Text

October 2003 Exam 50-369/2003-302 & 50-370/2003-302 Final SRO Written Exam References
	ML033090465
Person / Time
Site:	McGuire, Mcguire
Issue date:	10/21/2003
From:	; Duke Energy Corp
To:	; Office of Nuclear Reactor Regulation
References
	50-369/03-302, 50-370/03-302
	Download: ML033090465 (120)
	v • d • e

Final Submittal (Blue Paper)

1.

Senior Operator Written Examination References MCGUIRE OCTOBER 2003 EXAM 50-369 & 50-37012003-302 OCTOBER 21,2003

Questions with References Question

1. 121.1

2. 210.1

3. 1079

4. 1082

5. 1084

6. 1087

7. 1088 Reference Technical Specification 5.2.2 RP/O/A/5700/004 General Emergency Technical Specification 3.3.1 and Table 3.3 1-1 RTS Instrumentation EP/l/A/5000/F-O Containment page 9 EP/I/A/5000/ECA-l.I Loss of Emergency Coolant Recirc Technical Specification 3.7.1 Main Steam Safety Valves Data Book Curve 7.38 Pressurizer

Duke Power Company (1) IDNo. EP/l/N5000/ ECA-1.1 PROCEDURE PROCESS RECORD Revision No.

008 REPARATION (2) Station McGuire Nuclear Station (3) Procedure Title Loss of Emergency Coolant Recirc (4) Prepared By Weiner,Michael R Date June 3,2003 (5) Requires NSD 228 Applicability Determination? If Applicability Determination is required, attach NSD 228 documentation.

Yes 0 No 0

No (loincorporate approved changes)

(New procedure or revision with major changes)

(Revision with minor changes)

(6) Reviewed By

5.

(QR)

Cross-Disciplinary Review By Reactivity Mgmt. fieview By Mgm:. lnvolvemant Review By (OPS sup:.)

N A

~

Date Reviewed By Date Reviewed By Dale BY (OSMMR) Date-(7) Additional Reviews (8) Temporary Approval (if necessary)

Date Date-

19) Approved By PERFORMANCE (Compare with Control Cop. every 14 calendar days w;iile work is being performed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date By (QW (11) Date(s) Pedormed Work Order Number NO#)

COMPLETION (12) Procedure Completion Verification 0

Yes NA 0 Yes 0 NA 0 Yes 0 NA 0

Yes 0 NA 0

Yes 0 NA Verified By Date (13) Procedure Completion Approved Date (1 4) Remarks (Affach addifional pages. if necessary.)

Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

Required enclosures attached?

Data sheets attached. completed, dated and signed?

Charts. graphs, etc. attached, dated. identified. and marked?

Procedure requirements met?

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP/I/A/~OOO/ECA-I

. I 1 Of61 Rev 8 A. Purpose This procedure provides actions to restore emergency coolant recirc capability, to delay depletion of the FWST by adding makeup and reducing oufflow, and to depressurize the NC System to minimize break flow.

9. Symptoms or Entry Conditions This procedure is entered from:

UNIT 1 EP/I/A/5OOO/E-l [LOSS Of Reactor Or Secon_-ry Coolant), Step 13, and EP/l/A/5000/ES-I.2 (Post LOCA Cooldown And Depressurization), Step 4, when Cold Leg Recirc capability can not be verified.

aligned or maintained.

than setpoint.

from the sump can not be established or maintained.

not be verified.

EP/l/A/5000/ES-I.3 (Transfer To Cold Leg Recirc), Foldout Page, if recirc flow cannot be EP/l/A/5000/ES-1.3 (Transfer To Cold Leg Recirc), Step 3, if containment sump level less EP/l/A/5000/ES-1.3 (Transfer To Cold Leg Recirc), Step 6, when at least one flow path EP/l/A/5000/ES-1.3 (Transfer To Cold Leg Recirc), Step 11, if Cold Leg Recirc flow can EP/l/A/5000/ECA-1.2 (LOCA Outside Containment), Step 3, when a LOCA outside containment cannot be isolated.

A C T I O N I E X P E C T E D RESPONSE RESPONSE NOT O B T A I N E D C. Operator Actions

1.

Monitor Foldout page.

2.

Try to restore Cold Leg Recirc capability:

a. Check any ND pump - ON.

a. Perform the following:

7 j E ioiitaiilirtent sump k v i i is iess than 3 fr, THEN GO TO Step 2.b.

2) Close the following:

1ND-19A (A ND Pump Suct From FWST or NC) 1ND-4B (E ND Pump Suct From FWST or NC).

E Closing 1ND-19A and INU-48 meets one of the permissives to allow manual opening of associated sump valve.

3) WHEN 1 ND-I 9A is closed, THEN attempt to open 1NI-185A (RE Sump To Train A ND B NS) as follows:

- Place control permissive switch in "BYPASS and open lNI-185A.

4) WHEN IND-46 is closed, THEN attempt to open 1NI-1848 (RE Sump To Train 6 ND 8 NS) as follows:

- Place control permissive switch in

5)

"BYPASS" and open 1Nl-1848.

sump valve opens, THEN start ND pump on same train.

LOSS OF EMERGENCY COOLANT RECIRC A C T 1 ON/EXPECTED RESPONSE PAGE NO.

Rev. 8 3 Of 61 RESPONSE NOT OBTAINED d

Check containment sump level -

d.

NC inventory loss occurring outside

- GREATER THAN 3 FT containment, THEN GO TO Step 3.

ACTlDNiEXPECTED RESPONSE

2. (Continued)

RESPONSE NOT OBTAINED

~~

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP/l/A/5000/ECA-l 1 4 Of 61

e. Check Cold Leg Recirc capability RESTORED.

e. Perform the following:

1) Continue attempts to restore Cold Leg Recirc capability as follows:

- Power restoration Local valve operation e Otter. actioris as specified by station management.

2) E loss of Cold Leg Recirc capability is due to air binding of NV and NI pumps, THEN vent pumps PER (Venting NV and NI Suction for Cold Leg Recirc), prior to starting pumps.

3) WHEN Cold Leg Recirc capability is restored, THEN GO TO Step 2.f.

4)

Step 3

f. Check FWST level - LESS THAN 180 inches ("FWST LEVEL L O alarm)

g. Check the following pumps - ON:

At least one NI pump

- At least one NV pump.

f. RETURN TO procedure and step in effect.

g WHEN ND discharge is aligned to NI and NV pump suction in EP/l/N5000/ES-1 3 (Transfer To Cold Leg Recirc).

NV pumps as required by S/I Reinitiation Criteria on ES-I 3 foldout Page restart NI and

h. CO TO EP/l/A/5000/ES-I.3 (Transfer To Cold Leg Recirc).

