functions Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY UNEXPECTED INCREASE IN PLANT 3.

MAJOR DAMAGE TO IRRADIATED 3.

LOSS OF WATER LEVEL IN THE RADIATION OR AiRBORNE FUEL OR LOSS OF WATER LEVEL REACTOR VESSEL THAT HAS OR CONCENTRATION (BD 42)

THAT HAS OR WILL RESULT IN THE WILL UNCOVER FUEL IN THE OPERATING MODE: AU UNCOVERING OF IRRADIATED FUEL REACTOR VESSEL (BD 52)

OUTSIDE THE REACTOR VESSEL (BD 48)

OPERATING MODE: 5.6 A.

LT 5 reading 14 and decreasing with makeup not keeping up with leakage WITH fuel in the OPERATING MODE: All A.

Failure of heat sink causes loss of Mode 5 core (Cold Shutdown) conditions A.

ValidRlA 3*, 6, 41, OR 49* HIGH Alarm B.

Valid indication of uncontrolled water decrease in the SFP or fuel transfer canal with all fuel assemblics remaining covered by water Applies to Mode 6 and No Mode Only LT-5 indicates 0 inches after initiation of RCS B.

HIGH Alarm for portable area monitors on the Makeup AND main bridge or SFP bridge Unplanned Valid RIA 3. 6 or Portable Area B.

Failure of heat sink causes loss of ModeS Monitor readings increase.

C Report of visual observation of irradiated fuel (Cold Shutdown) conditions uncovered AND C.

I R!hr radiation reading at one foot away from a damaged storage cask located at the ISFSI 0.

Operators determine water level drop in either Either train ultrasonic level indication less than the SFP or fuel transfer canal svill exceed 0 inches and decreasing after initiation of RCS D.

Va/id area monitor readings exceeds limits makeup capacity such that irradiated fuel makeup stated in Enclosure 4.9.

be uncovered I NOTE: This Initiating Condition is also located I

I NOTE: This Initiating Condition is also located I NOTE: This Initiating Condition is also located in Enclosure 4.3, (Abnormal Rad I in Enclosure 4.3, (Abnormal Rad in Enclosure 4.3., (Abnormal Rad I

I Levels/Radiological Effluent). High radiation Levels/Radiological Effluent)

High radiation Levels/Radiological Effluent). 1-ugh radiation levels will also be seen with this condition.

I levels will also be seen with this condition.

levels will also be seen with this condition.

I I

(END)

(END) 13

.5 RP/O/B/1000/OO1 Loss of Power Page 1 of 1 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY LOSS OF ALL OFFSITE POWER TO 1.

LOSS OF ALL OFFSITE AC POWER AND I.

LOSS OF ALL OFFSITE AC POWER AND 1.

PROLONGED LOSS OF ALL OFFSITE ESSENTIAL BUSSES FOR GREATER LOSS OF ALL ONSITE AC POWER TO LOSS OF ALL ONSITE AC POWER TO POWER AND ONSITE AC POWER THAN 15 MINUTES (BD 55)

ESSENTIAL BUSSES (BD 57)

ESSENTIAL BUSSES (BD 59)

(RD 62)

OPERATING MODE: All OPERATING MODE:

5,6 OPERATING MODE:

1,2. 3,4 OPERATING MODE:

1,2. 3,4 Defueled A.

Unit auxiliaries are being supplied from A.

MFB I and 2 de-energized A.

MFB I and 2 dc-energized Keowee or CT5 A.

MFB 1 and 2 dc-energized AND AND NJ A?J Failure to restore power to at least one MFB SSF fails to maintain Mode 3 Failure to restore power to at least one MFB within 15 minutes from the time of loss of (Hot Standby)

{]

Inability to energize either MFB from an offsite within 15 rntnutes from the time of loss of both both offsite and onsite AC power source (either switchyard) within 15 minutes.

offstte and onsite AC power AND At least one of the following conditions exist:

2.

AC POWER CAPABILITY TO 2.

LOSS OF ALL VITAL DC POWER 2.

