ML032110332

.. .:.

,Accumulators

. . . I .

.

s:

3.5.1

D.l

Enter LCO 3.0.3.

Immediately

McGuire Units 1 and 2

3.5.1-.1

Amendment Nos. 184/166

SURVEILLANCE REQUIREMENTS

SURVEILLANCE

SR 3.5.1.1

Verify each accumulator isolation valve is fully open.

SR 3.5.1.2

Verify borated water volume in each accumulator is

-

> 6870 gallons and 5 7342 gallons.

SR 3.5.1.3

Verify nitrogen cover pressure in each accumulator is

-

z 585 psig and 5 639 psig.

SR 3.5.1 .$

Verify boron concentration in each accumulator is within

the limits specified in the COLR.

SR 3.5.1.5

Verify power is removed from each accumulator isolation

valve operator when RCS pressure is > 1000 psig.

.. . .

i

.

pccumulators

.... .

3.5.1

FREQUENCY

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

31 days

yJJ

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

3nly required to

,e performed for

3ffected

3ccumulators

Ince within

j hours after each

iolution volume

ncrease of 2 1 %

)f tank volume

hat is not the

esult of addition

rom the refueling

vater storage tank

)1 days

_.

McGuire Units 1 and 2

-,*st.

3.5.1-2

Amendment Nos. 184/166

, Containment

3.6.1

A.

Containment inoperable. I A.l

Res!cre containment I 3

OPERABLE status.

I

3.6 CONTAINMENT SYSTEMS

3.6.1 Containment

'~

1 hoiii

LCO 3.6.1

Containment shall be OPERABLE.

E.

Required Action and

associated Completion

Time not met.

APPLICABILITY:

MODES 1, 2, 3, and 4.

B.l

Be in MODE 3.

-

AND

8.2

Be in MODE 5

ACTIONS

CONDITION

REQUIRED ACTION

COMPLETION TIME

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

1 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

I

McGuire Units 1 and 2

3.6.1-1

Amendment Nos.207 & 188

-\\

k:

I

..i accordance with

the Containment

Leakage Rate

Testing Program

I

SURVEILLANCE REQUIREMENTS

SURVEILLANCE

SR 3.6.1.1

.-------------------..-NOTES~---------------------

1. The space between each dual ply bellows assembly

on penetrations between the containment building

and annulus shall be vented to the annulus during

Type A tests.

2. Following each Type A test, the space between each

dual-ply bellows assembly shall be subjected to a low

pressure test at 3 to 5 psig to verify no detectable

leakage, or the assembly shall be subjected to a leak

test with the pressure on the containment side of the

I

,

assembly at Pa.

3. Type C tests on penetrations M372 and M373 may be

perforred without draining the glycol-water mixture

from the seats of their diaphragm valves if meeting a

zero indicated leakage rate (not including instrument

error).

Perform required visual examinations and leakage rate

testing except for containment airlock testing, in

accordance with the Containment Leakage Rate Testing

Program.

McGuire Unils 1 and 2

3.6.1-2

Containment

n

3.6.1

FREQUENCY

I

Amendment Nos. 207 & 18

-

,I

Containment

0 3.6.1

J

B 3.6 CONTAINMENT SYSTEMS

B 3.6.1 Containment

' <

BASES

. .

BACKGROUND

The containment is a free standing steel pressure vessel surrounded by

a reinforced concrete reactor building. The containment vessel,

including all its penetrations, is a low leakage steel shell designed to

contain the radioactive material that may be released from the reactor

core following a design basis Loss of Coolant Accident (LOCA).

Additionally, the containment vessel and reactor building provide

shielding from the fission products that may be present in the

containmenl atmosphere following accident conditions.

The containment vessel is a vertical cylindrical steel pressure vessel with

hemispherical dome and a flat circular base. It is completely endosed

by a reinforced concrete reactor building. An annular space exists

between the walls and domes of the steel containment vessel and the

concrele reactor building to provide for the collection, mixing, holdup,

and controlled release of containment out leakage. Ice condenser

containments utilize an outer concrete building for shielding and an inner

SIeel conlainment for leak lightness.

Confainmeni piping penetration assemblies provide for the passage of

ptocess. service, sampling, and instrumentation pipelines into the

containment vessel while maintaining containment integrity. The reactor

building provides shielding and allows controlled release of the annulus

alrnosphere under accident conditions, as well as enrironmentat missile

proteaion for the containment vessel and Nuclear Steam Supply

Sysf em.

The inner steel containment and its penetrations establish the leakage

limiling boundary of the containment. Maintaining the containment

OPERABLE limits the leakage 01 fission product radioactivity from the

containment to the environment. SR 3.6.1.1 leakage rate requirements

comply with 10 CFR 50, Appendix J, Option B (Ref. 1). as modified by

I

,

approved as above exemptions.