MNS EP/l/A/5OOO/ECA-l. I LJNIT I ACTION/EXPECTEO RESPONSE

~~~

PAGE NO.

LOSS OF EMERGENCY COOLANT RECIRC 5 of 61 RESPONSE NOT O B T A I N E D

3.

Reset the following:

a. S/I.

a.

any reactor trip breaker is closed, T":

1) Dispatch operator to open Unit 1 reactor trip breakers.

2) WHEN trip breakers open, THEN reset SA.

b. Sequencers

b. Dispatch operator to open breaker for affected sequencer DC control power:

A Train - 1 EVDA Breaker 6 B Train - 1 EVDD Breaker 8.

c. IF A 1 ANY TIME a BIO signal occurs, THEN restart S/I equipment previously on.

4.

Depress "SS RESET" for the following valves:

1NI-1846 (RB Sump To Train B ND 8

- INI-185A (RB Sump To Train A ND 8 NS).

NS)

5.

Check if FWST level adequate:

a. FWST level - GREATER THAN 20 INCHES.

b. IF AT ANY TIME while in this procedure FWST level goes below 20 inches,

~

THEN GO TO Step 31

a. m m S t e p 31

6.

Determine NS requirements:

a Check NS pump suction - ALIGNED TO

a. G O m S t e p 9 FWST ACTION/EXPECTED RESPONSE I

RESPONSE NOT OBTAINED

b. Determine number of NS pumps required from the following table:

L E S S T H A N 10 P S I G

~~

~

FWST L E V E L CONTAINMENT PRESSURE I N S PUMPS R E O U I R E D 0

GREATER THAN 33 i n c h e s

( " F W S T L O - L O LEV E L " a 1 a rm )

L E S S THAN 33 i n c h e s

(" F W S T L O - L O G R t A l E R I H A N 15 P i l G BETWEEN IO P S I G AND 15 P S I G N I A L E V E L" a l a r m ) I MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP11/A/5000/ECA-I 1 6 of 61 Rev 8 IJNI?' 1 MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP11/A/5000/ECA-I 1 6 of 61 Rev 8 IJNI?' 1 0

c. Check NS pumps running - EQUAL TO

c. Perform the following.

NUMBER REQUIRED

- 1) Reset Containment Spray

2) Operate NS pumps as required by table above.

7.

Check criteria to align NS System for recirc:

a. Any NS pump - ON.

a. G O E S t e p 8.

b. Check containment sump level.

GREATER THAN 3 FT.

b. Perform the following:

- 1) WHEN containment sump level greater than 3 ft. THEN perform Step 7.c.

- c Align NS for recirc PER Enclosure 3 (NS Alignment To Containment Sump)

MNS EP/l/A/500O/ECA-l 1 UNIT 1 LOSS OF EMERGENCY COOLANT RECIRC

8.

Operate NS discharge isolation valves as follows:

PAGE NO 7 Of 61 Rev 8

a. Close NS spray valves on pumps that are off:

A C T I O N / E X P E C T E D RESPONSE 1ANSPump:

RESPONSE NOT O B T A I N E D I

- 1 NS-32A (A NS Pump Disch Cont Outside Isol)

- 1NS-ZSA (A NS Pump Cisch Coct Cutside Isol).

1B NS Pump:

- 1NS-12B (E NS Pump Disch Cont Outside Isol)

- 1NS-15B (B NS Pump Disch Cont Outside Isol).

b. IF AT ANY TIME NS pumps are stopped or started, THEN:

- Close aszociated NS pump aischarge isolation valves after securing a pump.

- Open associated NS pump discharge isolation valves prior to starting a pump.

9.

Makeup to FWST ~OPllIA162001014 (Refueling Water System), Enclosure 4.2 (FWST Makeup Using Reactor Makeup Blender During Modes 1-5 or While Defueled).

I.

LOSS OF EMERGENCY COOLANT RECIRC MNS EP/l/A/5000/ECA-I 1 UNIT I PAGE NO.

Rev. 8 8 Of 61 A C T I O N i E X P E C T E D RESPONSE RESPONSE NOT O B T A I N E D

b. Check VI header pressure - GREATER THAN 60 PSlG.

b. E CA flow can not be throttled with CA control valves in subsequent steps, THEN control flow PER E i V /A!XOO/G- 'I (Gene;ic Enclosures), Enclosure 16 (CA Flow Control With Loss of VI).

c. Throttle feed flow to maintain all intact SlGs N/R levels between 11%

(32% ACC) and 50%.

c.

N/R level in any intact S/G continues to go up, THEN stop feed flow to that S/G.

MNS EP/~/A/~OOO/ECA-I

. i UNIT 1 A C T I O N / E X P E C T E D RESPONSE LOSS OF EMERGENCY COOLANT RECIRC RESPONSE NOT OBTAINED PAGE NO.

9 of 61 Rev. 0

11.

Monitor shutdown margin during cooldown as follows:

a. WHEN the TSC is staffed, THEN request TSC to evaluate obtaining samples as follows:

1) Consider available cooling of sample HXs as follows:

- KC will remain isolated to normal sat:ipls HXs for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , until KC is realigned to normal sample HXs and KF per AP/l/A/5500/41 (Loss Of Spent Fuel Cooling or Level).

sample is desired prior to aligning KC to KC aux bldg non-essential header, AND fuel damage is not expected, THEN evaluate obtaining sample PER OP/l/A/6200/011 (Unit 1 N M

Sampling) Enclosure 4.6 (1NC Hot Leg with KC Non-essential Header Isolated).

2) Evaluate obtaining periodic NC System boron sample to check shutdown margin during cooldown.

NOTE Sample results are not required prior to initiating cooldown in subsequent steps.

b. WHEN each NC boron sample obtained, THEN:

1) Perform shutdown margin calculation for Cold Shutdown PER OP/O/A/6100/006 (Reactivity Balance Calculation).

2) Check shutdown margin ADEQUATE.

2) Notify station management

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EPII IAI~OOOIECA-1 1 10 of 61 Rev 8 UNIT I I

ACTION/EXPECTED RESPONSE I

RESPONSE NOT O B T A I N E D 1

- 12. WHEN "P-11 PRESSURIZER SI1 BLOCK PERMISSIVE" status light (13-18) lit, THEN depress "BLOCK on Low Pressure Steamline Isolation block switches.

NOTE After the Low Pressure Steamline Isolation signal is blocked, maintaining steam pressure negative rate less than 2 PSlG per second will prevent a Main Steam Isolation.

13.

Initiate NC System cooldown to Cold Shutdown as follows:

a. Check condenser available:

a. a RNO for Step 13.d

- "C-9 COND AVAILABLE FOR STEAM DUMP status light (1SI-18).

LIT

- MSlV on intact SIG(s) - OPEN STEAM PRESSURE MODE.

b. Check "STEAM DUMP SELECT' - IN

b. Perform the following to place steam dumps in steam pressure mode:

CONTROLLER in manual

1) Place "STM PRESS

2) Adjust "STM PRESS CONTROLLER" output to equal "STEAM DUMP DEMAND signal.

3) Place "STEAM DUMP SELECT" in steam pressure mode.

c. W""P-12 LO-LO TAVG" status light (ISI-18) lit, THEN place steam dumps in bypass interlock.

MNS EP/l/A/5000/ECA-l 1 lJNlT 1 LOSS OF EMERGENCY COOLANT RECIRC

d. Dump steam to condenser from intact

d. Perform the following:

- S/Gs while maintaining cooldown rate in NC T-Colds as close as possible without exceeding 100" F in an hour.

1) Ensure Main Steam Isolation reset.

2) Ensure SM PORVs reset.

3) Dump steam using all intact S/G(s)

SM PORVs while maintaining cco!down rate ii? NC T-Cclds as ciose as possible without exceeding 100" F in an hour.

4) any intact SIG SM PORV closed, THEN dump steam using any of the following while maintaining cooldown rate in NC T-Colds less than 100" F in an hour:

a) Dispatch operator to operate intact S/G(s) SM PORV.

b) unavailable. THEN evaluate using the following to dump steam:

Run TD CA Pump Use steam drains PER any intact S/G SM PORV is

- EP/l/A/5000/G-I (Generic Enclosures), Enclosure 19 (SIC Depressurization Using Steam Drains).

5) E no intact S/G available, THEN use faulted SIG.

~

PAGE NO.

11 of 61 Rev 0 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP/l/A15000/ECA-l 1 12 Of 61 Rev 8 UNIT 1

- 1NI-9A (NC Cold OPEN OR A C T I O N i E X P E C T E D RESPONSE 1Nl-lOE (NC CCI, OPEN RESPONSE NOT O B T A I N E D eg Inj From NV) -

Leg Inj From NV) -

OR

- Any ND pump - ON WITH SUCTION ALIGNED TO FWST OR CONTAINMENT SUMP.

I A C T l O N i E X P E C T E D RESPONSE

15.

Establish one train of SI1 flow:

I RESPONSE NOT OBTAINED

a. Check only one NV pump - ON.

a. Perform the following:

1) E both NV pumps on, THEN pertorm the following:

a) E all NC pumps off, AND "REACTOR V E S S E L T LEVEL" is less than 6O%, THEN GO TO Step 15.b.

I

3)

Stop one NV pump q t i

,, I

2) E both NV pumps off, THEN ensure suction aligned to FWST as follows:

i' I,,'

a) Ensure the following valves closed:

1 ND58A (Train A ND To NV 8 NI Pumps)

INI-136B (B NI Pump Suction From ND)

INI-332A (NV & NI Pumps Suction X-Over) 1 Nl-3338 (NV 8 NI Pumps Suction X-over).

b) Ensure the following valves open:

1NV-221A (NV Pumps Suct

- From FWST)

INV-2228 (NV Pumps Suct From FWST) c) Start one NV pump.

MNS EP/I/A/5000/ECA-l 1

[JNIT 1 A C T I O N / E X PEC I t 0 R E S P O N S E LOSS OF EMERGENCY COOLANT RECIRC I

RESPONSE NOT O B T A I N E D PAGE NO.

14 of 61 Rev. 0

15. (Continued)

- b. Check only one NI pump - ON.

b. Perform the following:

1) E both NI pumps on, THEN perform the following:

a) E all NC pumps off, AND "REACTOR VESSEL LR LEVEL" is less than 6O%, THEN GO TO Step 15.c.

5) S!op one NI pump.

2) both NI pumps off, THEN ensure suction aligned to FWST as follows:

a) Ensure the following valves closed:

IND-58A vrain A ND To NV 8 NI Pumps) 1NI.1368 (B NI Pump Suction From ND)

INI-332A (NV 8, NI Pumps Suction X-Over) 1Nl-3338 (NV 8, NI Pumps Suction X-over).

b) Ensure INI-1008 (FWST To NI Pumps) open c) WHEN NC pressure less than 1600 PSIG, THEN start one NI Pump

- c Check NC pressure - LESS THAN 286 PSIG

c. Perform the following:

- 1) Stop ND pumps.

2) GO To Step 16.

I A C T I O N / E X P E C T E D RESPONSE MNS EP111A15000/ECA-l. I LOSS OF EMERGENCY COOLANT RECIRC 1JNIT 1 I

RESPONSE NOT O B T A I N E D PAGE NO.

15 of 61 Rev. 8

15. (Continued)

d. Check only one ND pump - ON.

i G.

Check nowpath from FWST back to containment sump isolated:

a. A Train:

1) Check 1NI-185A (RB Sump To Train

2) Check 1ND-19A (A ND Pump Suct From FWST or NC) - CLOSED.

b. B Train:

A ND & NS) -OPEN.

1) Check 1 NI-184B (RB Sump To Train B ND 8 NS) -OPEN.

2) Check IND-4B (B ND Pump Suct From FWST or NC) - CLOSED.

d. Perform the following:

IF both ND pumps on, THEN stop one pump.

2) both ND pumps off AND available suction source is currently aligned, THEN start one ND pump.

1)

Step 16.b

2) Close IND-19A.

1) Observe Note prior to Step 17 and GO TO Step 17.

2) Close 1ND-4B

I I

A C T I O N / E X P E C T E D RESPONSE LOSS OF EMERGENCY COOLANT RECIRC I

RESPONSE NOT O B T A I N E D PAGE NO.

16 of 61 Rev. 8 E Preference should be given to running 1B NC Pump first, then 1A NC Pump to provide Pzr spray capability.

17.

Check if an NC pump should be started:

a. All NC pumps - OFF.

b. NC subcooling based on core exit T/Cs

c. Check if NC pump seal cooling has been maintained:

- Seal injection flow

- GREATER THAN 0" F.

OR

- KC flow to thermal barrier.

d. Try to start one NC pump PER EP/l/A/5000/G-l (Generic Enclosures), Enclosure 6 (NC Pump Startup).

a. Perform the following:

1) Stop all but one NC pump.

2) Place Pzr spray valve in manual and close for stopped NC pump.

3) m m S t e p 18.

- b. m m S t e p 18

c. Perform the following:

1) Notify station management to perform a status evaluation prior to starting an NC pump.

2) GO TO Step 18.

I,

ACTION/EXPECTED RESPONSE MNS EP/l/A/500O/ECA-l 1 UNIT 1 RESPONSE NOT O B T A I N E D LOSS OF EMERGENCY COOLANT RECIRC A

B PAGE NO.

17 of 61 Rev. 8 35%

15%

35%

15%

a. Check RVLIS indication:

a. GOmStep24.

- E all NC pumps off, THEN check "REACTOR VESSEL LR LEVEL" -

GREATER THAN 60%

OR

- E one NC pump on. THEN check "REACTOR VESSEL D I P -

GREATER THAN REQUIRED D/P FROM TABLE BELOW:

I R e q u i r e d "REACTOR VESSEL D / P "

I O P E R A T I N G NC PUMP

b. NC subcooling based on core exit TlCs

b. Perform the following:

- GREATER THAN 50" F.

1) Determine minimum SI1 flow required PER Enclosure 4 (Flow Required to Match Decay Heat).

2) Minimize SI1 flow by stopping one or more SI1 pumps while maintaining greater than or equal to flow required by Enclosure 4 (Flow Required to Match Decay Heat).

3) GO TO Step 24.

19.

Reset the following:

- Phase A Isolation Phase B Isolation

~

~~

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO EP/l/A/5000/ECA-l 1 18 of 61 Rev 8 UNIT 1 I

1 ACTION/EXPECTED RESPONSE

20.

Establish VI to containment:

a. Open the following:

- 1VI-129B (A Ess Hdr Cont Outside Isol)

- 1VI-16OB (E Ess Hdr Cont Outside Isol) 1VI-15OB (Lwr Cont Non Ess Cont Outside Isci).

b. Check VI header pressure - GREATER THAN 85 PSIG.

RESPONSE NOT O B T A I N E D

21.

Stop the following SI1 pumps:

NDpumps

- NI pumps All but one NV pump

b. Perform the following:

1) Align N2 to all PORVs by opening:

- 1NI-430A (Ernerg N2 From CLA TO 1 NC-34A) 1NI-431B (Ernerg N2 From CIA To 1NC-32B 8.366).

2)

VI not available for CA flow cordrol in subsequent steps, THEN control flow PER EP/l/A/5000/G-1 (Generic Enclosures), Enclosure 16 (CA Flow Control With Loss of VI).

3) Restore VI PER AP/l/A/5500/22 (Loss Of VI).

~~

~

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

22.

Isolate NV SI1 flowpath:

a. Check NV pumps miniflow valves -

a. Perform the following:

OPEN:

1) Open valves.

2) E both valves open, THEN GO TO Step 22.b.

3) E either valve closed, e:

a) Dispaich opera!w to open

- 1NV-1508 (aux bldg, 716+8,

"-55, room 627, NV pump room lA, west of pump motor)

- INV-151A (aux bldg. 716+9,

"-55, room 627, NV pump room lA, west of pump motor).

- 1NV-1508 (NV Pumps Recirculation)

- 1NV-151A (NV Pumps Recirculation).

vaiveis):

b. Close the following valves:

- 1NI-9A (NC Cold Leg lnj From NV)

- INI-108 (NC Cold Leg Inj From NV).

b) Realign charging PER EP/l/A/5000/G-I (Generic Enclosures). Enclosure 18 (Aligning Normal Charging With NV Recirc Path Isolated).

c) WHEN both 1 NV-1508 and 1NV-151A open, THEN charging flow may be throttled to less than 60 GPM.

d) m m S t e p 2 4

b. Dispatch operator to close valve(s):

- INI-9A (aux bldg, 733+12. JJ-52.

room 730, VCT hallway 1 ft south of JJ-52)

- INI-108 (aux bldg. 733+4. JJ-51, room 730, VCT hallway 1 A south of JJ-51).

I I

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP/I/A/500O/ECA-I 1 20 of 61 Rev 8 UNIT I ACTION/EXPECTED RESPONSE

23.

Establish charging:

RESPONSE NOT OBTAINED I

a. Check VI header pressure - GREATER

a. Perform the following:

THAN 60 PSlG.

1) Dispatch operators to perform the following and standby:

- Loosen lock nut and throttle handwheel on 1 NV-238 (Charging Line Flow Control) (aux hldg, 716+3. HH-54, romn 629, Pi3 Punp r a m ) to maintain 6-10 GPM seal injection flow to each NC pump.

- Loosen lock nut and close handwheel on 1NV-241 (Seal Inj Flow Control) (aux bldg, 716+9,

"-52.

room 603, above BW pumps).

2) WHEN 1NV-241 is locally closed, 1 NV-238 is locally throttled, T":

a) Open the following:

1 NV-244A (Charging Line INV-245B (Charging Line Cont Outside Isol)

Cont Outside Isol).

b) 1 NV-244A or 1 NV-245B closed, THEN dispatch operator to open valve(s):

- 1NV-244A (aux bldg, 716+10,

"-52, room 603, above BW pumps)

- INV-245B (aux bldg, 716+11,

"-52, room 603, west of BW c) Place INV-238 (Charging Line Flow Control) controller in manual and fully open.

d) Place 1 NV-241 (Seal lnj Flow Control) manual loader fully open.

I (RNO continued on next oaoe)

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

1.1 EP/I/A/5000/ECA-1.1 I I 21 of61 ACTION/EXPECTED RESPONSE I

- II UNIT 1 RESPONSE NOT OBTAINED I Rev. 8

3) IF AT ANY TIME charging flow is required to be controlled in subsequent steps, THEN have dispatched operators locally adjust flow rate as follows:

Slowly throttle handwheel on

- 1 NV-241.

- Throtrle haridviheel ori INV-230 while maintaining NC pump seal injection flow.

Maintain charging flow less than 175 GPM.

4) m m S t e p 2 4.

b. Throttle INV-238 (Charging Line Flow Control) to maintain 6-10 GPM seal injection flow to each NC pump.

c. Close INV-241 (Seal Inj Flow Control).

d. Open the following valves:

- 1NV-244A (Charging Line Cont Outside Isol)

- INV-245B (Charging Line Cont

e. IF AT ANY TIME charging flow is required to be controlled in subsequent steps, THEN:

Slowly throttle 1 NV-241 Throttle 1NV-238 while maintaining Outside Isol).

NC pump seal injection flow.

Maintain charging flow less than 175 GPM.

d. Dispatch operator to open valve(s):

- INV-244A (aux bldg, 716+10. "-52.

room 603, above BW pumps)

- INV-245B (aux bldg, 716+11, "-52, room 603. west of BW pumps).

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP/IIA/5000/ECA-I.I 22 of 61 LJNIT I Rev. 8 I

RESPONSE NOT OBTAINED ACTION/EXPECTED RESPONSE Check if NC System makeup flow is adequate:

a. Check RVLIS indication:

a. Raise NC System makeup flow as

~~ t 1

24.

required to maintain RVLIS indication all NC pumps off, THEN check "REACTOR VESSEL LR LEVEL" -

GREATER THAN 60%.

OR e

m e ?1C pump zn, I'"

check "REACTOR VESSEL D / P -

GREATER THAN REQUIRED DIP FROM TABLE BELOW:

C 15%

35%

I I

R e q u i r e d " REACTOR V E S S E L D / P "

7 D

15%

O P E R A T I N G N C PUMP I

R V L I S T R A I N

b. Core exit TlCs - STABLE OR GOING DOWN.

c. IF AT ANY TIME RVLlS indication goes below setpoint in Step 24.a, exit T/Cs start going up, THEN raise NC System makeup flow as required to maintain:

core

- RVLIS indication

- Core exit TlCs stable or going down

b. Raise NC System makeup flow as required to maintain core exit Tics stable or going down.

MNS EP/1 /A/5000/ECA-1 1 LOSS OF EMERGENCY COOLANT RECIRC llUlT 1

25.

IF AT ANY TIME NC pump number 1 seal DIP goes below 200 PSlD seal leakoff flow goes below 0.2 GPM, T":

number 1 PAGE NO 23 of 61 Rev 0

a. Stop affected NC pump@)

b. Place Pzr spray valve in manual and close for stopped NC pump.

A -I( f A " t ' l f ' 1 d L > ;

f q > f e

If all KC pumps are off, ihe upper head region may void during NC System depressurization. This will cause Pzr level to rise rapidly.

I R C 5 P O h S t hOT De I A I N E D 1

26.

Depressurize NC System to lower NC subcooling as follows:

a. aOStep 27.

a. Check NC subcooling based on core exit TICS - GREATER THAN 10" F.

b. WHEN following criteria met, THEN stop depressurization started in next step:

- NC subcooling based on core exit T/Cs - BETWEEN 0" F AND I O " F OR

- Pzr level - GREATER THAN 76%

(58% ACC).

LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

24 of 61 Rev 8

c. Depressurize NC System using normal

c. Depressurize NC System as follows Pzr spray until criteria above met.

until criteria met:

1) a Pzr PORV is available, THEN:

a) Depressurize NC System using one Pzr PORV.

b) LF AT ANY TIME during depressurization. NC wbcscling based 011 core exit TICS goes below 0" F, THEN:

Ensure PORV is closed or isolated.

(1)

(2) subcooling based on core exit TICS is still less than 0" F, THEN raise makeup flow as necessary to restore subcooling.

10 Pzr PORV will operate, THEN:

2) a) Align N2 to all PORVs by opening:

- 1NI-430A (Emerg N2 From CLA TO 1 NC-34A)

ACTION/EXPECTED RESPONSE

- INI-431B (Emerg N2 From CLA To INC-32B & 368).

RESPONSE NOT O B T A I N E D b) Use one Pzr PORV until criteria met.

3) E Pzr PORV available, THEN GO To Step 27.

(RNO continued on next page)

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP/l/A/5000/ECA-l. 1 25 of 61 UNIT 1 Rev. 8 I

1 ACTlONiEXPECTED RESPONSE RESPONSE NOT OBTAINED I

26. (Continued)

4) E no Pzr PORV available, THEN use NV aux spray as follows:

a) Close Pzr spray valves:

1 NC-27 (A Loop PZR Spray Control) 1 NC-29 (B Loop PZR Spray Control).

b) Open 1NV-21A (NV Spray To PZR Isol).

c) Close:

1 NV-138 (NV Supply TO A NC Loop Isol)

- 1NV-16A (NV Supply TO D NC Loop Isol).

d) Raise charging flow up to 175 GPM as desired to raise depressurization rate.

e) WHEN criteria to stop depressurization in Step 26.b is met, THEN isolate NV aux spray as follows:

(1) Open INV-138 (NV Supply To A NC Loop Isol).

(2) Close INV-21A (NV Spray To PZR Isol).

(3) Ensure charging flow is less than 175 GPM.

MNS EP/l/A/5000/ECA-l.l UNIT 1 LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

26 of 61 Rev. 0

27.

Check if ND can be placed in RHR mode:

a. Check the following:

a. GOTO Step 28.

- NC T-Hots - LESS THAN 350" F (347" F ACC)

ACTION/EXPECTED RESPONSE

- NC pressure - LESS THAN 385 PSlG.

I RESPONSE NOT OBTAINED

b. Consult station management to

~eterrnine if ND shouid be placed in RHR mode.

c.

station management decides to place ND in RHR mode, THEN REFER To (Placing ND in RHR Mode).

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A C T I O N / E X P E C T E D RLSPONSE MNS EP/l/A/5000/ECA-I.1 UNIT 1 RESPONSE NOT O B T A I N E D LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

27 of 61 Rev. 8

a. Check at least two NC T-Hots - LESS THAN 354" F.

b. Place the power disconnect switches to "ENABLE and close (he following:

- 1NI-54A (A CL Accum Disch Isol)

- 1 NI-65B (B CL Accum Disch Isol)

- INI-76A (C CL Accum Disch Isol)

- 1NI-88B (D CL Accum Disch Isol).

__ c. WHEN valves indicate closed for at least 5 seconds, THEN return power disconnect switches to disconnect.

- 29.

Check NC temperature - GREATER THAN 200" F.

a. Perform the following.

- 1) WHEN at least two NC T-Hots less than 354" F, THEN perform Steps 28.b and 28.c.

2) G O m S t e p 29.

b. Vent any unisolated CLA as follows:

1) Open isolation valve on atfected CLA:

1NI-50 (A CL Accum N2 Supply Isol)

- 1NI-61 (B CL Accum N2 Supply

- 1 NI-72 (C CL Accum N2 Supply

- 1NI-84 (D CL Accum N2 Supply Isol)

Isol)

Isol).

2) Open 1NI-83 (CL Accum N2 Hdr Atmos Vent Isol).

3) Do not depressurize NC System below CLA pressure in subsequent steps until CLAs are isolated or vented.

4)

CLA cannot be isolated or vented, THEN contact TSC for guidance.

- CO Step 39.

- 30 Check FWST level - LESS THAN 20 INCHES.

- RETURN TO Step 1.

II I

ACTION/EXPECTEO RESPONSE LOSS OF EMERGENCY COOLANT RECIRC RESPONSE NOT O B T A I N E D PAGE NO.

28 of 61 Rev. 8 MNS UNIT 1 1.1 EP/1/A/5000/ECA-1.1

31.

Stop pumps as follows:

a. Stop S/I pumps that are taking suction from FWST:

- NDpumps

- NI pumps

- NVpumps.

b.

either NS pump sucti6n aliyried to FWST. THEN perfomi the following an train aligned to FWST:

1) Reset Containment Spray

2) Stop NS pump(s).

3) Dispatch operator to remove control power fuses for NS pump(s) (1 ETA, 1 ETB swgr room).

c. Dispatch operator to open breakers to sequencer DC control power:

A Train - lEVDA Breaker 6 B Train - IEVDD Breaker 8.

32.

Try to raise makeup to NC System from any available alternate source:

a. VCT:

1) Dispatch operator to realign makeup back to VCT:

a) Close 1 NV-172 (Boric Acid Blender Disch to NV 8, FW) (aux hallway) bldg, 733+6, KK-51, VCT b) Close 1NV-174 (Boric Acid Blender Disch to NV 8 FW) (aux hallway) bldg, 733+6, KK-51, VCT

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

29 of 61 EP/l/A15000/ECA-l 1 Rev 0 UNIT 1 I

A C T I O N / E X P E C T E D RESPONSE I

RESPONSE NOT OBTAINED

32. (Continued)

2) Check VCT makeup control system:

a) Set boric acid flow control pot at 6.5.

b) Ensure NC System makeup controller in "AUTO.

c) Place NC System makeup w i x h t9 "S TAR'I".

d) Ensure VCT level is maintained.

3) Check VCT - AVAILABLE AS NV SUCTION SOURCE.

3) Perform the following:

a) WHEN VCT available, evaluate performing Step 32.a.

b) GO TO Step 32.b

4) Open:

- 1NV-141A (VCT Outlet Isol!

- 1NV-1426 (VCT Outlet Isol)

5) Close:

1NV-221A (NV Pumps Suct From FWST)

- 1 NV-2228 (NV Pumps Suct From FWST).

6) Close 1NV-241 (Seal Inj Flow Control).

7) Open:

1 NV-244A (Charging Line Cont Outside Isol) 1 NV-2456 (Charging Line Cont Outside Isol).

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP/IIA/5000/ECA-1 1 30 of 61 Rev 8 I

UNIT 1 ACTlONiEXPECTED RESPONSE RESPONSE NOT OBTAINED

32. (Continued)

8) Close:

- 1NI-9A (NC Cold Leg lnj From NV)

- 1 NI-1OB (NC Cold Leg Inj From NV).

9) Check if LOCA or steam break inside cc:i!aiiimefl! - HAS OCCURRED.

9) Perform the following:

a) Open:

- 1NV-1508 (NV Pumps

- INV-151A (NV Pumps Recirculation)

Recirculation).

b) Place controller in manual and close 1 NV-238 (Charging Line Flow Control).

c) Start one IdV pump d) Control charging as follows:

- Slowly throttle open 1 NV-241.

- Throttle INV-238 while maintaining NC pump seal injection flow 6-10 GPM.

- Maintain charging flow less than 175 GPM.

e) CO To Step 32.b IO) Place controller in manual and fully open INV-238 (Charging Line Flow Control).

11) Start one NV pump

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP/l/A/5000/ECA-l 1 31 of 61 Rev 8 UNIT 1 ACTION/EXPECTED RESPONSE RESPONSE NOT O B T A I N E D

32. (Continued)

CAUTION Failure to maintain charging flow above 60 GPM will result in inadequate NV pump miniflow protection. This limit applies to all subsequent EPs.

12) Throttle 1NV-238 (Charging Line Flow Control) and 1NV-241 (Seal lnj Flow Control) to:

- Establish and control charging flow belween 60 GFM and 175 GPM.

- Control NC pump seal injection flow between 6-10 GPM.

b. Check any NV pump - ON.

b. E NC System depressurized, THEN evaluate aligning BATIRMWST to NC System (through NV suction), using any of the following:

- Emergency boration to NV suction.

OR Use VCT overpressure:

- Maintain VCT level.

Align NV suction to VCT.

E flowrate is too high for VCT makeup, THEN realign NV S/I flowpath to normal charging.

c. Start standby Makeup pump PER (Standby Makeup Pump Startup).

d. Consult with station management staff to evaluate pumping sump to FWST using the following flowpaths:

ND pump recirc NS pump recirc.

MNS EPlllA15000lECA-1. 1 UNIT 1 LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

32 of 61 Rev. 0 I

A C T I O N / E X P E C T E D RESPONSE RESPONSE NOT OBTAINED

33.

Depressurize intact SlGs to 660 PSIG as follows:

a. Check all intact SIG pressures GREATER THAN 660 PSIG.

b. Check condenser available:

- "C-9 COND AVAllABLE FOR STEAM DUMP status light (ISI-18) -

LIT

- tJlSlV on intact S/G(s) - OPEN

c. Check "STEAM DUMP SELECT" - IN STEAM PRESSURE MODE.

a. G O m S t e p 34.

b. a RNO for Step 33.e.

c. Perform the following to place steam dumps in steam pressure mode:

1) Place "STM PRESS

2) Adjust "STM PRESS CONTROLLER in manual.

CONTROLLER output to equal "STEAM DUMP DEMAND signal.

3) Place "STEAM DUMP SELECT" in steam pressure mode.

d. WHEN "P-12 LO-LO TAVG" status light (ISI-18) lit, THEN place steam dumps in bypass interlock.

~~

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MNS EP/l/A/5000/ECA-l. 1 UNIT I LOSS OF EMERGENCY COOLANT RECIRC A C T l O N i E X P E C T E D RESPONSE PAGE NO.

33 of 61 Rev. 8 RESPONSE NOT OBTAINED

e. Dump steam from intact S/G(s) to condenser at maximum rate while attempting to avoid a Main Steam Isolation.

f.

g. Stop S/G depressurization.

Check S/G pressures - LESS THAN 660 PSlG.

e. Dump steam using intact S/G SM PORVs as follows:

1) Ensure Main Steam Isolation reset.

2) Ensure SM PORVs reset

3) Dump steam using all intact S/G(s)

SM PORVs at maximum rate.

4) E any intact S/G SM PORV closed, e

dump steam at maximum rate:

a) Dispatch operator to operate intact S/G(s) SM PORV.

b) E any intact SIG SM PORV is unavailable, THEN evaluate using the following to dump steam:

- Run TD CA Pump.

Use steam drains PER

- EP/l/A/5000/G-I (Genetic Enclosures), Enclosure 19 (S/G Depressurization Using Steam Drains).

f. RETURN To Step 33.b.

LOSS OF EMERGENCY COOLANT RECIRC 1 PAGENO.

I 34 Of 61 MNS

'.I EPIl/A/5000/ECA-l.l I

ACTION/EXPECTED RESPONSE 1 Rev. 0 UNIT 1 I

RESPONSE NOT O B T A I N E D 1

R V L I S T R A l F l Required " REACTOR V E S S E L D I P "

O P E R A T I N G NC PUMP A

B C

D

~

A e

~

35%

1 5 %

15%

35%

15%

b Check SiG pressures - LESS THAN b

RETURN LO Step 34 a 110 PSlG i

c. Stop SIG depressurization.

LOSS OF EMERGENCY COOLANT RECIRC I

MNS 11 EP/lIA/5000/ECA-1.1 ACTIONiEXPECTED RESPONSE II RESPONSE NOT OBTAINED 1

UNIT 1 I

PAGE NO.

35 of 61 Rev. 8

a. Check at least two NC T-Hots - LESS THAN 354" F.

b. Place the power disconnect switches to "ENABLE and clr,se the fGl;O'.Qif?g:

- 1NI-54A (A CL Accum Disch Isol)

- 1 NI-656 (6 CL Accum Disch Isol)

- 1NI-76A (C CL Accum Disch Isol)

- 1NI-88B (D CL Accum Disch Isol).

a. Perform the following:

- 1) WHEN at least two NC T-Hots less than 354" F, THEN perform Steps 35.b and 35.c.

2) m m S t e p 36

b. Vent any unisolated CLA as follows:

'I)

Open isolation vaive on affected CLA:

0 1 NI-50 (A CL Accum N2 Supply Isol)

- 1NI-61 (B CL Accum N2 Supply

- 1NI-72 (C CL Accum N2 Supply

- 1 NI-84 (D CL Accum N2 Supply Isol)

Isol)

Isol).

2) Open 1 NI-83 (CL Accum N2 Hdr Atmos Vent Isol).

3) Do not depressurize NC System below CLA pressure in subsequent steps until CLAs are isolated or vented.

CIA cannot be isolated or vented, THEN contact TSC for guidance.

4) c WHEN valves indicate closed for at least 5 seconds, return power disconnect switches to disconnect

MNS EP/l/A/5000/ECA-I 1 I

UNIT I LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

36 of 61 Rev. 0 A C T I O N / E X P E C T E D RESPONSE RESPONSE NOT O B T A I N E D

36.

IF AT ANY TIME NC pump number 1 seal DIP goes below 200 PSlD seal leakoff flow goes below 0.2 GPM, number 1 T":

a. Stop affected NC pump(s) b Place Pzr spray valve in manual and close for stopped NC pump.

37.

Cepressurire intact 3% lo atmospheric pressure as foilows:

a. Check "C-9 COND AVAILABLE FOR STEAM DUMP" status light (ISI-18) -

LIT.

a. Perform the following:

1) Ensure Main Steam Isolation reset

2) Ensure SM PORVs reset.

3) Dump steam using all intact S/G(s)

SM PORVs while maintaining cooldown rate in NC T-Colds as close as possible without exceeding 100" F in an hour.

4) E any intact S/G SM PORV closed, THEN dump steam using any of the following while maintaining cooldown rate in NC T-Colds less than 100" F in an hour:

a) Dispatch operator to operate intact S/G(s) SM PORV.

b) E any intact SIG SM PORV is unavailable, T" evaluate using the following to dump steam:

- Run TD CA Pump

- Use steam drains PER EP/l/N5000/G-1 (Generic Enclosures), Enclosure 19 (S/G Depressurization Using Steam Drains).

5) @To Step 38

MNS EP/l/A/500O/ECA-l 1 I

UNIT 1

37. (Continued)

LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

37 of 61 Rev 8

b. Check MSlVs on intact S/Gs - OPEN.

b. Perform the following:

I A C T I O N / E X P E C T E D RESPONSE

1) Reset Main Steam Isolation signals:

RESPONSE NOT O B T A I N E D a) Main Steam Isolation.

b) SMPORVs.

c) MSlV Bypass Valves

2) IF intact 3iG MSlVs required closed to isolate leak, THEN GO TO RNO for Step 37.e.

3) Place "STEAM DUMP SELECT" in steam pressure mode.

C.

- Check "STEAM DUMP SELECT' - IN STEAM PRESSURE MODE.

4) Place "STM PRESS CONTROLLER in manual and close.

5) ODen MSlV bvDass valves on intact I

SiGs to equal& pressure across MSIVs.

6) WHEN pressure equalized, THEN:

a) Open all MSlVs on intact SIGs.

b) Close all MSlV bypass valves.

c) Perform Steps 37.d and 37.e.

7) a Step 38.

c. Perform the following to place steam dumps in steam pressure mode:

- 1) Place "STM PRESS

2) Adjust "STM PRESS CONTROLLER" in manual.

CONTROLLER" output to equal "STEAM DUMP DEMAND signal.

3) Place "STEAM DUMP SELECT in steam pressure mode.

ACTION/EXPECTED RESPONSE RESPONSE NOT O B T A I N E D 1

MNS EPll/A/500O/ECA-l 1 I

UNIT 1 LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

38 of 61 1 Rev 8

37. (Continued)

d. WHEN "P-12 LO-LO TAVG" status light (1SI-18) lit, THEN place steam dumps in bypass interlock.

e. Dump steam to condenser from intact S/Gs while maintaining cooldown rate in NC T-Colds as close as possible without exceeding 100" F in an hour.

e. Perform the following:

1) Dump steam using all intact S/G(s)

SM PORVs while maintaining cooldown rate in NC T-Colds as clwe as pcssiblc without excseding 100" F in an hour.

2) any intact SIG SM PORV closed, THEN dump steam using any of the following while maintaining cooldown rate in NC T-Colds less than 100" F in an hour:

a) Dispatch operator to operate intact S/G(s) SM PORV.

b) any intact S/G SM PORV is unavailable, THEN evaluate using the following to dump steam:

- Run TD CA Pump.

- Use steam drains PER EP/l/A/5000/G-I (Generic Enclosures), Enclosure 19 (S/G Depressurization Using Steam Drains).

LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

MNS UNIT 1 EPII/A/5000/ECA-1 1 39 of 61 Rev. 8 A C T I O N / E X P E C T E D RESPONSE RESPONSE NOT O B T A I N E D 38 Check if ND can be placed in RHR mode:

a. Check the following:

a. RETURN To Step 37

- All NC T-Hots - LESS THAN 350" F (347" F ACC)

- NC System pressure - LESS THAN 385 PSIG.

b. Consult station management to determine if ND should be placad in RHR mode.

c.

station management decides to place ND in RHR mode, THEN REFER (Placing ND in RHR Mode).

MNS LOSS OF EMERGEhCY COOLANT RECIRC PAGE NO EP/I /A/5000/ECA-1 1 40 of 61 I Rev. 8 UNIT 1 I

I I

I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

39.

Maintain NC System heat removal:

a. E ND in RHR mode, THEN initiate cooldown with ND System.

b. Check "C-9 COND AVAILABLE FOR

b. Perform the following:

STEAM DUMP" status light (13-18)

LIT.

1) Ensure Main Steam Isolation reset

2) Ensure SM PORVs reset

3) Dump steam using intac: S/G(sj SM PORVs.

4) any intact S/G SM PORV closed, THEN dump steam as follows:

a) Dispatch operator to operate intact S/G(s) SM PORV.

b) IF any intact S/G SM PORV is unavailable, THEN evaluate using the following to dump steam:

- Run TD CA Pump.

- Use steam drains PER EP/1 /A/5000/G-1 (Generic Enclosures), Enclosure 19 (S/G Depressurization Using Steam Drains).

5) no intact S/G available AND ND not in RHR mode, =use faulted S/G.

6) Go To Step 40.

MNS LOSS OF EMERGENCY COOIANT RECIRC PAGE NO.

EP/1 /A/5000/ECA-1 1 41 of 61 Rev 8 UNIT 1 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 39 (Continued)

c. Check MSlVs on intact S/Gs - OPEN.

c. Perform the following:

d.

- Check "STEAM DUMP SELECT' - IN STEAM PRESSURE MODE.

1) Reset Main Steam Isolation signals:

a) Main Steam Isolation b) SMPORVs.

c) MSlV Bypass Valves

2) IF intact S/G MSlVs required closed to isolate leak, THEN GO TO RNO for Step 39.f.

3) Place "STEAM DUMP SELECT' in steam pressure mode.

4) Place "STM PRESS CONTROLLER" in manual and close.

5) Open MSlV bypass valws on intact S/Gs to equalize pressure across MSIVs.

6) WHEN pressure equalized, THEN:

a) Open all MSlVs on intact SIGs.

b) Close all MSlV bypass valves.

c) Perform Steps 39.e and 39.f.

7) W D S t e p 40.

d. Perform the following to place steam dumps in steam pressure mode:

- I) Place "STM PRESS

2) Adjust "STM PRESS CONTROLLER" in manual.

CONTROLLER output to equal "STEAM DUMP DEMAND signal.

3) Place "STEAM DUMP SELECT in steam pressure mode,

PAGE NO 42 of 61 MNS EP/1 /A/5000/ECA-1 1 LOSS OF EMERGENCY COOLANT RECIRC lJNIT I Rev 8 ACTlONiEXPECTED RESPONSE RESPONSE NOT OBTAINED 39 (Continued) e WHEN "P-12 LO-LO TAVG" status light (ISI-18) lit, THEN place steam dumps in bypass interlock

f.

Dump steam to condenser from intact S/G s.

f.

Perform the following:

1) Dump steam using intact S/G(s) SM PORVs.

2) ;F ally intact S/G SM FGRV ciosed, THEN dump steam as follows:

a) Dispatch operator to operate intact S/G(s) SM PORV.

b) E any intact SIG SM PORV is unavailable, THEN evaluate using the following to dump steam:

Run TD CA Pump

- Use steam drains PER EP/I/A/5000/G-l (Generic Enclosures), Enclosure 19 (SIG Depressurization Using Steam Drains).

3) E no intact SIG available AND ND not in RHR mode, THEN use faulted S/G.

MNS UNIT I EP/l/A/5000/ECA-l.l ACTION/EXPECTEO RESPONSE LOSS OF EMERGENCY COOLANT RECIRC RESPONSE NOT O B T A I N E D 1

PAGE NO.

43 of 61 Rev. 8

d. Check H2 igniters - ON.

d. WHEN the following conditions met, THEN place H2 igniters in service:

- NFAHUsoff

- H2 concentration less than 6%

e. Check H2 concentration - LESS

- e. Dispatch operator to place H2

- THAN 0.5%.

recombiners in service PER EP/l/Al5000/G-1 (Generic Enclosures), Enclosure 4 (Placing H2 Recombiners In Service).

- 41.

Consult station management staff for further actions.

It I

I 4

t 44 of 61 Rev. 0 PAGE No.' I MNS.

LOSS OF EMERGENCY COOLANT RECIRC - Page 1 of 1 EP/llA/5000/ECA-I.1 UNIT 1 Foldout I

J

1.

Emergency Coolant Recirc Capability Restoration:

WHEN Cold Leg Recirc capability is restored, THEN GO TO Step 2.f in body of this procedure.

2.

ECCS Suction Monitoring Criteria:

E FWST level goes below "FWST LEVEL LO-LO" alarm setpoint (33 inches), AND NS pumps are taking suction from the FWST, THEN:

a. Reset Containment Spray.

b. Stop both NS pumps.

E suction source is lost to any NV, NI. ND, or NS pump, THEN stop pump.

FWST level goes below 20 inches, THEN stop all pumps taking suction from the FWST.

3.

CA Suction Sources:

CA Storage Tank (water tower) goes below 1.5 ft, THEN perform EP/I/A/5000/G-l (Generic Enclosures), Enclosure 20 (CA Suction Source Realignment).

M I

N I

M U

M S

I I

F L

0 W

R A

T E

G P

M MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

51 of61 - Page 1 of 1 EP/l/A/500O/ECA-l 1 Rev. 8 600 500 400 300 200 100 0

10 4

100 1000 T I M E AFTER REACTOR T R I P ( M I N U T E S )

10000

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 The MSSVs shall be OPERABLE as specified in Table 3.7.1-1 and Table 3.7.1-2.

APPLICABILITY:

MODES 1.2, and 3.

ACTIONS CONDITION A.

One or more required MSSVs inoperable.

McGuire Units 1 and 2 REQUIRED ACTION A.l Reduce power to less than or equal to the applicable

% RTP listed in Table 3.7.1-1.

AND A.2 Reduce the Power Range Neutron Flux High Trip Setpoints to the % RTP value listed in Table 3.7.1-1.

3.7.1-1 L

I_

COMPLETION TIME 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 4 hours (continued)

Amendment Nos. 184/166

MSSVs 3.7.1 ACTIONS (continued)

CONDITION B.

Required Action and associated Completion Time not met.

OR One or more steam generators with less than two MSSVs OPERABLE.

REQUIRED ACTION B.l Be in MODE 3.

AND 8.2 Be in MODE 4.

I COMPLETION TIME I

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.1.1

________________________________NOTE Only required to be performed prior to entry into MODE 2.

Verify each required MSSV lift setpoint per Table 3.7.1-2 in accordance with the Inservice Testing Program.

Following testing, lift setting shall be within 21%.

FREQUENCY In accordance with the Inservice Testing Program McGuire Units 1 and 2 3.7.1 -2 Amendment Nos. 184/166

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus Maximum Allowable Power Range Neutron Flux High Setpoints in Percent of RATED THERMAL POWER MSSVs PER STEAM POWER RANGE NEUTRON GENERATOR REQUIRED FLUX OPERABLE I HIGH SETPOINTS (% RTP) 5 58 5 39 5 19 Table 3.7.1-2 (page 1 of 1)

Main Steam Safely Valve Lift Settings VALVE NUMBER I LIFTSETTING STEAM GENERATOR I

1170 I

sv-20 SV-14 SV-8 sv-2 sv-21 SV-15 sv-9 sv-3 sv-22 SV-16 sv-10 sv-4 SV-23 sv-17 sv-11 sv-5 SV-24 sv-10 sv-12 SV-6 1190 1205 1220 1225 McGuire Units 1 and 2 3.7.1 -3 Amendment Nos. 184/166

0 O

N 0

w O

n 0

r rn 2 2

v 5 r

A w

o W

r n o 8

U 0

0, 0

a 0

0 0

VOLUME (GALLONS) -

O N

D 0

0 0

0 C

0 0

0 C

0 0

0 C

0 N

D 0

0 0

8

Organization 5.2 5.2 Organization (continued) 5.2.2 Unit Staff The unit staff organization shall include the following:

a.

A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4.

A total of three non-licensed operators are required for the two units.

At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2,3, or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the controi room.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.9 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

A Radiation Protection Technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

Administrative procedures shall be developed and implemented to limit the working hours of station staff who perform safety related functions (e.g., licensed SROs, licensed ROs, radiation protection technicians, auxiliary operators, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day with alternating 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and 36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months weeks while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or plant modification, on a temporary basis the following guidelines shall be followed:

1.

b.

c.

d.

e.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time; (continued)

McGuire Units 1 and 2 5.2-2 Amendment Nos. 184/166

, Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

2.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period, all excluding shii turnover time; A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time; Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

3.

4.

Any deviation from the above guidelines shall be authorized in advance by the Station Manager or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to ensure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

f.

The Operations Manager shall hold or have held an SRO license.

g. The Shift Technical Advisor (STA) shall provide advisory technical support to the Control Room Senior Reactor Operator (CRSRO) in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

I I

(continued) 213 and 194 McGuire Units 1 and 2 5.2-3

(1) ID No RP/O/N5700/004 Duke Power Company

~~

~~-

~

017

~~

PROCEDURE PROCESS RECORD Revision No Reviewed By Reviewed By (8) Temporary Approval (it necessary)

PERFORMANCE (Compare with dontrol Copy6vefy 14 calendar days while work is being performed.)

Date

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Date Date (10) Compared with Control Copy

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Compared with Control Copy Compared with Control Copy

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~~~~~~~~~