UNPLANNED LOSS OF REQUIRED DC ESSENTIAL BUSSES REDUCED TO A (BD 60)

Restoration of power to at least one POWER FOR GREATER THAN 15 SINGLE SOURCE FOR GREATER THAN MFB within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is NOT likely MINUTES (BD56)

I5MINUTES (BD58)

OPERATINGMODE:

1,2,3.4 Qg OPERATING MODE: 5, 6 OPERAIING MODE:

1.2,3.4 A.

Unplanned loss of vital DC power to required Indicatiotis of coHtinuing DC busses as indicated by bus voltage lest than degradation of core cooling based A.

Unplanned loss of vital DC power to required A.

AC power capability has been degraded to a 1 10 VDC on Fission Product Barrier DC busses as indicated by bus voltage less single power source for> 15 minutes due to the monitoring than 110 VDC loss of all but one of the following:

(END)

Unit Normal Transfomier (baekcharged)

Failure to restore prmer to at least one required Unit SL Transfonricr DC bus within 15 minutes from the time of loss Failure to restore power to at least one required Another Unit SU Transformer (aligned)

DC bus within 15 minutes from the time of loss CT4 (END)

CT5 (END)

(END)

Loss of Power

- Emergency Action Levels (EAL5) apply to the ability of electrical energy to perform its intended function, reach its intended equipment. ex.

- If both MFBs, are energized but all 4160V switchgear is not available, the electrical energy can not reach the motors intended. The result to the plant is the same as if both MFBs were dc-energized.

14

.6 RP/O/B/1000/OO1 Fire/Explosions and Security Actions

{2}

{3}

Page of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY FIRES/EXPLOSIONS WITHIN THE 1.

FIRE/EXPLOSION AFFECTING (CONTINUE TO NEXT PAGE)

(CONTINUE TO NEXT PAGE)

PLANT (BD 65)

OPERABILITY OF PLANT SAFETY SYSTEMS REQUIRED TO ESTABLISH/MAINTAIN SAFE OPERATING MODE: All SHUTDOWN (BD 70)

NOTE: Within the plant means:

Turbine Building V

V V

V NOTE: Only one train of a system needs to Auxiliary Building V

V V

be affected or damaged in order to satisfy this Reactor Building V

V condition V

Keowee Hydro V

V Transformer Yard B3T B4T Service Air Diesel Compressors A

Fire/explo.cioii.c Keowee Hydro & associated Transformers AND SSF Affected safciy-rclaicd system parameter indications show degraded perfonstance OR A.

Fire within the plant not extinguished within 15 minutes of Control Room notification or Plant personnel report visible damage to verification of a Control Room alann permanent structures or equipment required for sale shutdown B.

Unanticipated eVrp/oVsmoim within the plant resulting in visible damage to pennuinent (Continued) structures/equipment includes steam line break and FDW line break (Continued) 15

.6 Fire/Explosions and Security Actions 2}

{3)

RP/0/B/ 1000/001 Page 2 of2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY I

GENERAL EMERGENCY 2.

CONFIRMED SECURITY CONDITION OR THREAT WHICH INDICATES A POTENTIAL DEGRADATION IN THE LEVEL OF SAFETY OF THE PLANT (BI) 67)

OPERATING MODE: All A.

Security condition that does not involve a HOSTILE ACTION as reported by the Security Shifi Supervisor B.

A credible site-specific security threat notification C.

A validated notification from NRC providing information of an aircraft threat 3.

OTHER CONDITIONS EXIST WHICH IN THE JUDGEMENT OF THE EMERGENCY DIRECTOR WARRANT DECLARATION OF A NOUE.

(BD 69)

A.

Other conditions exist which in the judgment of the Emergency Director indicate that events are itt progress or have occurred whtch indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been inittated. No releases of radioactive material requirtng off-site response or monitoring are expected unless further degradation of safety systems 2

HOSTILE ACTION WITHIN THE OWNER CONTROLLED AREA OR AIRBORNE ATTACK THREAT.

(BD 72)

A.

A HOSTILE ACTION is occstrnng or has occurred witltiti the OWNER CONTROLLED AREA as reported by the Security Shift Supervisor.

B.

A validated notification from NRC of an AIRLINER attack threat within 30 minutes of 3.

OTHER CONDITIONS EXIST WHICH IN THE JUDGEMENT OF THE EMERGENCY DIRECTOR WARRANT DECLARATION OF AN ALERT (BD 75)

OPERATING MODE: All A.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred whtch involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equiptsietlt because of HOSTILE ACTION.

Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

(END)

HOSTILE ACTION within the PROTECTED AREA (BD 76)

OPERATING MODE: All A.

A HOSTILE ACTION is occurring or baa occurred within the PORTECTED AREA as reported by the Security Shift Supervisor.

2.

OTHER CONDITIONS EXIST WHICH IN THE JUDGEMENT OF THE EMERGENCY DIRECTOR WARRANT DECLARATION OF A SITE AREA EMERGENCY.

(BD 78)

A.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which tnvolve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I ) toward Site personnel or equipment that could lead to the likely failure of or: (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the stte bottndary.

A HOSTILE ACTION RESULTING IN LOSS OF PHYSICAL CONTROL OF THE FACILITY (BD 79)

OPERATING MODE: All A.

A HOSTILE ACTION has occurred such that plant personnel are unable to operate equipment required to maintain safety functions B.

A HOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT fuel damage is likely for a freshly off-loaded reactor core in pool.

2.

OTHER CONDITiONS EXIST WHICH IN THE JUDGMENT OF THE EMERGENCY DIRECTOR WARRANT DECLARATION OF A GENERAL EMERGENCY.

(BD 81)

OPERATING MODE: All A.

Other conditions exist which itt the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or I1vIMINENT substatitial core degradation or inciting with potential for loss of containtrient integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.

Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the tmmediate Site area.

(Itl\\D) the site.

OPERATING MODE: All OPERATING MODE: All occurs.

(END)

(END) 16

.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety RP/0/B/ 1000/001 Page 1 of3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1.

NATURAL AND DESTRUCTIVE PHENOMENA AFFECTING THE PROTECTED AREA (BD 83)

OPERATING MODE: All A.

Tremor felt and valid alarm on the strong motion aceelerograph B

Tornado striking within Protected Area Boundary C.

Vehicle crash into plant structures/systems within the Pi-otected Area Boundary D.

Turbine failure resulting in casing penetration or damage to turbine or generator seals 1.

NATURAL AND DESTRUCTIVE PHENOMENA AFFECTING THE PLANT VITAL AREA (BD 89)

OPERATING MODE: All A.

Tremor felt and seismic trigger actuates (O.05g)

NOTE: Only one train of a safety-related system needs to be affected or damaged in order to satisfy these conditions.

B.

Tornado, high winds, missiles resulting from turbine failure, vehicle crashes, or other catastrophic event.

AND Visible damage to permanent stmcwres or equipment required for safe shutdown of the unit.

OR Affected safety system parameter indications show degraded performance.

(CONTINUED)

(CONTINUE TO NEXT PAGE)

(CONTINUED) 17

.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety RP/0/B/1 000/001 Page 2 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY I

GENERAL EMERGENCY 2.

NATURAL AND DESTRUCTIVE PHENOMENA AFFECTING KEOWEE HYDRO CONDITION B (RD 85)

OPERATING MODE: All A.

Reservoir elevation 805.0 feet with all spillway gates open and the lake elevation Continues to rise B.

Seepage readings increase or decrease greatly or seepage water is carrying a significant amount of soil particles C

New area of seepage or wetness, with large amounts of seepage water observed on dam, dam toe, or the abutments D.

Slide or other movement of the darn or abutments which could develop into a failure E.

Developing failure involving the powerhouse or appurtenant structures and the operator believes the safety of the structure is questionable 3.

NATURAL AND DESTRUCTIVE PHENOMENA AFFECTING JOCASSEE HYDRO CONDITION B (RD 86)

RELEASE OF TOXIC/FLAMMABLE GASES JEOPARDIZING SYSTEMS REQUIRED TO MAINTAIN SAFE OPERATION OR ESTABLISH]

MAINTAIN MODE 5 (COLD SHUTDOWN)

(BD 91)

OPERATING MODE: All A.

Reportldetection of toxic gases in concentrations that will be life-threatening to plant personnel B.

Report/detection of flammable gases in concentrations that will affect the safe operation of the plant:

Reactor Building Auxiliaiy Building Turbine Building Control Room OPERATING MODE: All A.

Turbine Building flood requiring use of AP/l 2,3/All 700/I 0, (Turbine Building Flood) 4.