I

The isolation devlces for the penetrations in the containment boundary

are a part of the containment leak light barrier. To maintain this leak

tighl barrier:

a

All penelrattons required IO be closed during accident conditions

arc either'

__-

.~

_.

.- ..

. ..

.

McGuire Units 1 and 2

D 3 G . l . 1

Revision No. 32

wnrainrnenr

B 3.6.1

I

BASES

I

BACKGROUND (continued)

1.

capable of being closed by an OPERABLE automatic

containment isolation system, or

2.

closed by manual valves, blind flanges, or de-activated

automatic valves secured in their closed positions, except as

provided in LCO 3.6.3, 'Containment Isolation Valves';

b.

Each air lock is OPERABLE, except as provided in LCO 3.6.2.

'Containment Air Locks';

All equipment hatches are closed and sealed; and

The sealing mechanism associated wkh a penetration (e.g., welds,

bellows, or O-rings) is OPERABLE.

c.

d.

APPLICABLE

SAFETY ANALYSES withstand the pressures and temperatures of the limiting Design Basis

The safety design basis for the containment is that the containment must

Accident (DBA) without exceeding the design leakage rates.

The DBAs that result in a challenge to containment OPERABILITY from

high pressures and temperatures are a loss of coolant accident (LOCA)

and a steam line break (Ref. 2). In addition, release of significant fission

product radioactivity within containment can occur from a LOCA. In the

DBA analyses, it is assumed that the containment is OPERABLE such

that, for the DBAs involving release of fission product radioactivity,

release to the environment is controlled by the rate of containment

leakage. The containment was designed with an allowable leakage rate

of 0.3% of containment air weight per day (Ref. 3). This leakage rate.

used in the evaluation of offsite doses resulting from accidents. is

maximum allowable containment leakage rate at the calculated peak

containment internal pressure (Pa) resulting from the limiting design

basis LOCA. The allowable leakage rate represented by La forms the

basis lor the acceptance criteria imposed on all containmenl leakage

rate testing. La is assumed lo be 0.3% per day in the safety analysis at

Pa = 14.8 psig (Ref. 3). Satisfactory leakage rate test results are a

requirement lor the establishment of containment OPERABILITY.

The containment satislies Criterion 3 01 10 CFR 50.36 (Rel. 4).

defined in 10 CFR 50, Appendix J, Option B (Ref. l), as La: the

I

-

- -. .. -. . .. - -

. .

.~~

.

. .

... . . . .

B 3.6.1.2

Revision No. 32

McGuire Units 1 and 2

BASES

LCO

Containment OPERABILIW is maintained by limiting leakage to 2 1.0 La,

excepl prior to the first startup after performing a required Containment

Leakage Rate Testing Program leakage test. At this time, the applicable

leakage limits must be met.

Compliance with this LCO will ensure a containment configuration,

including equipment hatches, that is structurally sound and that will limit

leakage to those leakage rates assumed in the safety analysis.

Individual leakage rates specified for the containment air lock .

(LCO 3.6.2). purge valves with resilient seals, and reactor building

bypass leakage (LCO 3.6.3) are not specifically pari of the acceptance

criteria of 10 CFR 50, Appendix J. Therefore, leakage rates exceeding

these individual limits only result in the containrnerit being inoperabie

when the leakage results in exceeding the overall acceptance criteria of

1.0 L.

I

.,

APPLICABILITY

In MODES 1 , 2, 3, and 4, a DBA could cause a release of radioactive

material into containment. In MODES 5 and 6. the probability and

consequences of these events are reduced due to the pressure and

temperature limitations of these MODES. Therefore, containment is no1

required to be OPERABLE in MODE 5 to prevent leakage of radioactive

material from Containment. The requirements for containment during

MODE 6 are addressed in LCO 3.9.4, 'Containment Penetrations.'

A. 1

ACTIONS

-

In the event containment is inoperable, containment must be restored to

OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time provides

a period of lime to correct the problem commensurate with the

importance of maintaining containment OPERABLE during MODES 1, 2,

3, and 4. This time period also ensures that the probability of an

accident (requiring Containment OPERABILITY) occurring during periods

when containment is inoperable IS minimal.

6.1 and 8.2

If containment cannol be reslored lo OPERABLE slatus within the

required Completion Time, lhe plant must be brought lo a MODE in

which Ihe LCO does not apply. To achieve this stalus, lhe plant must be

brought lo at leas1 MODE 3 wtthm G hours and to MODE 5 within

.~

~

~ ~.

McGuire Unlts 1 and 2

e 3.6.1-3

Revision No. 32

Containment

B 3.6.1

n

BASES

'.

ACTIONS (continued)

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on

operating experience, to reach the required plant conditions from full

power conditions in an orderly manner and without challenging plant

systems.