~~~~~

~~~~

(1 1) Date@) performed

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~~~~~~~

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~~~~~

Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification 0

N/A 0

Yes 0

Yes 0 N/A Required enclosures attached?

0 Yes Yes Check lists and/or blanks initialed. signed, dated or filled in NA, as appropriate?

0 N/A 0

N/A Data sheets attached. completed, dated and signed?

Charts, graphs, etc. attached, dated. identified, and marked?

0 Yes 0 N/A Procedure requirements met?

Verified By Procedure Completion Approved (1 4) Remarks (attach additional pages. i f necessary)

Date Dare

Duke Power Company McGuire Nuclear Station General Emergency Reference Use Procedure No RP/O/A/5700/004 Revision No.

017 3ectronic Reference No MCOOJSM7

RP/O/A/5700/004 Page 2 of 5 General Emergency

1. Symptoms Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity.

2. Immediate Actions NOTE:

The Immediate Actions and part of the Subsequent Actions have been separated into position specific enclosures to enhance timely completion and consistent execution.

2.1 The following Enclosures should be given to the appropriate personnel:

The OSM should execute Enclosure 4.9 (OSM Immediate and Subsequent Actions) in a timely manner.

The WCC SRO, or another SRO designated by the OSM should execute Enclosure 4.10 (WCC SRO Immediate and Subsequent Actions) in a timely manner.

The STA should execute Enclosure 4.1 I (STA Immediate and Subsequent Actions) in a timely manner.

RP/O/N5700/004 Page 3 of 5

3. Subsequent Actions 3.1 Follow-up Notifications