CONTROL ROOM EVACUATION HAS BEEN INITIATED (BD 94) 1.

CONTROL ROOM EVACUATION AND PLANT CONTROL CANNOT BE ESTABLISHED (BD 96) 1 OPERATiNG MODE: All A.

Control Room evacuation has been initiated AND Control of the plant cannot be established from the Aux Shutdown Panel or the SSF within 15 minutes 2.

KEOWEE HYDRO DAM FAILURE (BD 97)

OPERATING MODE: All A.

Imminent/actual darn failure exists involving any of the following:

Keowee Hydro Darn Little River Darn Dikes A, B. C. or D Intake Canal Dike Jocassee Dam

- Condition A (CONTUUED)

A.

Evacuation of Control Room (CONTINUED)

AND AND ONE OF THE FOLLOWING:

Plant control IS established from the Aux shutdown Panel or the SSF OR Plant control IS BEING established from the Aux Shutdown Panel or SSF (CONTINUED) 2.

(CONTINUE TO NEXT PAGE) 3.

TURBINE BUILDING FLOOD (RD 93)

OPERATING MODE: All A.

Condition B has been declared for the Jocassee Dam OPERATING MODE: All 18

.7 RP/O/B/1000/OOl Natural Disasters, Hazards and Other Conditions Affecting Plant Safety Page 3 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4

RELEASE OF TOXIC OR FLAMMABLE 5.

OTHER CONDITIONS WARRANT 3.

OTHER CONDITIONS WRRANT 1.

OTHER CONDITIONS WARRANT GASES DEEMED DETRIMENTAL TO SAFE CLASSIFICATION OF AN ALERT DECLARATION OF SITE AREA DECLARATION OF GENERAL OPERATION OF THE PLANT (BD 87)

(BD 95)

EMERGENCY (RD 98)

EMERGENCY (BD 99)

OPERATING MODE: All OPERATING MODE: All OPERATING MODE:

AU OPERATING MODE: All A.

Report/detection of toxic or flammable gases A.

Emergency Coordinator judgment indicates A

Emergency Coordinator/EOF Director A.

Emergency Coordinator/EOF Director that could enter within the site area boundary in that:

judgment judgment indicates:

amounts that can affect nonnal operation of the plant Plant safety may be degraded Actual/imminent subsiantial core (END) degradation with potential for loss of B.

Report by local, county, State officials for containment potential evacuation of site personnel based on offsite event Increased monitoring of plant functions OR is warranted Potential for uncontrolled (END) radionuclide releases that would 5.

OTHER CONDITIONS EXIST WHICH result in a dose projection at the WARRANT DECLARATION OF AN site boundary greater than 1000 mRem UNUSUAL EVENT (BD 88)

TEDE or 5000 inRem CDE Adult Thyroid OPERATING MODE:

All (END)

A.

Emergency Coordinator determines potential degradation of level of safety has occurred (END) 19

.8 Rp/0/B/1000/001 Radiation Monitor Readings for Emergency Classification Page 1 of 1 All RIA values are considered GREATER THAN or EQUAL TO HOURS SINCE A 57 RIhr I

RIA 58 RIhr*

REACTOR TRIPPED Site Area Emergency General Emergency Site Area Emergency

]

General Emergency 0.0

- < 0.5 5.9E+003 5.9E+004 26E+003 2.6E+004 0.5

- < 1.0 2.6E+003 2.6E+004 1.IE+003 1.1E+004 1.0

- < 1.5 1.9E+003 1.9E+004 8.6E+002 8.6E+/-003 1.5 -<2.0 1.9E+003 1.9E+004 8.5E+002 8.5E+003 2.0

- < 2.5 1.4E--0O3 1.4E+004 6.3E+002 6.3E+003 2.5

- < 3.0 1.2E+003 1.2E+004 5.7E+002 5.7E+003 3.0- < 3.5 1.1E+003 1.IE+004 5.2E+002 5.2E+003 3.5- < 4.0 1.OE+/-003 1.OE+004 4.8E+002 4.8E+003 4.0- < 8.0 1.OE+003 1.OE+004 4.4E+002 4.4E+003

RIA 58 is partially shielded 20

.9 RP/O/B/1000/001 Unexpected/Unplanned Increase In Area Monitor Readings Page 1 of I NOTE:

This Initiating Condition is not intended to apply to anticipated temporary increases due to planned events (e.g.; incore detector movement, radwaste container movement, depleted resin transfers, etc.).