SURVEILLANCE

SR 3.6.1.1

REQUIREMENTS

Maintaining the containment 0PERABL.E requires compliance with the

visual examinations and leakage rate test requirements of the

Containment Leakage Rate Testing Program. Failure to meet specific

leakage limits for the air lock, semndav containment bypass leakage

path, and purge valve with resilient seals (as speafied in LCO 3.6.2

and LC9 3.6.3) does not invalidate the acceptability of Ihe overall

contairlcient leakage determinations unless the specific leakage

contribution to overall Type A, B, and C leakage causes one of these

overall leakage limits to be exceeded. As left leakage prior to the first

startup after performing a required Containment Leakage Rate Testing

Program leakage test is required to be < 0.6 L, for combined Type B

and C leakage, and 5 0.75 La for Option B for overall Type A leakage.

At all other times between required leakage rate tests. the acceptance

criteria is based on an overall Type A leakage limit of 5 1.0 La. At 5 1.0

La the offsite dose consequences are bounded by the assumptions of the

safety analysis. SR Frequencies are as required by the Containment

Leakage Rate Testing Program. These periodic testing requirements

verify that the containment leakage rate does not exceed the leakage

rate assumed in the safety analysis.

The Surveillance is modified by three Notes.

Note 1 requires that the space between each duel-ply bellows assembly

on containment penetrations between the containment building and the

annulus be vented to the annulus during each Type A test.

Note 2 requires that following each Type A test. the space between each

dual-ply bellows assembly be subjected lo a low pressure leak lest with

no detectable leakage. Otherwise. the assembly must be tested with the

containmenl side of the bellows assembly pressurized to P, and meet

the requirements of SR 3.6.3.8 (bypass leakage requirements).

Note 3 allows penetrations M372 and M373 lo be tested without draining

the glycol-water mixture lrom the associated diaphragm valves (NF-

288A. NF-2336 and NF-231A) as long as no1 leakage is indicaled. This

IesI may be used in lieu of 10 CFR 50. Appendix J. Oplion Bas defined

_ _

~~

-

McGuire Units 1 and 2

B 3.6.1-1

Revision No. 32

I

Containment

0 3.6.1

BASES

.I,,

SURVEILLANCE REQUIREMENTS (continued)

1

I

in ANSVANS 56.8-1994 Section 3.3.5 (Test Medium). The required test

pressure and interval are not changed.

All test leakage rates shall be calculated using observed data converted

to absolute values. Error analysis shall also be performed to select a

balanced integrated leakage measurement system.

REFERENCES

1.

10 CFR 50, Appendix J, Option B.

I

2.

UFSAR, Chapter 15.

3.

UFSAR, Section 6.2.

4.

10 CFR 50.36, Technical Specifications, (c)(2)(ii).

./

.

~

..__

~

__

McGuire Unils 1 and 2

8 36.1-5

Revision No. 32

Containment Air Temperature

3.6.5

REQUIRED ACTION

3.6 CONTAINMENT SYSTEMS

3.6.5 Containment Air Temperature

COMPLETION TIME

LCO 3.6:5

Containment average air temperature shall be:

A.l

Restore containment

average air temperature to

within limits.

a.

b.

2 75OF and s 100°F for the containment upper compartment, and

2 100°F and S 120°F for the containment lower compartment.

1.

The minimum containment average air temperature in MODES 2.3,

and 4 may be reduced to 60°F.

Containment lower compartment tempsrature may be between

120°F and -for

up to 90 cumulative days per calendar year

provided lower compartment temperature average over the previous

365 days is less than 120°F. Within this 90 cumulative day period,

lower compartment temperature may be between 125°F and 135'F

for 72 cumulative hours.

2.,

..................................................................................................

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

APPLICABILITY:

MODES I , 2, 3, and 4.

ACTIONS

CONDITION

A.

Containment average air

temperature not within

limits.

B.

Required Action and

associated Completion

Time not met.

B.l

Be in MODE 3.

-

AND

B.2

Be in MODE 5.

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

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

McGuire Units I and 2

3.6.5-1

Amendment Nos. 1841166

Containment Air Temperature

3.6.5

SURVEILLANCE

FREQUENCY

SR 3.6.5.1

Verify containment upper compartment average air

temperature is within limits.

S R 3.6.5.2

Verify containment lower compartment average air

temperature is within limits.

McGuire Units 1 and 2

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

3.6.5-2

Amendment Nos. 184/166

UNIT 1

A PI1 lA/5500/19

& 1.

Check VI - AVAILABLE.

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 1 of 23

Startup of ND Pumps

PAGE NO.

Rev. 15

75 Of 152

GO TO Enclosure 18 (Startup of ND

Pumps Without VI Available) to start

ND pump.