~~~

NOTE: E changes to the initial Protective Action Recommendations are recognized and approved by the Emergency Coordinator, these changes shall be transmitted to the offsite agencies within 15 minutes. (PIP-M-00-02138) 3.1. I Assess protective action recommendations made to the State and Counties in the previous notification. Refer to Enclosure 4.2, page 1 of 4.

The Emergency Coordinator shall make follow-up notifications to State and County authorities utilizing Enclosure 4.1 (Emergency Notification Form):

- Every hour until the emergency is terminated

- If there is any significant change to the situation

- As agreed upon with &individual agency. Documentation shall be

__ 3. I.2 OR OR -

maintained for any agreed upon schedule change and the interval shall not be greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to any agency.

~

3.1.3 Complete Enclosure 4.1 (Emergency Notification Form) in accordance with.S, Section 1.

Make follow-up notification lo State and County authorities using the Emergency Notification Form in accordance with Enclosure 4.5. Section 2.

__ 3.1.4

RP/O/A/5700/004 Page 4 of 5 NOTE:

A TSC preprogrammed fax button is available on the Control Room fax machine.

IF changes to the initial Protective Action Recommendations are recognized during the turnover, the turnover should not be completed until the Control Room transmits this notification to the offsite agencies. (PIP-M-0-00541)

--_I

__ 3.2 Ensure completion of Enclosure 4.7 (Emergency Coordinator / Emergency Operations Facility Director Turnover Checklist) prior to turnover of Emergency Coordinator responsi bi lities OR -

~

Fax turnover sheet to the TSC

___ 3.4 In the event that a worker's behavior or actions contributed to an actual or potential substantial degradation of the level of safety of the plant (incidents resulting in an Alen or higher emergency declaration), the supervisor must consider and establish whether or not a for cause drug/alcohol screen is required. The FFD Program Administrator or designee is available to discusslassist with the incident.

3.5 Protective Actions Onsite

__ 3.5.1 Evacuate non-essential personnel from the sire after all personnel have been accounted for via Site Assembly. Refer to RP/O/N5700/0I 1 (Conducting a Stte Assembly, Site Evacuation or Containment Evacuation).

__ 3.5.2 a situation which is immediately hazardous to life or valuable property exists, THEN evaluate potential dose rates by one of the following methods:

a.

b.

Assess area monitors Complete Enclosure 4.8 (Request for Emergency Exposure), prior to dispatch of emergency workers if emergency situation precludes documentation.

Contact RP Shift at Ext. 4282

__ 3.5.3

RP/O/A/57001004 Page 5 of 5 3.6 Using Section D of the Emergency Plan (EAL Basis). assess the emergency condition:

3.6.1 Remain in a General Emergency, OR 3.6.2 Terminate the emergency. REFER TO RP/O/A/5700/012 (Activation of the Technical Support Center [TSC)), Enclosure 4.19 for termination criteria.

3.7 Termination Notifications NOTE.6 has instructions for completion and transmission of termination notifications.

__ 3.7. I Complete Enclosure 4.1 (Emergency Notification Form) in accordance with.6, Section 1 Make termination notification to State and County authorities using the Emergency Notification Form in accordance with Enclosure 4.6, Section 2.

__ 3.7.2

4. Enclosures 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 4.10 Emergency Notification Form.

Guidance for Offsite Protective Actions Initial Notification Completion~ransmission NRC Event Notification Worksheet Follow-up Notification CompletionlTransmission Termination Notification Completion/Transmission Emergency Coordinator I Emergency Operations Facility Director Turnover Checklist Request for Emergency Exposure OSM Immediate and Subsequent Actions {PIP 0-M97-4638)

WCC SRO Immediate and Subsequent Actions {PIP 0-M97-4638) 4.1 I STA Immediate and Subsequenl Actions {PIP 0-M97-4638)

5.