UNITS 1, 2, 3 MONITOR NUMBER UNUSUAL EVENT l000x ALERT NORMAL LEVELS mRAD/HR mRAD/HR RIA 7, Hot Machine Shop Elevation 796 150 5000 RIA 8, Hot Chemistry Lab Elevation 796 4200 5000 RIA 10, Primary Sample Hood Elevation 796 830 5000 RIA 11, Change Room Elevation 796 210 5000 RIA 12, Chem Mix Tank Elevation 783 800 5000 RIA 13, Waste Disposal Sink Elevation 771 650 5000 RIA 15, HPI Room Elevation 758 NOTE*

5000 NOTE:

RIA 1 5 normal readings are approximately 9 mRad/hr on a daily basis. Applying I 000x normal readings would put this monitor greater than 5000 mRad/hr just for an Unusual Event. For this reason, an Unusual Event will NOT be declared for a reading less than 5000 rnRad/br.

21

Regulating Rod Position Limits 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Regulating Rod Position Limits LCO 3.2.1 Regulating rod groups shall be within the physical position, sequence, and overlap limits specified in the COLR.

NOTE Not required for any regulating rod positioned to perform SR 3.1.4.2.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Regulating rod groups A.1 Restore regulating rod 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months sequence or overlap groups to within limits.

requirements not met.

(continued)

OCONEE UNITS 1, 2, & 3 3.2.1-1 Amendment Nos. 300, 300, & 300

Regulating Rod Position Limits 3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Regulating rod groups B.1 NOTE positioned in restricted Not applicable to or unacceptable region.

regulating rod groups positioned in the restricted region.

Initiate boration to 15 minutes restore SDM to within the limits specified in the COLR.

AND B.2.1 Restore regulating 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months rod groups to within acceptable region.

OR B.2.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to less than or equal to THERMAL POWER allowed by regulating rod group position limits.

C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B not met.

OCONEE UNITS 1,2, & 3 3.2.1-2 Amendment Nos. 300, 300, & 300

Regulating Rod Position Limits 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify regulating rod groups are within the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sequence and overlap limits as specified in the COLR.

SR 3.2.1.2 Verify regulating rod groups meet the position 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limits as specified in the COLR.

SR 3.2.1.3 Verify SDM to be within the limit as specified Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to in the COLR.

achieving criticality 000NEE UNITS 1, 2, & 3 3.2.1-3 Amendment Nos. 300, 300, & 300

105 J

Oconee *I Cycle 27 100 Control Rod Position Setpotnts 95 Nn mo rnbIe nods 4 um F

90 85 80 75 70 Unacceptable Operation 65 0

60 55 C

C-5Q 0

40 35 30 25 20 15 10 5

5 1

25 0

10 10 2030 40 50 60 70 80 90 iop_J 1 GroupJ ONEJ-040C

ev 32 Page 25 of 33 105 100 95 90 85 80 75 70 65 60 55 Acceptable 50 Operation 45 40 35 30 25 20 15 10 5

75 85 II iliti II II j 1

Iljltlt 0

[5 10 20 30 4050607080 90 100 J Group7J Control Rod Posfilon, % WD

105 100 95 90 85 80 75 70 65 0

60 55 050 0

C) cc 40 35 30 25 20 15 10 5

0 Oconee I Cycle 27 0

10 20 30 40 50 60 70 80 90 100 I GroupJ ONEI-04(

ev 32 Page 26 of 33 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5

0 0

10 20 3040 50 60 70 80 90 100 LGrOUP7J Control Rod Position, % WD

J Oconee I Cycle 27 105 105 100 Control Rod Position Setpoint ioo fno erable Rod, 4 Ptim 95 95 90 90 85 85 80 80 75 75 70 70 65 65 Unacceptable Li so Operation 60 55 55 0

0 5Q 50 Acceptable 45 Operation 45 ci) 40 40 35 35 30 30 25 25 20 20 15 15 10 10 5