_--

I ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

NOTE

1ND-35 (ND To FWST Isol) may be assumed to be closed, unless known to be

open.

-

2.

Check 1NQ-35 (ND To FWST Isa!) -

CLOSED.

NOTE

IND-35 will be closed later in

this enclosure, prior to

starting ND pump.

-

Dispatch operator to stand by 1ND-35

(ND To FWST Isol) (aux bldg, 750~7,

KK-52, just outside 16 NDlNS Hx room).

3.

Check if ND letdown valves should be

closed:

-

a. Check Pzr level - LESS THAN 96%.

a. Perform the fol!owing:

- 1) IF letdown flow indicates zero,

____

THEN GO TO Step 3.b.

-

2) E any NC system opening known to

exist, THEN GO TO Step 3.b.

-

3) GEimStep4.

-

b. Close INV-121 (ND Letdown Control).

c. Close the following:

c. Dispatch operator to close affected

- 1ND-32 (A ND Hx To Letdown Hx)

- IND-17 (B ND Hx To Letdown Hx).

valve(s).

- 1ND-32 (aux bldg, 733+6, 1A ND Hx

Room, 3 feet from west wall and 1

foot from south wall)

- 1ND-17 (aux bldg, 733+12, 15 ND

Hx Room, 3 feet from west wall and

10 feet from south wall).

-

d. GOTOStep 5

LOSS OF ND OR ND SYSTEM LEAKAGE

PAGE NO.

Enclosure 14 - Page 2 of 23

76 of 152

Startuo of ND Pumos

AP/I/A/5500/19

UNIT 1

Rev. 15

I

J

I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

I

4.

Align ND letdown per one of the

following:

E

desired to place 1A ND pump in

service, THEN perform the following:

-

a. Open IND-32 (A ND Hx To Letdown

Hx).

-

b. Close 1lilD-17 (E ND Hx To Letdown

HX).

E

desired to place 1 B ND pump in

service, THEN perform the following:

-

a. Open IND-17 (B ND Hx To Letdown

Hx).

b. Close 1ND-32 (A ND Hx To Letdown

Hx).

-_

-

5. Check S/I -HAS OCCURRED.

6.

Reset the following:

a. SA

-

b. Sequencers.

-

a. Dispatch operator to open IND-32

(aux bldg, 733+6, 1A ND Hx Room, 3

feet from west wall and 1 foot from

south wall).

-

b. Dispatch operator to close IND-17

(aux bldg, 73342, 1B ND Hx Room,

3 feet from west wall and 10 feet

from south wall).

-

a. Dispatch operator to open IND-17

(aux bldg, 733+12,1B ND Hx Room,

3 feet from west wall and 10 feet

from south wall).

-

b. Dispatch operator to close 1ND-32

(aux bldg, 733+6, 1A ND Hx Room, 3

feet from west wall and 1 foot from

south wall).

GO TO Step 7.

_--

-

c. Reset modulating valves using reset

buttons on RN control board.

I

Rev. 15

UNIT 1

Startup of ND Pumps

I

1

.(

I

.

AP/I/Af5500/19

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 3 of 23

PAGE NO.

77 of I52

7.

Start desired ND pump PER one of the

following:

I

ACTION/EXPECTED RESPONSE

E 1A ND Pump is to be started, THEN

- _ _

GO TO Step 8.

RESPONSE NOT OBTAINED

I

1B ND Pump is to be started,

-

Step 48.

8.

Dispatch 2 operators to perform the

following on IND-24 (A ND Pump

Discharge Isol) (aux bldg, 695+12,

GG-54, room 501, ND Pump room 1A 0.1

east wall):

a. Unlock valve.

-

b. Close valve.

-

c. Open valve 2 turns.

-

9. Dispatch operator to open breaker

IEMXA - F12B (1A ND Pump 8, Hx

Miniflow lsol Motor (IND-68A)) (aux bldg,

750, FF-54-55).

-

10.

Check 1A RN Pump -AVAILABLE.

-

11.

Start 1A RN Pump.

12.

Start 1A KC pumps as follows:

-

a. Select "AUTO on 1KC-51A (Train A

Recirc Isol).

-

b. Start 1 A l and 1A2 KC pumps

13.

Ensure RN flow established to KC Hx in

operation.

-

GO TO Step 13.

_--

I

LOSS OF ND OR ND SYSTEM LEAKAGE

PAGE NO.

78 of 152

Rev. 15

Enclosure 14 - Page 4 of 23

Startup of ND Pumps

APlllA15500/19

UNIT 1

I

IJ

I

ACTION/EXPECTEO RESPONSE

RESPONSE NOT OBTAINED

1

14.