EMERGENCY CIASSIFICATION:

NOTlFlCAllON OF UNUSUAL M N T ALERT OSITE AnEA EMERGENCY OGENERAL EMERGENCY -

8. PLAAT CONDITION BIMPROVING a S T A B L E ODEGRADING

- 1 I-

~ p % P O W E R ItlltlRJ mm 7T YI

9. REACTOR STATUS. T SHUTDOWN:

TIMEIDATE:

10. EMERGENCY RELEASE(S):

"ONE (Go 10 item 14.)

@'OTENTIAL (GO TO ITEM 14.) alS OCCURRING a H

A S

OCCURRED

-11.

TYPE OF RELEASE:

OELFVATED GROUND LEVEL gAIRBORNE:

Started:

riir-1

-1

-E-/-

Slopped:

yII,_ I 1-1-

(tytunl -J-&--

1m lKlSlcf"l

-lT&-l-Slopped:

<~

H L I D U I D :

Started:

"12.

RELEASE MAGNITUOE:

OCURlES PER SEC. O C U R l E S NORMAL OPERATING LIMRS: O B E L O W QABOVE NOBLE GASES

~ I O D I N E S

!CJPARTICULATES OTHER PROJECTION TIME:

,Eane,")

"13. ESTIMATE OF PROJECTED OFFSlTE DOSE:

ONEW OUNCHANGED TEDE Thyroid CDE rnrern rnrern ESTIMATED OURATION:

HRS.

SITE BOUNDARY 2 MILES 5 MILES 10 MILES "14. METEOROLOGICAL DATA:

WIND DIRECTION (trom) n S P E E 0 (mph)

15.

~ S T A B l L l T Y CLASS

@'RECIPITATION (type)

RECOMMENDED PROTECTIVE ACTIONS:

n N 0 RECOMMENDED PROTECTIVE ACTIONS EVACUATE -

SHELTER IN-PLACE

~ O M E R

- ~ _ _

Emergency It items 8-14 have no1 changed, only items 1-7 and 15-16 ale required 10 be compleled.

Inlormation may not be available on initial notifications.

.1 JiP/O/A/S 700/004 Page 2 of 2 GOVERNMENT AGENCIES NOTIFIED R w r d me -e.

dale. Une and a w e s WJskd'

1.

~

(name)

NC Slate (ag?J EOC se( S q 314 7dalo)

( b m )

EOC &#Line (919) 73s3943 6

(name)

Calawba County

geqJ WP sel SQ I18 (dale)

( O m )

W P B ~ X I W (828)46FJ111

.2 Guidance for Off-site Protective Actions RP/O/A/5700/004 Page 1 of 4 General Emergency Declared Yks I

URGENT Evacuate zones L, B. M. C. N. A, D, 0, R I

I I Shelter zones E. F, G, H, I. J, K, P, Q. S I

1 Recommend evacuation of 2 mile radius & 5 miles downwind. Recommend in-place shelter for all zones not evacuated out to I O miles (See Enclr.~ re 4.2. page 3 of 4) 7 I

No Containment?

(See Enclosure 4.2. page 2 Off-site doses projected by RP to exceed Protective Action Guides'?

Recommend protective actions in accordance with the Protective Action Guides.

(See Enclosure 4 2. page 3 of 4)

Recommend evacuation of 5 mile radius &

10 miles downwind. Recommend in-place shelter for all zones not evacuated out to IO miles.

(See f;nclosure 4.2. page 2 of 4)

R PIOIN5 lOOlOO4 Page 2 of 4.2 Guidance for Off-site Protective Actions GUIDANCE FOR DETERMINATION OF GAP ACTIVITY NOTE:

Fission product inventory inside containment is greater than gap activity if the containment radiation level exceeds the levels in the table below.

~

If the OAC is available, call up the following computer points based on need:

Unit 1 OAC MlA0829 IEMFSIA MIA0835 IEMFSIB TIME !.ITER SHUTDOWN (HOURS) 0 0-2 2-4 4-8

> 8 Unit 2 OAC M2A0829 2EMFS 1 A M2A083S 2EMFS I B CONTAINMENT MONITOR READING (RIHR)

EMF SIA or SIB (100% GAP Activity Release) 2,340 864 624 450 265 Protective Action Zones Determination

.2 Dose Equivalent CEDE) c I rem

> I rem Guidance for ON-site Protective Actions Equivalent (CDE)

< S rem ZSrem Thyroid Recommendation No Protective Action is required based on qrojected dose.

Evacuate affected zones and shelter the remainder of the 10 mile EPZ not evacuated.

RP/O/A/S 700l004 Page 3 of 4 i

i GUIDANCE FOR OFFSITE PROTECTIVE ACTIONS PAGs (Projected Dose)

Total Effective 1 Committed Dose 1 Protective Action Guides (PAGs) are levels of radiation dose at which prompt protective actions should be initiated and are based on EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.

RPf o/N57oO/OO4 Page 4 of 4.2 Guidance for Off-site Protective Actions McGUIRE PROTECTIVE ACTION ZONES (2 and 5 mile radius, inner circles) 10 MILE EPZ 0-I 22.10 N

.3 Initial Notification Cornpletioflransmission R P/~/At57#/004 Page 1 of 9

1. Completion of the Emergency Notification Form NOTE:

ONLy Items 1 - IO, 15 and 16 are required.

Items 1 1 - 14 may be skipped.

I 1.1 Complete Enclosure 4.1 (Emergency Notification Form) as follows:

Message #s should be sequentially numbered throughout the dnlllemergency.

NOTE:

~

Item 1 Check A for Drill O R B for Actual Emergency AND Check INITIALAND Write in riessage number.

NOTE:

Certain events could occur at the plant site such that both units are affected. These may include:.3 (Abnormal Rad LevelsIRadiological Effluent), Enclosure 4.6 (FiresExplosions and Security Events) and Enclosure 4.7 (Natural Disasters, Hazards and Other Conditions Affecting Plant Safety) from RP/O/A/5700/000, (Classification of Emergency). Consider this when completing the unit designation on line 2 of the Emergency Notification Form. {PIP 0-M97-4638)

REPORTED BY: is the Communicators name.

t

~

Item 2 Write in the unit(s) AND Communicators name.

NOTE:

Information for Items 3 and 4 will be completed dunng transmission of the Emergency Notification Form.

I

~

Item 3

__ Item 4

~

Item 5 Check D for GENERAL EMERGENCY.

Wnte in the transmittal time AND date.

Wnte in appropriate number AND codeword.

~

Item 6 Check A for Emergency Declaration At: AND Write the time AND date the classification was declared.

.3 Initial Notification CompletioruTransmission RP/O/A/5700/M)4 Page 2 of 9 NOTE:

Reference RP/O/A/5700/000, (Classification of Emergency)

Item 7 Enter EAL Number and Emergency Description of the reason for declaring the emergency classification (in layman's terms. if possible). DO NOT use system abbrcviations, acronyms orjargon which may cause confusion. Instead, write out the description in long hand. Be sensitive to the fact that certain descriptive technical terms may elicit unanticipated reactions from others. {PIP 0-M98-2065 1 Check the appropriate plant condition. (PIP O-M97-4210 NRC-I )

.A Improving: Emergency conditions are improving in the direction of a Item 8 lower classification or termination of the event.

.B Stable: The emergency situation is under control. Emergency core cooling systems, equipment, plans. etc.. are operating as designed.

.C Degrading: Given current and projected plant conditions/equipment status. recovery efforts are not expected to prevent entry into a higher emergency Classification or the need to upgrade offsite Protective Action Recommendations.

Item 9 Check A SHUTDOWN AND write the time and date of Reactor Shutdown Check B AND wnte in the Reactor Power level

.3 Initial Notification Completioflransmission RP/O/A/5700/004 Page 3 of 9 1 NOTE:

1. An emergency release is any unplanned, quantifiable discharge to the environment associated with a declared emergency event. (This definition is based on an NRC commitment made on 11/30/90 following McCuire's Steam Generator Tube Rupture.) (PIP O-M97-4256)

2. Notify the OSM if box C or box D is checked.

3. Base the determination of emergency release on:

EMF readings, containment pressure and other indications, a

field moiiitoring resulis.

knowledge of the event and its impact on systems operation and resultant release paths.

4. An emergency release is occurring if any one or more of the following bulleted conditions are met associated with a declared emergency:

Either containment particulate, gaseous, iodine monitor (EMFs 38. 39 andor 40) readings indicate an increase in activity.

Containment monitor (EMFs 51A and/or 51B) readings indicate greater than I.SR/hr, u

r containment pressure is greater than 0.3 psig, An actual containment breach is known to exist.

Unit vent paniculate. gaseous, iodine monitor (EMFs 35.36, andor 37) readings indicate an increase in activity.

Condenser air ejector exhaust monitor (EMF 33) or other alternate means indicate Steam Generator tube leakage.

Confirmed activity in the environment reported by Field Monitoring Team(s)

Knowledge of the event and its impact on systems operation and resultant release paths I

OR AND OR -

I i

Item IO Check the appropriate box for emergency release.

NONE: clearly no emergency release is occurring or has occurred A

B POTENTIAL: discretionary option for the EC or EOFD.

C IS OCCURRING: meets the specified conditions.

D HAS OCCURRED: previously met the specified conditions.

~~/0/~15700/004.3 Initial Notification Completionransmission Page 4 of 9 Item 15 Check B AND write affected zones for evacuation AND Check C AND write the letter designation for all other zones not evacuated.

Have the Emergency Coordinator approve the message AND Write in the time AND date the message was approved.

__ Item 16

2. TRANSMISSION OF THE EMERGENCY NOTIFICATION FORM NOTE:

1. All initial notifications are verbal. Avoid using abbreviations orjargon likely to be unfamiliar lo the State and Counties. If any information is not available or not applicable, write out "Not Available" or "Not Applicable" in the margin or other space as appropriate. Do not abbreviate "N.A.".

2. The backup means of communications are the Bell line or County Emergency Response Radio.

RP/O/A/S700/014. Enclosure 4. I is available for needed backup numbers.

3. Refer to page 6 of 9 of this Enclosure for instructions on how to use the County Emergency Response Radio if selective signaling or Bell line is not available.

2.1 2.2 Use the Selective Signaling telephone by dialing

I and depressing the push to talk button Selective Signaling Group Call fails, go to RP/O/A/S700/014. Enclosure 4.1 for manual selective signaling numbers.

NOTE:

The time when the first party is contacted should be recorded on Line 3.

I 2.3

~

2.4 2.5 2.6 As the State and Counties answer, check them off on the back of the notification form. At least one attempt using the individual selective signaling code must be made for any missing agencies. Proceed with the notification promptly following an attempt to get missing agencies on the line.

Check the State and Counties arc on the line, document this [!.ne in item #3 on the form. This time should not exceed 15 minutes from the time of declaration (Item # 6).

Tell them you have an emergency notification from the McGuire Control Room and to get out the Emergency Notification Form.

Read the complete message slowly. line by line. heginning with Item # I, allowing ample time to copy.

.3 Initial Notification Completioflransmission RP/O/A/5700/004 Page 5 of 9 NOTE:

Refer to page 7 of 9 of this enclosure for the authentication codeword list.

1 2.7

__ 2.8

_ _ ~

2.9 2.10 When you reach item #4, ask the State or a County to authenticate the message. The agency should give you a number and you should provide the appropriate codeword. Write the number and codeword on the form.

After communicating the initial message, ask if there are any questions. Record individuals names and times on the back of the form. This time is the same time as Item #3.

After verba!ly transmit!ing !he message. FAX 3 ccpy (front page only) to thc agencies. Refer tu pages 8 of 9 and 9 of 9 of this Enclosure for FAX operation.

Continuous attempts to contact missing agencies must be made if unable to complete the notification per step 2.3. Document the time these agencies were contacted on the back of the notification form.

A.3 Initial Notification Completioflransmission RP/O/A/5700/M)4 Page 6 of 9 COUNTY EMERGENCY RESPONSE RADIO NOTE:

This radio will onlycontact the County warning points. The State canaot be contacted on this radio.

Have one of the Counties relay the message to the State.

Group Call:

___ I.

_- 2.

Press 20 to activate all County radio units.

When the ready light comes on, press the bar on the transmitter microphone and say:

"This is McGuire Contfol Room to all Counties, do you copy?"

Once all Counties respond, begin transmitting the message using step 2.3 through 2.10 of this enclosure.

Proceed with the ndification promptly following an attempt to get missing agencies on the air.

' ' W E :

RP/O/A/S700/014. Enclosure 4.1 is available for needed individual radio codes.

3.

If a County fails to respond on the group call, press their individual code on the encoder ;ind say:

"This is McGuire Control Room to (Agency you are calling). do you copy?"

Once the County responds, begin transmitting the message using step 2.3 through 2. IO of this enclosure.

- 4 After you have finished transmitting the message, conclude by saying:

"This is WQC700 base clear."

Continuous attemptsto contact missing agencies must be made if unable to complete the notification per step 2. Document the time these agencies were contacted on the hack of the notification form.

5.

.3 RP/O/A/5700/004 Initial Notification Completioflransmission Page 7 of 9 AUTHENTICATION CODEWORD LIST This page is left intentionally blank.

.3 Initial Notification Completioflransmission OPERATION OF THE FAX A. GROUPFAX RP/O/A/5700/004 Page 8 of 9

~

NOTE:

1. The FAX will dial each agency in sequence. If the FAX is busy, it will try again after completing the other calls.

2. This sends a FAX to all County Warning Points, State EOC, TSC. EOF. News Group and JIC.

__ I. Insert the Emergency Notification Form face down into the FAX.

2. Press GROUP FAX button.

~

3. Press "SENDIRECEIVE button B. INDIVIDUAL FAX

~

I.

Insert the Emergency Notification Form face down into the FAX

__ 2. Select location(s) to receive the fax:

Press NewsGroup PressTSC.

0 Press State of North Carolina EOC,

~

Press Mecklenburg County Warning Point,

~

Press Gaston County Warning Point.

0 Press Lincoln County Warning Point 0

Press Iredell County Warning Point.

Press Catawba County Warning Point 0

Press Caharms County Warning Point Press EOF, Press JIC.

3. WHEN the appropnatc individual location IS sclccied. THEN press ihe "SENDIRECTIVE" hutton.

.3 Initial Notification Cornpletioflransrnission R PIoIAl51 OOlOO4 Page 9 of 9 NOTE:

RP/O/A/5700/014, Enclosure 4.1 is available for needed manual FAX numbers.

1 C.

To send a FAX to as&&

location dialing manually:

~

1,

__ 2.

~

3.

Press "SENDIRECEIVE button.

Insert the document face down into the FAX.