GroupS 5

5 15 25 35 45 55 65 75 85 95 0

c

c c

I I

I l

c

c 1j c

iii I

I 1f I I I I

0 I 0 10 20 304050 6070 80 90 100 J

j b

20 30 40 50 60 70 80 90 ioOl L!:pup 5 f

[oup 7 I

ONEI-041 ev 32 Page 27 of 33 Control Rod Position, % WD

105 100 95 90 85 80 75 70 65 a60 55 0

50 0

()

(0 40 35 30 25 20 15 10 5

0 L

Oconee I Cycle 27 10 20 30 40 50 60 70 80 90 100 Group 5 ONEI-0 t-ev 32 Page 28 of 33 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5

0 0

10 20 30 4050 60 70 80 90 100 Group 7 Control Rod Position, % WD

EFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Emergency Feedwater (EFW) System LCO 3.7.5 The EFW System shall be OPERABLE as follows:

a.

Three EFW pumps shall be OPERABLE, and b.

Two EFW flow paths shall be OPERABLE.

NOTE Only one motor driven emergency feedwater (MDEFW) pump and one EFW flow path are required to be OPERABLE in MODE 4.

APPLICABILITY:

MODES 1,2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One MDEFW pump A.1 Restore MDEFW pump 7 days inoperable in MODE 1, to OPERABLE status.

2,or3.

AND 10 days from discovery of failure to meet the LCO B.

Turbine driven EFW B.1 Restore turbine driven 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pump inoperable in EFW pump and EFW MODE 1,2,or3.

flowpathto AND OPERABLE status.

OR 10 days from discovery of failure to meet the One EFW flow path LCO inoperable in MODE 1, 2, or 3.

(continued)

OCONEE UNITS 1, 2, & 3 3.7.5-1 Amendment Nos. 300, 300, & 300

EFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Two MDEFW pumps C.1 Restore one MDEFW 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable in MODE 1 pump to OPERABLE 2, or 3.

status.

D.

Required Action and D.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, AND or C not met.

D.2 Be in MODE 4.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR Turbine driven EFW pump and one EFW flow path inoperable in MODE 1,2, or3.

(continued)

OCONEE UNITS 1,2, &3 3.7.5-2 Amendment Nos. 300, 300, & 300

EFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

Three EFW pumps El NOTE inoperable in MODE 1, LCO 3.0.3 and all other 2, or 3.

LCO Required Actions requiring MODE Qfl changes are suspended until one Two EFW flow path EFW pump and one inoperable in MODE 1, EFW flow path are 2, or 3.

restored to OPERABLE status.

Initiate action to restore Immediately one EFW pump and one EFW flow path to OPERABLE status.

F.

Required MDEFW F.l Initiate action to restore Immediately pump inoperable in required MDEFW MODE 4.

pump and required EFW flow path to OR OPERABLE status.

Required EFW flow path inoperable in MODE 4.

000NEE UNITS 1, 2, & 3 3.7.5-3 Amendment Nos. 300, 300, & 300

EFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each EFW manual, and non-automatic 31 days power operated valve in each water flow path and in the steam supply flow path to the turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.5.2 Verify the developed head of each EFW pump In accordance with the at the flow test point is greater than or equal Inservice Testing to the required developed head.

Program SR 3.7.5.3 NOTE Not required to be met in MODES 3 and 4.

Verify each EFW automatic valve that is not 18 months locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.5.4 NOTE Not required to be met in MODES 3 and 4.

Verify each EFW pump starts automatically 18 months on an actual or simulated actuation signal.

SR 3.7.5.5 Verify proper alignment of the required EFW Prior to entering MODE 2 flow paths by verifying valve alignment from whenever unit has been the upper surge tank to each steam in MODE 5 or 6 for> 30 generator.

days 000NEE UNITS 1, 2, & 3 3.7.5-4 Amendment Nos. 300, 300, & 300

Examination KEYfor: 1LT42 ONS SRO NRC Examin Question Answer Number 76 A

77 A

78 A

79 B

80 A

81 D

82 B

83 B

84 A

85 D

86 D

87 A

88 A

89 C

90 D

91 D

92 C

93 C

94 A

95 C

96 B

97 C

98 D

99 B

100 A

Printed 11/29/2012 3:21:17PM Page 4 of4

ML13018A352

Text

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