Establish KC flow to I A ND Hx as

follows:

-

a. Close IKC-81B (KC To B ND Hx)

-

a. IF AT ANY TIME adequate KC flow to

1A ND Hx cannot be established,

dispatch operator to close IKC-81B

(aux bldg, 750+10, LL-53. above UHI

nitrogen heaters).

b. IF AT ANY TIME adequate KC flow to

1A ND Hx cannot be estab!ished, THEN

throttle closed the following valves as

required:

- IKC-I49 (A KF Hx Outlet Flow)

- IKC-156 (E KF Hx Outlet Flow).

e. Throttle open IKC-56A (KC To A ND

Hx) to establish 2000 GPM to

5000 GPM KC flow to 1A NO Hx, while

limiting each KC pump flow to

4000 GPM.

-

c. Evaluate opening KC cross-tie valves to

establish flow from other train as

follows:

1) Open:

- IKC-1A (Trn A Aux Bldg Non Ess

Ret Isol)

IKC-2B (Tm B Aux Bldg Non Ess

Ret lsol).

-

2) Open:

IKC-5OA (Tm A Aux Bldg Non

Ess Sup Isol)

IKC-53B (Trn B Aux Bldg Non

Ess Sup Isol).

-

II

AP'

15.

-

._

-

-7

LOSS OF ND OR ND SYSTEM LEAKAGE

PAGE NO.

79 Of 152

Rev. 15

I

Enclosure 14 - Page 5 of 23

Startup of ND Pumps

AP/I/A/550Oll9

UNIT 1

Check 1N.D-35 (ND To FWST lsol) -

CLOSED.

ACTION/EXPECTED RESPONSE

Perform the following:

RESPONSE NOT OBTAINED

a. Do not continue until Steps 8 through 14

are completed.

-

CAUTION

I f IND-35 is being

used far feed and

bleed, NC

temperature may

rise after valve is

closed. Subsequent

steps to start ND

pump should be

performed without

delay to avoid

excessive heatup.

-

b. Notify dispatched operator to dose an

lock IND-35 (ND TO FWST Iso~).

-

c. Do not continue until 1ND-35 is closed.

16. Check the following valves:

-

a. IND-18 (C NC Loop to ND Pumps)

OPEN.

-

b.- 1ND-2AC (C NC Loop To ND Pumps) -

OPEN.

-

c. IND-I9A (A ND Pump Suct From

FWST or NC) - OPEN.

-

17.

Step 20.

-

a. a

WStep 18.

-

b. GOWStep 18.

-

c. W m S t e p 19.

-

18.

Check IFW-27A (FWST Supply To ND) -

CLOSED.

NOTE

Closing IFW-27A meets

interlock to allow opening

1ND-IB (C NC Loop to ND

Pumps) and 1 ND-2AC (C NC

Loop To ND Pumps).

-

Close 1FW-27A.

APlllA15500119

UNIT 1

.

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 6 of 23

Startup of ND Pumps

PAGE NO.

80 of 152

Rev. 15

19.

Realign NC to ND valves as follows:

I

ACTION/EXPECTED RESPONSE

-

a. Check 1A ND Pump discharge pressure

PRESSURE.

- WITHIN 200 PSlG OF NC

I

RESPONSE NOT OBTAINED

a. Perform the following:

1) E NC pressure is greater than ND

pump discharge pressure, THEN

_ _

GO TO Enclosure 1 (Equalizing

Pressure Between NC and ND).

-

2) E ND pump discharge pressure is

grea:er than I C pressure,

contact station management for

guidance to perform the following:

-

a) Ensure ND System remains

subcooled when depressurizing

ND.

b) Equalize pressure between ND

- and NC systems.

b. Open the following valves:

- IND-18 (C NC Loop to ND Pumps)

- IND-2AC (C NC Loop To ND Pumps)

IND-19A (A ND Pump Suct From

FWST or NC).

-

20.

Close the following valves:

- IND-29 (A ND Hx Outlet)

- IND-18 (B ND Hx Bypass)

Dispatch operator to close affected

valve(s):

- 1ND-18 (aux bldg, 733+8. LL-52, room

732, ND heat exchanger room 1B)

- IND-15B (Train B ND To Hot Leg Isol)

- INI-183B (ND To B & C Hot Legs Isol).

- 1ND-15B (aux bldg, 733+8, LL-51, room

732, ND Hx room 18)

- 1NI-183B (aux bldg, 733+10. FF-52,

room 602, midget hole, enter from

electrical penetration room, 4 ft from

reactor bldg wall, 3 ft from ceiling).

AP/I/A/5500/19

UNIT 1

21.