Using the keypad, dial the number that you wish to call c

r

. urlUVATE EVENTTLVE & ZONE Rcmon I1 ENS 1-888-270-0173 u 17041-875-M)44 EVENT DATE FOWEWMODE BEFORE I

POWERlMODE AFTER

RP/OfNS700/004 Page 2 of 2.4 NRC Event Notification Worksheet I

I I

I PLANTSTACK CONDENSEW MAIN SlFAM LINE SG BLOWDOWN OTHER (EMF35, 36.37)

AIR UECrOR (UNW I-EMF24.25.26.27 (EMF 34)

S LlMrrS EXCEEDED Xc eqpmCi/ml

RP/01A/5700/004 Page 1 of 6.5 Follow-Up Notification Completio~ransmission

1. Completion of the Emergency Notification Form NOTE:

If items 8 - 14 have not changed from the previous message, only items I - 7, 15 and 16 are required to be completed. Avoid using abbreviations or jargon likely to be unfamiliar to the State and Counties. If any information is not available or not applicable. write out "Not Available" or "Not Applicable" in the margin or other space as appropriate. Do not abbreviate "N.A.".

Complete Enclosure 4.1 (Emergency Notification Form as follows):

1.1 NOTE:

Message #'s should be sequenrialiy numbered throughout the drilllemergency.

I Item 1 Check A for Drill OR B for Actual Emergency -

AND Check FOLLOW-UP AND Write in message number.

NOTE:

Certain events could occur at the plant site such that both units are affected. These may include:.3 (Abnormal Rad LevelslRadiological Effluent), Enclosure 4.6 (FiresExplosions and Security Events) and Enclosure 4.7 (Natural Disasters, Hazards and Other Conditions Affecting Plant Safety) from RP/O/A/5700/000, (Classification of Emergency). Consider this when completing the "unit designation" on line 2 of the Emergency Notification Form. ( P P 0-M97-4638)

REPORTED BY: is the Communicator's name.

__ Item 2 Write in the unit(s) AND Communicator's name.

NOTE:

Transmittal time is the time you FAX the form to the agencies.

Item 3 Item 4 Write in the transmittal time AND date.

Authentication is not required when faxing.

__ Item 5 Check D for GENERAL EMERGENCY.

__ ltem 6 Check A for Emergency Declaration At: AND Write the time AND date the classification was declared

R P / ~ / A I ~ ~ o o / o o ~

Page 2 of 6.5 Follow-Up Notification Completioflransmission

[ NOTE:

Reference RP/OlA/5700/000, (Classification of Emergency)

Item 7 Enter EAL Number and Emergency Description of the reason for declaring the emergency classification (in layman's terms, if possible). DO NOT use system abbreviations. acronyms or jargon which may cause confusion. Instead. write out the description in long hand. Be sensitive to the fact that certain descriptive technical terms may elicit unanticipated reactions from others. (PIP 0-M98-206S)

In addition. provide a description of changes in plant conditions since the last notification. Items to be considered for inclusion are as follows: [PIP 0-M98-2065) 0 0

k 0

0 0

Other unrelated classifiable events (for example, during an Alert, an event which, by itself would meet the conditions for an Unusual Event)

Major/Key Equipment Out of Service Emergency response actions underway Fire(s) onsite Flooding related to the emergency Explosions Loss of Offsite Power Core Uncovery Core Damage Medical Emergency Response Team activation related to the emergency Personnel injury related to the emergency or death Transport of injured individuals offsite - specify whether contaminated or not Site Evacuation/relocation of site personnel SaboteursllntruderslSuspicious devicesnhreats Chemical or Hazardous Material Spills or Releases Extraordinary noises audible offsite Any event causindrequinng offsite agency response Any event causing increased media attention Remember to "close the loop" on items from previous notifications.

RPIOIN57001004 Page 3 of 6.5 Follow-Up Notification Comple tioflransmission Item 8 Check the appropriate plant condition. {PIP M-097-4210 NRC-1)

.A. Improving: Emergency conditions are improving in the direction of a lower classification or termination of the event.

-6. Stable: The emergency situation is under control. Emergency core cooling systems, equipment, plans, etc., are operating as designed.

.C. Degrading: Given current and projected plant conditions/equipment status, recovery efforts are not expected to prevent entry into a higher emergency classification or the need to upgrade offsite Protective Action Recommendations.

Item 9 Check A SHUTDOWN -

AND write the time and date of Reactor Shutdown OR -

Check B AND write in the Reactor Power level

RP/O/A/S 700/004 Page 4 of 6.5 Follow-Up Notification Completiodl'ransmission IYOTE:

1. An emergency release is any unplanned, quantifiable discharge to the environment associated with a declared emergency event. (This definition is based on an NRC commitment made on I1/30/90 following McGuire's Steam Generator Tube Rupture.) (PIP 0-M97-4256 1

2. Notify the OSM if box C or box D is checked

3. Base the determination of emergency release on:

EMF readings.

containment pressure and other indications, ficld moilitonrig results, knowledge of the event and its impact on systems operation and resultant release paths.

4. An emergency release is occurring if any one or more of the following bulleted condition!

are met associated with a declared emergency:

m r

containment particulate, gaseous. iodine monitor (EMFs 38, 39 andor 40) readings indicate an increase in activity.

Containment monitor (EMFs 51A and/or 51B) readings indicate greater than 1.SWhr.

Either containment pressure is greater than 0.3 psig.

An actual containment breach is known to exist.

Unit vent particulate, gaseous, iodine monitor (EMFs 35, 36, and/or 37) readings indicate an increase in activity.

Condenser air ejector exhaust monitor (EMF 33) or other alternate means indicate Steam Generator tube leakage.

Confirmed activity in the environment reported by Field Monitoring Team(s)

Knowledge of the event and its impact on systems operation and resultant release paths OR AND OR

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Item I O Check the appropriate box for emergency release.

A B

POTENTIAL: discretionary option for the EC or EOFD.

C IS OCCURRING: meets the specified conditlons.

D HAS OCCURRED: previously met the specified conditions.

NONE: clearly no emergency release is occumng or has occurred

.5 RP/O/A/5700/004 Follow-Up Notification Completioflransmission Page 5 of 6

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1.2 follow-up notification is due and information for Items 1 I through 14 cannot be obtained from RP shift, THEN mark each item Not Available and go to Item 15.

Item I 1 Check GROUND LEVEL AND Check A for AIRBORNE Write in the time AND date the release started &NJ stopped if available B for LIQUID AND hem 12 Check CURIES PER SECOND AND Check BELOW Check the appropriate blocks A, B, C, D AND write in the value(s).

ABOVE normal operating limits AND NOTE:

If unchanged from the previous notification, the information does not have to be repeated.

Item 13 Check NEW UNCHANGED AND Write in the projection time Write in the estimated duration AND Write in the TEDE and Thyroid CDE values.

Check A, B. C, D w p r o v i d e values foreach.

Check B AND write affected zones for evacuation Item 14 Item IS

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AND -

Check C AND write the letter designation for all other zones not evacuated Have the Emergency Coordinator approve the message a Write in the time AND date the message was approved.

Item 16

.5 Follow-Up Notification Cornpletioflransmission

2. Transmission of the Emergency Notification Form R P/~/N5700/004 Page 6 of 6 2.1 2.2 2.3 2.4 5

For routine, follow-up notifications, FAX a copy of the notification form instead of verbally transmitting the message (front page only). This applies only if the message does not involve a change in the emergency classification or the protective action recommendations or a termination of the emergency. Call each agency to verify they received the message.

Insert !he Emergency Notification Form (front page nn!y) face down in!o the F.4X Press "GROUP FAX button.

Press "SENDRECEIVE" button.

IF programmed functions fail, THEN go to RP/O/A/5700/014. Enclosure 4.1 for manual FAX numbers.

Ensure the State and Counties received the FAX by calling them.

Ask if there are any questions on the Emergency Notification Form, then record individuals' names and times on the back of the form.

.6 Termination Notification Completioflransmission rgency Notification Form

1. c o ipleti n f the Em RP/O/A/5700/004 Page I of 6 I NOTE:

A termination message should be marked as FOLLOW-UP on the Emergency Notification Form. I 1. I Complete Enclosure 4.1 (Emergency Notification Form) as follows:

Item 1 Check A for Drill QlJ B for Actual Emergency AND Check FOLLOW-UP AND Write in message number.

NOTE:

Certain events could occur at the plant site such that both units are affected. These may include:.3 (Abnormal Rad LevelslRadiological Effluent), Enclosure 4.6 (FiresExplosions and Security Events) and Enclosure 4.7 (Natural Disasters, Hazards and Other Conditions Affecting Plant Safety) from RP/O/A/5700/000. (Classification of Emergency). Consider this when completing the unit designation on line 2 of the Emergency Notification Form. (PIP 0-M97 46381 REPORTED BY: is the Communicators name.

Item 2 Write in the unit(s) AND Communicators name NOTE:

Information for Items 3 and 4 will be completed dunng transmission of the Emergency Notiflcatlon Form Item 3

- Item 4 Item 5 Item 6 Write in the transmittal time I\\ND date Write in appropriate number AND codeword Check D for GENERAL EMERGENCY Check B forTermination At: AND Write the time AND date the classification was terminated.

Have the Emergency Coordinator approve the message AND Write in the time AND date the message was approved.

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Item 16

.6 Termination Notification Completion/Transmission RP/O/N5700/004 Page 2 of 6

2. Transmission of the Emergency Notification Form NOTE:

1. All termination notifications are verbal. Avoid using abbreviations orjargon likely to be unfamiliar to the State and Counties. If any information is not available or not applicable, write out "Not Available" or "Not Applicable" in the margin or other space as appropriate. Do not abbreviate "N.A.".

2. The backup means of communications are the Bell line or County Emergency Response Radio.

RP/O/A/5700/014, Enclosure 4.1 is available for needed backup numbers.

3. Refer to pa^ 3 of 6 of this enclosure for instructions on how to use the County Emergency Response Radio if selective signaling or Bell line is not available.

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2.1

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2.2 2.3 k

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2.4

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2.5

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2.6 Use the Selective Signal telephone by dialing

I and depressing the push to talk button IF Selective Signaling Group Call fails, THEN go to RP/O/A/5700/014, Enclosure 4.1 for manual selective signaling numbers.

As the State and Counties answer. check them off on the back of the notification form. At least one attempt using the individual selective signaling code must be made for any missing agencies Proceed with the notification promptly following an attempt to get missing agencies on the line.

Check the State and Counties are on the line, document this time in item #3 on the form Tell them you have an emergency notification from the McGuire Control Room and to get out the Emergency Notification Form.

Read the complete message slowly. line by line, beginning with Item # I, allowing ample time to COPY.

NOTE:

Refer to page 4 of 6 of this Enclosure for the authentication codeword list.

When you reach item #4. ask the State or a County to authenticate the message. The agency should give you a number and you should provide the appropriate codeword. Write the number and codeword on the form.

After communicating the message. ask if there are any questions. Record individuals' names and times on the back of the form. This time is the same time as Item #3.

After verhally trmsmitting the message, FAX ;I copy (front page only) to the ascncies. Refer to page 5 o l 6 and 6 0 1 6 of this enclosure lor K;\\X o p w i t i o n.

2.7 2.8 2.9

RP/O/Al5700/004 Page 3 of 6.6 Termination Notification Completion/Transmission

2. IO Continuous attempts to contact missing agencies must be made if unable to complete the notification per step 2.3. Document the time these agencies were contacted on the back of the notification form.

COUNTY EMERGENCY RESPONSE RADIO NOTE:

This radio will only contact the County warning points. The State radio. Have one of the Counties relay the message to the State.

be contacted on this Group Call:

I.

Press 20 to activate a11 County radio units

2.

When the ready light comes on, press the bar on the transmitter microphone and say:

"This is McGuire Control Room to a11 Counties, do you copy?"

Once all Counties respond, begin transmitting the message using step 2.3 through 2.10 of this enclosure.

Proceed with the notification promptly following an attempt to get missing agencies on the air.

NOTE:

RP/O/N5700/014, Enclosure 4.1 is available for necded individual radio codes.

3.

If a County fails to respond on the group call, press their individual code on the encoder and say:

"This is McGuire Control Room to (Agency you are calling), do you copy'?"

Once the County responds, hegin transmitting the message using step 2.3 through step 2.10 of this enclosure.

4.

After you have finished transmitting the message. concluue by saying:

"This i s WQC7M) base clear."

Continuous attempts to contact missing agencies must be made if unable to complete the notification per Step 2. Document the time these agencies were contacted on the back of the notification form.

_- 5.

.6 Termination Notification Completioflransmission AUTHENTICATION CODEWORD LIST This page is left intentionally blank.

RP/O/A/5700/004 Page 4 of 6

.6 Termination Notification Completio~ransmission RPfOfN5700f004 Page 5 of 6 OPERATION OF THE FAX A. GROUPFAX NOTE:

1. The FAX will dial each agency in sequence. If the FAX is busy, it will try again after completing the other calls.

2. This sends a FAX lo all County Warning Points, State EOC. TSC. EOF. News Group and JIC.

~

1.

~

2.

Press "GROUP FAX" button.

~

3. Press "SENDIRECEIVE button.

Insert the Emergency Notification Form face down into the FAX.

B. INDIVIDUAL FAX

1.

2.

Insert the Emergency Notification Form face down into the FAX.

Select location(s) to receive the fax:

Press News Group.

Press TSC.

Press State of North Carolina EOC.

Press Mecklenburg County Warning Point Press Gaston County Warning Point.

Press Lincoln County Warning Point.

Press Iredell County Warning Point.

Press Catawba County Warning Point.

Press Cabarms County Warning Point.

Press EOF.

Press JIC.

3. WHEN the appropnate individual location 1'i selecied,.m press the "SENDIRECEIVE hutton.

.6 Termination Notification Completioflransmission OPERATION OF THE FAX RP/O/N5700/004 Page 6 of 6 NOTE:

RP/O/A/5700/014, Enclosure 4.1 is available for needed manual FAX numbers.

I C. To send a FAX to a &

location dialing manually:

~

1. Insert the document face down in !he FAX.

__ 2. Using !he keypad. dia! the numbei that you wish to call.

__ 3. Press "SEND/RECEIVE" button.

__-.7 Emergency Coordinator / Emergency Operations Facility Director Turnover Checklist RP/O/A/5700/004 Page 1 of 1 UNITIS) AFF'ECTED UI U2

{ PIP-M-99-3800)

POWER LEVEL NCS TEMP NCS PRESS I

DATE:

TIME:

u-l U.2 TSC ACllVATEDAT:

EOF ACTIVATED AT:

NOUE DECLARED AT:

,\\LERT DECLARli.D AT:

SAE DECLARED AT, G.E. DECL,\\RED,\\T:

REASON FOR EhlER TIASS:

YES NO TIME I.OCI\\TION OR COhIhlENTS SITE EVA(:. INON-ESSEN.1 SITE EVAC. (ESSENTIAL)

OTHER OFFSITE,\\GENCY INVOI.VEMENF niEDic,\\L FIRE POI.I('E NUMBER NUhlBER ASSEM.

DEPLOYED FIELD \\IOV. T E m s ZONFS ZONES EVAC sllk:LTEm:l>

PARS:

YFS NO RELEASE IN PROGRESS RELE.\\SE PI\\TII\\VAY CONTr\\lN3lENT PRESSURE PSlG WINDSPEED WIND DIRECTION NUMBER TIME LhST h1ESSAT.E SENT:

NEXT MESSAGE DUE:

NOTE: EOF ('Ohlhll~NlChTION ('IIECKS SII0UI.I) RE ('0hlPI.ETEI) PRIOR TO,\\CTIV,\\TIN(; ~TllE EOF.

R P/o/A/5 7oO/oO4 Page 1 of 1.8 Request for Emergency Exposure (a)

Protection of Large Protectioa of Largz (a) Excludes declared pregnant women (b) Includes skin and body extremities (c) Only on a volunteer basis to persons fully aware of the risks involved. All factors being equal. select volunteers above the age of 45 and those who normally encounter little exposure.

My signature indicates my acknowledgement that I have k e n informed that I may be exposed to the levels of radiation indicated above. I have been fully briefed on the task to be accomplished and on [he risks of this exposure.

I.

acknowledge this planned Emergency Exposure (RPM or designee, signature or note of verbal authorization Datemime I.

approve this planned Emergency Exposure 31 (Emergency Coordinator or EOF Director. signature or note of verbal authorization Datemime Subsequent Radiation Protection Action:

- Determine need for medical evaluation

- Initiate reporting requirements per I(K'FR?O

- ('opy to Individual's Exposure History File

.9 OSM Immediate and Subsequent Actions NOTE:

For drill purposes, state This is a drill. This is a drill.

Any plant phone in the Control Room horse shoe area or extension 4021 is programmed to access 710, site all call. {PIP 0-M98-2545!

L RP/O/A/5700/004 Page 1 of 4

1. Immediate Actions Initial

__ 1. I The Operations Shift Manager or designee SHALL ANNOUNCE the event over the plant P.A. system by performing the following:

I. 1.1 Turn on the outside page speakers.

I. I.3 I. 1.4 Repeat the preceding announcement one time.

Turn off the outside page speakers.

.9 RPIOlN5 7OOlOO4 OSM Immediate and Subsequent Actions Page 2 of 4 NOTE:

1.

Initial notification to the State and Counties be made within 15 minutes of fhe event declaration, using Enclosure 4.1..3 has instructions for completionltransmission of the Emergency

2.

~.

Notification Form J

1.2 The Emergency Coordinator shall recommend to offsite authorities in the initial notification the following:

NOTE:

I. To obtain the wind speed, use chart recorder IEEBCR9100. point #5 (Average Lower Wind Speed).

2. To obtain the wind Jirection. use chart recorder IEEBCR9100, point >t8 (Average Upper Wind Direction).

3. If either point on 1EEBCR9100 is unavailable. obtain needed data from one of the following sources in order of sequence:

A. DPC Meteorological Lab (8-594-0341)

B. National Weather Service in Greer. S.C. (864-879-1085 or 1-800-268-7785)

C. Catawha iquclear Station Control Room (8-831-5345).

NOTE: E changes to the initial Protective Action Recommendations are recognized and approved by the Emergency Coordinator, these shall be transmitted to the offsite agencies within 15 minutes. (PIP-M-00-01238)

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I.2. I Bcontainment radiation levels exceed the levels on Enclosure 4.2%

page 2 of4, Guidance for Determination of Gap Activity, w:

Evacuate the 5-mile radius AND 10 miles downwind as shown on Enclosure 4.2, page 2 of 4, Protective Action Zones Determination, using wind direction

- Shelter remaining zones as shown on Enclosure 4.2, page 2 of 4, Protective Action Zones Detcrniination. using wind direction.

RP/O/A/S700/004 Page 3 of 4.9 OSM Immediate and Subsequent Actions 1.2.2 Xcontainment radiation levels DO NOT exceed the levels on Enclosure 4.2, page 2 of 4, Guidance for Determination of Gap Activity, THEN perform one of the following:

IF wind speed less than or equal to S MF, THEN:

Evacuate zones L, B, M, C, N. A. D. 0. R AND Shelter zones E, F, G. H, I, J. K, P, Q, S.

OR -

IF wind speed greater than 5 MPH, THEN:

Evacuate the 2-mile radius AND S miles downwind as shown on Enclosure 4.2, page 3 of 4, Protective Action Zones Determination, using wind direction Shelter remaining zones as shown on Enclosure 4 2, page 3 of 4, Protective Action Zones Determination. using wind direction

___ I.3 valid trip 11 alarm occurs on any one of the following:

1 2 EMF36(L)

I EMF24,25,26,21 2 EMFIO, 11. 12, 13 THEN immediately contact RP shift at 4282 to perform HP/O/B/1009/029 (Initial Response On-Shift Dose Assessment).

E box C (IS OCCURRING) or box D (HAS OCCURRED) from Item 10 (EMERGENCY RELEASE) on Enclosure 4. I, (Emergency Notification Form) is checked, THEN immediately contact RP shift at 4282 to perform HPIOIB/1009/029 (Initial Response On-Shift Dose Assessment).

1.4

RP/O/N5700/004 Page 4 of 4.9 OSM Immediate and Subsequent Actions

2. Subsequent Actions NOTE:

Site Assembly is a required on-site protective action in response to an Alert or higher declaration.

2.1 a site assembly has not already bem initiated, THEN refer to RP/O/N5700/011 (Conducting a Site Assembly, Site Evacuation or Containment Evacuation) to evaluate and initiate a site assembly.

Augment shift resources to assess and respond to the emergency situation as needed GO TO Step 3.1 in the body of this procedure and continue with the prescribed subsequent

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2.2

__ 2.3 aCliGliS.

.10 WCC SRO Immediate and Subsequent Actions

1. Immediate Actions Initial NOTE:

I. Initial notification to the State and Counties must be made within 15 minutes of the event declaration, using Enclosure 4. I.

2. Enclosure 4.3 has instructions for completion/transmission of the Emergency Notification Form.

I. 1 The Emergency Coordinato: shall recommend io offsite authorities in the initial notitication the following:

NOTE:

1.

To obtain the wind speed, use chart recorder lEEBCX9100, point #S (Average Lower Wind Speed).

To obtain the wind direction. use chart recorder IEEBCR9100, point #8 (Average Upper Wind Direction).

If either point on lEEBCR9100 is unavailable. obtain needed data from one of the following sources in order of sequence:

2.

3.

A. DPC Meteorological Lab (8-594-0341)

B. National Weather Service in Greer, S.C. (864-879-1085 or 1-800-268-7785).

C. Catawba Nuclear Station Control Room (8-83 1-5345)

I NOTE: E changes to the initial Protective Action Recommendations are recognized and approved by the Emergency Coordinator, these shall be transmitted to thc offsite agencies within IS minutes. { PIP-M-00-0 1238)

I. I. 1 E

containment radiation levels exceed the levels on Enclosure 4.2. page 2 of 4, Guidance for Determination of Gap Activity, THEN:

___a Evacuate the S-mile radius AND I O miles downwind as shown on Enclosure 4.2, page 2 of 4, Protective Action Zones Determination, using wind direction a

Shelter remaining zones as shown o n Enclosure 4.2, page 7 ol4, Protective Action Zones Detcrmination, using wind direction.

RP/O/A/S700/004 Page 2 of 2.10 WCC SRO Immediate and Subsequent Actions 1.1.2 Ifcontainment radiation levels DO NOT exceed the levels on Enclosure 4.2, page 2 of 4, Guidance for Determination of Gap Activity, THEN perform one of the following:

IF wind speed less than or equal to 5 MPH, THEN:

Evacuate zones L. B, M, C, N. A, D, 0, R AND

-- Shelter zones E, F. G, H, I. I. K, P. Q, S OR -

IF wind speed greater than 5 MPH, THEN:

- 0 Evacuate the 2-mile radius AND 5 miles downwind as shown on Enclosure 4.2, page 3 of 4, Protective Action Zones Determination, using wind direction AND

- 0 Shelter remaining zones as shown on Enclosure 4.2, page 3 of 4. Protective Action Zones Determination, using wind direction.

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1.2 Complete items 1 -10. 15 and 16 on Enclosure 4.1 (Emergency Notification Form) in accordance with Enclosure 4.3, Section 1.

Make initial notification to State and County authorities using the Emergency Notification Form in accordance with Enclosure 4.3, Section 2.

1.3

2. Subsequent Actions

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2. I Notify the NRC Operations Center by completing Enclosure 4.4 and transmltting immediately but no later than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of the event declaration using RP/O/A/5700/014,.2.

2.2 Inform the OSM when this enclosure has been completed, reporting any deficiencies or problems encountered.

.1 1 STA Immediate and Subsequent Actions I

R PlolA/S 7OolOo4 Page 1 of 2

1. Immediate Actions Initial

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1 NOTE:

I, 1

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1.2 For a Drill, the Community Alert Network (CAN) is not activated.

For a security event, go to steps 1.4, 1.5. and 1.6.

Activate the Emergency Response Organization by contacting Security via the ringdown phone to the CAYSAS, or al extension 2688 or 4900 and issue the following message:

!.2.1 For 3 Di!l Activate thc TSC/OSCEOI: pagers. McGuire Delta, General Emergency declared at (time).

Activate the TSCIOSCEOF pagers, McGuire Echo, General Emergency declared at (time).

Activate the CAN system.

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I I.2.2 For an Emergency AND -

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NOTE:

For a Drill, the Emergency Response Data System (ERDS) is not activated.

ERDS can only be activated I deactivated from designated computer terminals with SDS access. These are located in the Shift Work Managers office, the Data Coordinators room in theTSC and all within the Control Room horseshoe area.

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1.3 For an Emergency, activate the Emergency Response Data System (ERDS) as soon as possible, but not later than one hour after the emergency declaration per the following:

1.3.1 1.3.2 Click on MAIN.

I.3.3 Click on GENERAL.

1.3.4 Click on ERDS.

I.3.5 Click on ACTIVATE.

1.3.6 Record the time and date ERDS was activated. TIMWDATE 1

1 Eusrem mm dd yy Ensure SDS is running on the selected terminal.

1.3.7 1.3.8 Inform the OSM that ERDS was activated.

Ir; ERDS failed lo 3ctiv;lte after five (S) attempts, T)IEN have an Offsite Agency Communicator notify the NRC via ENS or other availahle means.

1.5 I.6 For a I

RP/O/N5700/004 Page 2 of 2.11 STA Immediate and Subsequent Actions 11, E a security event exists and offsite ERO staging is desired before giving instructions to report to the TSC and OSC, THEN contact Security via the ringdown phone to the CAS/SAS, or at extension 2688 or 4900, and give instructions to activate the TSC/OSC, according to the Emergency Response Pager Instructions for a security event drill.

For an actual emergency, E a security event exists and offsite ERO staging is desired before giving instructions to report to the TSC/OSC, THEN contact Security via the ringdown phone to the CAS/SAS, or at extension 2688 or 4900. and give instructions to activate the TSC/OSC, according to the Emergency Response Pager Instructions for a security event emergency.

When the security event is stabilized to the point that ERO members can come on site, go to step 1.2.

2. Subsequent Actions

__ 2.1

__ 2.2 Notify one of the NRC Resident Inspectors using RP/O/A/5700/014. Enclosure 4.2.

Contact Duke Management using RP/O/A/5700/014. Enclosure 4.3 as soon as possible following event declaration.

Inform the OSM when this enclosure has been completed, reporting any deficiencies or problems.

2.3

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION

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3.3.1 Reactor Trip System (RTS) Instrumentation

..-\\

The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

LCO 3.3.1 APPLICABILITY:

According to Table 3.3.1-1.

ACTIONS Separats Condi!ion entry is allowed for each Function.

CONDITION A.

One or more Functions with one or more required channels inoperable.

6.

One Manual Reactor Trip channel inoperable.

C.

One channel or train inoperable.

.-/

McGuire Units 1 and 2 REQUIRED ACTION A.l Enter the Condition referenced in Table 3.3.1-1 for the channel@).

6.1 Restore channel to OPERABLE status OR B.2 Be in MODE 3.

COMPLETION TIME

!mmediately C.1 Restore channel or train to OPERABLE status.

C.2 Open reactor trip breakers (RTBs).

(continued) 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 54 hours 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 49 hours 3.3.1-1 Amendment Nos. 184/166

ACTIONS (continued)

CONDITION D.

One channel inoperable REQUIRED ACTION One channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing and setpoint adjustment.

D.l.l Place channel in trip.

AND D.1.2 Reduce THERMAL PCWEF? :O 5 75% RTP.

OR D.2.1 Place channel in trip.

AND Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable.

D.2.2 Perform SR 3.2.4.2 OR D.3 Be in MODE 3.

McGuire Units 1 and 2 3.3.1-2 RTS Instrumentation 3.3.1 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 12 hours (continued)

Amendment Nos. 184/166

RTS Instrumentation 3.3.1 CONDITION ACTIONS (continued)

I I

REQUIRED ACTION COMPLETION TIME E.

One channel inoperable.

F.

THERMAL POWER

> P-6 and e P-10, one Intermediate Range Neutron Flux channel inoperable.

One channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months I

E.1 Place channel in trip.

I -

OR E.2 Be in MODE 3.

F.1 Reduce THERMAL POWER to < P-6.

OR F.2 Increase THERMAL POWER to > P-10.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2 hours 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months G.

THERMAL POWER

> P-6 and < P-10, two Intermediate Range Neutron Flux channels inoperable.

G.l Suspend operations involving positive reactivity additions.

AND G.2 Reduce THERMAL POWER to < P-6.

Immediately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months H.

THERMAL POWER c P-6. one or two Intermediate Range Neutron Flux channels inoperable.

H.l Restore channel(s) to OPERABLE status.

Prior to increasing THERMAL POWER to > P-6 McGuire Units 1 and 2 3.3.1-3 (continued)

Amendment Nos. 184/166

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION

1.

One Source Range Neutron Flux channel inoperable.

J.

Two Source Range Neutron Flux channels inoperable.

K.

One Source Range Neutron F!ux chsnne!

inoperable.

L.

Required Source Range Neutron Flux channel inoperable.

REQUIRED ACTION 1.1 Suspend operations involving positive reactivity additions.

J.l Open RTBs.

K.l Restore channel to CPERAELE s:atus.

OR K.2 Open RTBs.

L.l Suspend operations involving positive reactivity additions.

AND L.2 Close unborated water source isolation valves.

L.3 Perform SR 3.1.1.1.

McGuire Units 1 and 2 3.3.1-4 COMPLETION TIME

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Immediately Immediately 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 49 hours Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter (continued)

Amendment Nos. 1841166

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION M.

One channel inoperable N.

One Reactor Coolant Flow - Low (Single Loop) channel inoperable.

REQUIRED ACTION

___---___--_______ NOTE-------------------

One channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing.

M.l Place channel in trip.

OR M.2 Reduce THERMAL POWER to < P-7.

NOTE--------------------

One channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing.

N.l Place channel in trip.

OR N.2 Reduce THERMAL POWER to < P-8.

McGuire Units 1 and 2 3.3.1-5 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 10 hours (continued)

Amendment Nos. 184/166

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION

0.

One Turbine Trip - Low Fluid Oil Pressure channel inoperable.

P.

One or more Turbine Trip - Turbine Stop Valve Closure channels inoperable.

0.

One train inoperable.

REQUIRED ACTION One channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing.

0.1 Place channel in trip.

OR 0.2 Reduce THERMAL POWER to c F-0.