Open the following valves:

Dispatch operator to open affected

.- -

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 7 of 23

Startup of ND Pumps

PAGE NO,

81 of 152

Rev. 15

INI-173A (Train A ND To A & B CL)

I

ACTION/EXPECTED RESPONSE

valve(s):

I

RESPONSE NOT OBTAINED

-

INI-173A (aux bldg, 716+21. GG-52,

room 602, midget hole near reactor bldo

-

IND-30A (Train A ND To Hot Leg Isol)

-

IND-33 (A ND Hx Bypass)

-

I

wall above ledge, 4 ft south of GG-52

near VCT area)

- IND-34 (A & B ND Hx Bypass).

- IND-30A (aux bldg, 733+4, LL-52, room

733, ND heat exchanger room IA, 1 ft

from east, 8 fi from south)

- IND-33 (aux bldg, 733+8, LL-52, room

732, ND heat exchanger room IB).

22.

Check if either of the following are

believed to have occurred:

- Air entrainment in ND System

- Voiding of NC System.

Perform the following:

NOTE

Makeup options using

IND-35 (ND To FWST

Isol) cannot be used,

since it must be closed

prior to starting ND

pump.

-

a. IF AT ANY TIME NC level drops when

ND pump is started, THEN makeup as

required PER Enclosure 3 (NC

System Makeup During Loss of ND).

-

b. a m s t e p 2 5

NOTE

Makeup options using IND-35 (ND To FWST Isol) cannot be used, since it must

be closed prior to starting ND pump.

23.

Initiate makeup PER Enclosure 3 (NC

System Makeup During Loss of ND)

prior to starting ND pump, to avoid

losing level when pump is statted.

LOSS OF ND OR ND SYSTEM LEAKAGE

PAGE NO.

Enclosure 14 - Page 8 of 23

Startuo of ND Pumos

'/l/A/5500/19

UNIT 1

II

I I '

I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

IF voiding has occurred, THEN restore

Goling slowly in next steps, to avoid

rapid loss of level due to void collapse.

Check core exit TlCs -AVAILABLE.

---

GO TO Step 27.

Check subcooling based on core exit

TKs - GREATER THAN 0' F.

Perform the following:

a. E core exit T/Cs indicale less tinan

200" F, THEN GO TO Step 27.

-

b. Raise makeup flow rate.

c. E makeup flow inadequate, THEN use

different or multiple makeup flowpaths

in Enclosure 3 (NC System Makeup

During Loss of ND).

d. E IND-35 (ND To FWST Isol) is used

for makeup, THEN ensure IND-35 is

closed prior to starting ND pump.

e. Attempt to restore subcooling based on

core exit TICS to greater than Oo F.

E subcooling restored, THEN GO TO

Step 27

-

f

-

g. E

FWST level less than 20 inches,

__--

THEN GO TO Step 27.

h. E

subcooling cannot be restored,

THEN perform the following:

- 1) Open 1 FW-27A (FWST Supply To

ND).

-

2) E

IFW-27A will not open, THEN_

dispatch operator to open and

standby 1FW-27A (aux bldg. 695

pipechase, GG-52, 5 ft from north

wall).

-

3) GOlStep28.

II

I

LOSS OF 'ND OR ND SYSTEM LEAKAGE

I PAGENO. 1

ACTlONlEXPECTED RESPONSE

I

11

AP/I/A15500/19

UNIT 1

RESPONSE NOT OBTAINED

1

Enclosure 14 - Page 9 of 23

Startup of ND Pumps

I'

I

1

27.

-

28.

-

29.

-

30.

-

31.

-

Check IFW-27A (FWST Supply To ND) -

CLOSED.

Do not continue until IND-24 (A ND

Pump Discharge lsol) throttled 2 turns

open.

Establish communications with

operators at 1ND-24 (A ND Pump

Discharge Isol).

Check NC level - GREATER THAN

10 INCHES.

Check 1ND-32 (AND Hx To Letdown Hx)

- CLOSED.

-

Ensure IFW-27A closed prior to starting

ND pump.

Attempt to raise level.

-

IF ND letdown in service, THEN:

- Anticipate a step rise in letdown flow

WHEN ND pump is started, THEN

when ND pump is started in next step.

immediately throttle letdown flow as

required to maintain stable NC pressure

and level.

- -

CAUTION

Starting an ND pump may result in a level drop due to shrink or the

release of trapped air.

32.

Start 1A ND Pump.

-

33.

Have operators s

m

open 1ND-24 (A

ND Pump Discharge Isol) until ND flow is

1000 GPM to 1500 GPM.

APll/A/5500/19

UNIT 1

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 10 of 23

Startup of ND Pumps

PAGE NO.

84 of 152

Rev. 15

-

34.

Check IFW-27A (FWST Supply To ND) -

CLOSED.

I

ACTION/EXPECTED RESPONSE

Perform the following:

-

a. E control room operation of IFW-27A

is unavailable, THEN locally operate

IFW-27A in next steps.

b. IF AT ANY TIME FWST level goes

below 20 inches, THEN close

-

IFW-27A.