2.1 Place channel in trip.

23 P.2 Reduce THERMAL POWER to < P-0.

.-----------------NOTE-------------------

3ne train may be bypassed for up to 4 hou% for surveillance testing provided the other train is OPERABLE.

Q.l Restore train to OPERABLE status OR Q.2 Be in MODE 3 McGuire Units 1 and 2 3.3.1-6 COMPLETION TIME j hours IO hours i hours 0 hours0 days 0 hours 0 weeks 0 months i hours 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (continued)

Amendment Nos. 184/166

RTS Instrumentation 3.3.1 1

REQUIRED ACTION

1.

One train may be bypassec for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, provided the other train is OPERABLE.

2.

One RTB may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for maintenance on undervoltage or shunt trip machanisms, provided the other train is OPERABLE.

ACTIONS (continued)

CONDITION R.

One RTB train inoperable.

S.

One or more channel(s) inoperable.

R.l Restore train to OPERABLE status.

OR R.2 Be in MODE 3.

S.l Verify interlock is in required state for existing unit conditions.

OR S.2 Be in MODE 3.

McGuire Units 1 and 2 3.3.1-7 COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7 hours 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7 hours (continued)

Amendment Nos. 184/166

RTS Instrumentation 3.3.1 ACTIONS (continued)

~

CONDITION T.

One or more channel@)

inoperable.

U.

One trip mechanism inoperable for one RTB.

V.

Two RTS trains inoperable.

REQUIRED ACTION T.l Verify interlock is in required state for existing unit conditions.

OR T.2 Be in MODE 2.

J.l Restore inoperable trip mechanism to OPERABLE stetus.

SR J.2 Be in MODE 3.

J.l Enter LCO 3.0.3.

COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7 hours 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 54 hours Immediately McGuire Units 1 and 2 3.3.1-8 Amendment Nos. 184/166

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE SR 3.3.1.1 Perform CHANNEL CHECK.

1.

Adjust NIS channel if absolute difference is > 2%

RTP.

2.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is 2 15% RTP.

Compare results of calorimetric heat balance calculation to Nuclear Instrumentation System (NIS) channel output.

SR 3.3.1.3

1.

Adjust NIS channel if absolute difference is 2 3%

AFD.

2.

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is 15% RTP.

Compare results of the incore detector measurements to NIS AFD.

FREQUENCY 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 24 hours 31 effective full power days (EFPD)

(continued)

McGuire Units 1 and 2 3.3.1-9 Amendment Nos. 184/166

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.1.4 This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.

Perform TADOT.

Si3 3.3.1.5 Perform BCTUATlON LOGIC TEST.

SR 3.3.1.6 Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is 2 75% RTP.

Calibrate excore channels to agree with incore detector measurements.

Perform COT.

McGuire Units 1 and 2 3.3.1 -1 0 FREQUENCY 31 days on a STAGGERED TEST BASIS 31 days on a STAGGERED rEST BASIS 32 EFPD 32 days (continued)

Amendment Nos. 184/166

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.1.8 This Surveillance shall include verification that interlocks P-6 (for the Intermediate Range channels) and P-10 (for the Power Range channels) are in their required state for existing unit conditions.

Perform COT.

McGuire Units 1 and 2 3.3.1-1 1 FREQUENCY

NOTE------

Only required when not performed within p:evious 92 days Prior to reactor startup Four hours after reducing power below P-10 for power and intermediate range instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND Every 92 days thereafter (continued)

Amendment Nos. 184/166

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

Y SURVEILLANCE Perform TADOT.

SR 3.3.1.10 This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

SR 3.3.1.1 1

1.

Neutron detectors are excluded from CHANNEL CALIBRATION.

Power and Intermediate Range Neutron Flux detector plateau voltage verification is not required to be performed prior to entry into MODE 1 or2.

2.

Perform CHANNEL CALIBRATION.

SR 3.3.1.12 Perform CHANNEL CALIBRATION.

SR 3.3.1.13 Perform COT.

McGuire Units 1 and 2 3.3.1

-1 2 FREQUENCY 92 days 18 months 18 months 18 months 18 months (continued)

Amendment Nos. 18411 66

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE Perform TADOT.

Perform TADOT.

SR 3.3.1.16 Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits.

SR 3.3.1.17 Verify RTS RESPONSE TIME for RTDs is within limits.

FREQUENCY 18 months

NOTE--------

Only required when not performed within previous 31 days Prior to reactor startup 18 months on a STAGGERED TEST BASIS 18 months McGuire Units 1 and 2 3.3.1 -1 3 Amendment Nos. 18411 66

APPLICABLE MOOES OR OTHER SPECIFIED REOUIRED SURVEIWCE MLOWAELE TRIP FUNCTION CONDlTlONS OUNNELS CONDITIONS AEOUIREMENTS VALUE snpoiw

2. Power Range Nevtmr Rm

a.

HlQh

b.

Low 3

Power Range N e w flu Role Hioh P w e Rota

5. SaK. Rupe

. NaEmlRux 1.2 4

1@)2 4

D E

1.2 4

D SR3.3.1.14 SR3.3.1.14 SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SA 3.3.1.1 1 SR3.3.1.16 SR3.3.1.1 SR 3.3.1.8 SR 3.3.1.1 1 SR3.3.1.16 SR3.3.1.7 SR 3.3.1.1 1 S R 3 3 1. 1 SA 3.31.11 SR 3.3.1.1 SR 3.91 d SA 331.1 1 s ~ 3 a i. a SR331.l SR331B SR 331.1 1 SR331.1 SR331.7 SR331.11 S R 3 3 1 1 SR331.11 NA NA NA NA NJA NIA

RTS Instrumentation 3.3.1 la318 3 3 1.1 ( p g e 2 01 7)

Redcloi T'ID Syslsm Ins1mrnenta:~oo APPLICABLE MODES OR OlHER SPECIFIED REWIRED S U R V E I W C E ALLOWABLE TRIP "CTlOh CONDITIONS CHANNELS CONDmONS REOUIAEMENTS V U E SETPONT

6. Ov#nemparalum AT 1.2 4

1.2 4

4

b.

Him 1 2 b

3 E

E M

N M

M SR3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR3.3.1.7 SR 3.3.1.12 SR 3.3.1.16 SR 3.3. I. 17 SR 3.3.1.1 SR 3.3.1.3 SR33.1.7 SR 3 3.1. 17 SR 3.3.1. :E SR 33 1.17 SR 33.1.6 SR3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR35.1.16 SR391.1 SR391.7 SR 3.3.1.10 SR331.16 s R w 1. 1 SR331.10 s~13ai.7 SR 3.31.1 SR331.7 s R ~ 1. 1 0 SR 331.16 SR 93.1.1 SR33.1.7 SR 33.1.10 SR 33.1.18 SR 3 3 1.9 SR 33.1 10 SR 3.3.1 6

W M to No10 1 (PEW 3.3.1-18)

Refer 0 Nolo 2 (Pap0 3.3.1 -191

> 5016 v R e f a m Note 1 (Paw 33.1-18)

Reler 0 Note 2 (Pap0 3.3.1-19) 1915 pS9 pa5 pup 92%

01%

5082V

RTS lnslrumenfation 3 3.1 APPLICABLE MODES OR SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP O7HER NOMINAL FUNCTION CONDITIONS W N E L S CONOITIONS REQUIREMENTS VALUE SETPOlM

12. Underlrequmq RCPs 13 Steam Gemmlor (SG) Water Level.

LOW LOW 14 TurbneTnp a

LouFIMdO~I Pressure b

TvrbraSQ?

.Vdve a u r e 15 Sateiy lnpcbcn (SI)

Input I r a n Engmeerec Salery Fsahne Armawn synm (ESFAS) 16 Remw Tnp System Inter(&

a Inlermedmle RilngeNeuam flm. P 4

b.

LarPwm R a w Trips m a l P-7

d.

PorsrRange Naubm FIm.

P-10

e.

T u r b n e I W Pnrrwre. P.13 1 per bus 4 per SG 3

4 2 tram 2

l w b s l n 4

4 2

M E

0 P

0 S

T T

S 1

5-3331.9 SR3.3.1.10 SR 3.3.1.16 SR 3.3 1.1 SR 3.3 1.7 SR3.3.1 10 SR3.3 1.16 SR 3.3.1.10 SR3.3.1.15 SP3.3.1.lC SR3.3~1.15 SR 3.3 1.5 SR3.3.1.14 SR 3.3 1.11 SR3.3.1.13 SR 3.3.1.5 SR 3.3.1.1 1 SR 3.3.1.13 SR 3.3.1.ll SR 3.3.1.13 SR3.3.1.12 SR3.3.1.13 I

56.4 Hz 16.W.

1 NA 2 4E-11 amp NA NA 1E.lOamp 1

NA m R T P I

1 W R T P I

McGuire Units 1 and 2 3.3 1-16

RTS Instrumentalion 3.51 APPLICAKE I

MODES OR SPECIFIED REWIRED SURVEILLANCE ALLOWABLE TRIP OTnER NOMINAL FUNCTION CONDITIONS CHANNELS CONDITIONS REOUIREMENTS VALUE SETPOINT 17 ReauorTnp 1.2 2 m n r R. V SR3.3.1.4 NA NA (il 3 i ~ 1,

41a1, d a )

z IT(~U~S C

SR 3.3 I 4 NA NA

18. Reador Tnp Breaker 1.2 1 each psr u

SR3.31.4 NA NA uwmimw and RTB Mechanisms 3@1, 4181, 5181 1 each per C

SR3.3.1.4 NA NA Breakers Shun1 Tnp RTB 13 AuVmatc Tnp ;opi 1.2 2 L.a:ns

0. v SR3.3.1.5 NA NA 3@1,.i(a), 51')

2 ualm C

SR 3.3.1.5 NA NA la)

(I)

WtC RTBs dosed end Rod Conlrd S r j m capable 01 md wnmdrarrm IKlUdicg m y reanor mp bvpass breaken mal are radW n and d a d lor bypaszing an RTB McGuire Units 7 and 2 3.3.1-17

Table 3 3 1-1 (page 5 of 7 )

Reactor Trip System listrumentation RTS Inst:umenlalion 3.3.1 Note 1: Overtemwrature AT The Overtemperature AT Function Allowable Value shall not exceed the following NOMINAL TRIP SETPOINT by more than 4.4% of RTP.

I t K, ( P - P ' ) - I, ( A / )

AT -[-IS 1

AT, [ K, - K, 1

(l+r,sJ 1 + r,s Where: AT is measured RCS AT by loop narrow range RTDs, "F ATo is the indicated AT at RTP, O F.

s is the Laplace transform operator, sec-1 T is the measured RCS average temperature, O F.

T' IS tho nomina! Tavg at RTP, < S E. ! O F.

P is the measured pressurizer pressure. psig P is the nominal RCS operating pressure, = 2235 psig K,

= Overtemperature AT reactor trip NOMINAL TRIP SETPOINT, as presented I

in the COLR.

K2

= Overtemperature AT reactor trip heatup setpoint penalty wefficient, as presented in the COLR.

K3

= Overtemperature AT reactor trip depressurization setpoint penalty adiaent. as presented in the COLR.

7>,72 = Time constants utilized in the lead-lag controller for AT, as presented in the

COLR, 7,

= Time constants utilized in the lag compensator for AT, as presemed in the

COLR, 7..

= Time constants utilized in the lead-lag controller for T as presented in the

COLR, re

= Time m t

s mied in the measured Tw lag compensator, as pcssemed in the COLR. and.

f,(Al) = a furdon of the mdicated difference between lop and bottom detectors of the power-range nuclear ion chambers; wrttr g a m to be selected based on measured instrument respcnse dunng plant startup tests such that (I) for q, - q, between the 'posmve' and 'negabve' fl(Al) breakpoints as presented in the COLR. f,(AI) = 0. where ql and f& are percent RATED THERMAL POWER in the top and bottom halves of the core respectrvely. and q1 + q, is total THERMAL POWER in percent of RATED THERMAL POWER, (continuedl McGuire Unlts 1 and 2 3.3.1-1 8

RTS Instrumentation 3.3.1 Table 3.3 1-1 (page 6 of 7)

Reactor Trip System Instrumentation (ii) for each percent imbalance that the magnitude of q, - q, is more negative than the f,(Al) 'negative' breakpoint presented in the COLR, the AT Trip Setpoint shall be automatically reduced by the f,(Al) 'negative' slope presented in the COLR; and for each percent imbalance that the magnitude of ql - q, is more positive than the f,(AI) 'positive' breakpoint presented in the COLR.

the AT Trip Setpoint shall be automatically reduced by the f,(Al)

'pasitive" slope presented in the COLR.

(iii)

Note 2: Overpower AT The Overpower AT Funciion Ailowable 'tiilw shall not exceed the follobving NOMINAL TRIP SETPOINT by more than 3.0% of RTP.

i Where: AT is measured RCS AT by loop narrow range RTDs. O F.

ATo is the indicated AT at RTP, "F.

s is the Laplace transform operator, sed'.

T is the measured RCS average temperature, O F.

T' is the nominal TNo at RTP, 5 585.1 OF.

K,

= Overpower AT rehctor NOMINAL TRIP SETPOINT as presented in the cow.

K6

= 0.02PF for increasing average temperature and 0 for decreasing average temperature, Ke

= Overpower AT reaUor trp heatup setpolnt penalty axtkient as presented in the COCR for T > T' and & = 0 for T cT, 71,72 = Time canstants tiiilied in the W l a g controller for AT, as presented in the COLR.

T~

= l-trne constants utilied m the lag compensator for AT. as presented in the

COLR, rs

= Tme constants utilized in the measured Tq tag compensator. as presented in the COLR, 77

= Time constant utilized in the rate-lag wntroller for T as presented in the COLR, and fdAl) = a function of the indicated ditference belween top and bottom detectors of the power-range nuclear ion chambers: wrth gains to be selected based on measured instrument response during plant startup tests such that:

(continued)

McGuire Units : 2nd 2 3 3 1-19 L -. ? l : l a l t I,>?!.

1451175

(i)

(ii)

(iii)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 7)

Reactor Trip System Instrumentation for q, - qb between the "positive" and 'negative' fz(Al) breakpoints as presented in the COLR; fz(Al) = 0, where q, and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER; for each percent imbalance that the magnitude of q, - qb is more negative than the fz(Al) 'negative' breakpoint presented in the COLR, the AT Trip Setpoint shall be automatically reduced by the fz(Al) "negative" slope presented in the COLR; and for each percent imbalance that the magnitude of q, - qb is more positive than tics f2(61j "pcsitive' breakpoint preseilted in the COiFI, the AT Trip Setpoint shall be automatically reduced by the fe(A1)

'positive' slope presented in the COLR.

McGuire Units 1 and 2 3.3.1-20 Amendment Nos. 184/166

~~

CRITICAL SAFETY FUNCTION STATUS TREES Containment - Page 1 of 1 PAGE NO.

9of 11 Rev. 3 EP/1 /A/500O/F-O pp pppp cow 1i2 cow LESS THAN 0 I%

GO TO FR-Z.I GO TO FR-Z 3 0

0

ML033090465

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