RESPONSE NOT OBTAINED

I

NOTE

1FW-27A (FWST Supply

To ND) can be throttled

in the open direction only

(seals in on closed

direction).

c. E core exit TICS available, THEN:

- -

0 WHEN subcooling based on core exit

T/Cs is greater than Oo F, THEN

throttle or close 1 FW27A while

ensuring NC level is maintained.

-

d. E core exit T/Cs unavailable, THEN

throttle or close 1 FW-27A while

ensuring NC level is maintained.

35. Check NC level -GREATER THAN

4iNCHES.

-

Perform the following:

a. Stop ND pump.

-

b. Evaluate need to vent ND pump suction

PER Enclosure 2 (Venting of ND

Pumps and Suction Piping),

-

c. Makeup to the NC System pEJ

Enclosure 3 (NC System Makeup

During Loss of ND) until NC level is

greater than 10 inches.

-

d. WHEN conditions established to start

ND pump,

RETURN TO Step 1.

e. RETURN TO Step in effect in body of

this procedure.

-

36. Slowly throttle close IND-34 (A & B ND

Hx Bypass) until a drop in ND flow is

observed.

-

37.

Have operators open, backseat, and lock

IND-24 (A ND Pump Discharge Isol).

38.

Throttle the following as necessary to

maintain stable NC temperature:

IND-29 (A ND Hx Outlet)

IND-34 (A & B ND Hx Bypass).

-

GO TO Step 41.

---

-

39. Check NC temperature based on core

exit TK's - LESS THAN ZOOo F.

-

40.

Reduce KC flow to 1A ND HX as required

to control NC temperature.

41.

IF AT ANY TIME cooldown is required,

THEN REFER TO Unit 1 Data Book Curve

1.6 b (Heatup and Cooldown Limits for

LTOP).

-

APlllAl5500119

UNIT 1

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 12 of 23

Startuo of ND Pumos

PAGE NO.

86 Of 152

Rev. 15

42.

Check feed and bleed cooling -

INITIATED.

ACTION/EXPECTED RESPONSE

_--

GO TO Step 43.

I

RESPONSE NOT OBTAINED

I

-

a. Initiate cooldown to 200" F on core exit

TIC'S.

b. WHEN NC temperature is less than

200" F on core exit Tlc's,

perform the following:

CAUTION

Failure to stop makeup to NC System prior to closing Pzr PORVs

may cause low temperature over pressure concern.

-

1) Stop or reduce makeup to NC

System.

2)

vent path, AND makeup to NC

System stopped, m:

-

a) Close PZR PORVs.

PORV (s) not required open as

-

b) Place closed Pzr PORVs in

"AUTO.

-

3) Control ND flow to maintain NC

System subcooled.

-

43. Ensure ND flow greater than 1500 GPM. ----

-

44.

Dispatch operator to reclose breaker

IEMXA- F12B (1A ND Pump & Hx

Miniflow lsol Motor (IND-68A)).

-

45.

Ensure IND-68A (A ND Pump & A Hx

Miniflow) remains closed.

APl1lAl5500J19

UNIT 1

-

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 13 of 23

Startup of ND Pumps

PAGE NO.

87 of 152

Rev. 15

46.

air entrainment may have occurred on

the idle train, THEN:

I

ACTION/EXPECTED RESPONSE

-

a. Remove noncondensible gases from

idle ND Hx

Train Hx Flush).

-

b. Ensure idle train vented PER Enclosure

2 (Venting of ND Pumps and

Suction Piping).

Enclosure 15 (Idle ND

I

RESPONSE NOT OBTAINED

I

-

47.

RETURN

step in effect ill kody of this

procedure.

48.

Dispatch 2 operators to perform the

following on IND-9 (B ND Pump

Discharge Isol) (aux bldg, 695+12, FF-54,

room 500, ND Pump room 1 B on north

wall]:

a. Unlock valve

-

b. Close valve

-

c. Open valve 2 turns

-

49.

Dispatch operator to open breaker

IEMXBI - 2C (1B ND Pump 8 Hx Miniflow

Is01 Motor (1ND-678)) (aux bldg, 733,

GG-55-56).

-

50.

Check 18 RN Pump -AVAILABLE.

_--

GO TO Step 53.

-

51.

Start 1B RN Pump.

52.

Start KC pumps as follows:

-

a. Select "AUTO on 1KC-54B (Train B

Recirc Isol).

-

b. Start 1 B1 and 182 KC Pumps

~

__ .

LOSS OF ND OR ND SYSTEM LEAKAGE

PAGE NO.

88 Of 152

Rev. 15

Enclosure 14 - Page 14 of 23

Startup of ND Pumps

APll/A/5500/19

UNIT 1

54.

Establish KC flow to 1B ND Hx as

follows:

-

a. Close IKC-56A (KC To A ND Hx)

-

b. IF AT ANY TIME adequate KC flow to

1B ND Hx cannot be established, THEN

throttle closed the following valves as

required:

- 1 KC-I49 (A KF Hx Outlet Flow)

-

0 IKC-156 (E KF Hx Outlet Flow).

-

c. Throttle open IKC-81B (KC To B ND

Hx) to establish 2000 GPM to

5000 GPM KC flow to 1B ND Hx, while

limiting each KC pump flow to

4000 GPM.

ACTION/EXPECTED RESPONSE

a. IF AT ANY TIME adequate KC flow to

1B ND Hx cannot be established, THEN

dispatch operator to close IKC-56A

(aux bldg. 750+3, MM-54, room 811,

above cation demineralizer hatch),

-

RESPONSE NOT OBTAINED

c. Evaluate opening KC cross-tie valves to

establish flow from other train as

follows:

1) Open:

- IKC-1A (Tm A Aux Bldg Non Ess

Ret Isol)

- 1 KC-2B r r n B Aux Bldg Non Ess

Ret Isol).

2) Open:

IKC-5OA (Trn A Aux Bldg Non

-

Ess Sup Isol)

1 KC-538 (Tm B Aux Bldg Non

Ess Sup Isol).

-

AP/I/A15500/19

UNIT 1

-

55.

Check 1N.D-35 (ND To FWST Isol) -

CLOSED.

-

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 15 of 23

Startup of ND Pumps

PAGE NO.

89 Of 152

Rev. 15

Perform the following:

-

a. Do not continue until Steps 48

through 54 are completed.

ACT I ON/ EXPECTED RESPONSE

CAUTION

If IND-35 is being

used for feed and

bleed, NC

temperature may

rise after valve is

closed. Subsequent

steps to start ND

pump should be

performed without

delay to avoid

excessive heatup.

-

b. Notify dispatched operator to close and

-

c. Do not continue until 1ND-35 is closed,

lock 1 ND-35 (ND TO FWST 1~01).

RESPONSE NOT OBTAINED

56.

Check the following valves:

-

a. IND-1B (C NC Loop to ND Pumps) -

-

a. a

QStep 57.

-

b.- 1ND-2AC (C NC Loop To ND Pumps) -

-

b. m u s t e p 5 7

OPEN.

-

c. IND-4B (B ND Pump Suct From FWST

-

c. a m s t e p 5 8

or NC) - OPEN.

-

d. GOmStep 59

-

57.

Check 1FW-27A (FWST Supply To ND) -

CLOSED.

NOTE

Closing 1 FW-27A meets

interlock to allow opening

1ND-1B (C NC Loop to ND

Pumps) and 1ND-2AC (C NC

Loop To ND Pumps).

-

Close 1FW-27A.

I

I,

._ .

AP/I/A/5500/19

UNIT I

LOSS OF NO OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 16 of 23

Startup of ND Pumps

PAGE NO.

90 of 152

Rev. 15

I

ACTION/EXPECTED RESPONSE

58.

Realign NC to ND valves as follows:

I

RESPONSE NOT OBTAINED

I

-

a. Check 16 ND Pump discharge pressure

-WITHIN 200 PSlG OF NC

PRESSURE.

b. Open the following valves:

- 1ND-I6 (C NC Loop to ND Pumps)

- 1ND-2AC (C NC Loop To NO Pumps)

- IND-46 (E ND Pump Suct From

FWST or NC).

59.

Close the following:

IND-30A (Train A ND To Hot Leg Isol)

1ND-33 (A ND Hx Bypass)

1ND-14 (B ND Hx Outlet)

-

1NI-183B (NO TO B & C Hot Legs Isol).

-

a. Perform the following:

1) E

NC pressure is greater than ND

pump discharge pressure, THEN

-_

GO TO Enclosure 1 (Equalizing

Pressure Between NC and ND).

2) E

ND pump discharge pressure is

greater than NC pressure, THEN

contact station management for

guidance to perform the following:

a) Ensure.ND System remains

subcooled when depressurizing

ND.

b) Equalize pressure between ND

-

- and NC systems.

Dispatch operator to close affected

valve(s):

- IND-30A (aux bldg. 733+4, LL-52, room

733, ND heat exchanger room 1A. 1 ft

from east, 8 ft from south)

- IND-33 (aux bldg, 733+8. LL-52, room

732, ND heat exchanger room 16)

- 1NI-1836 (aux bldg. 733t10, FF-52,

room 602, midget hole, enter from

electrical penetration room, 4 ft from

reactor bldg wall, 3 ft from ceiling).

-

1

LOSS OF ND OR ND SYSTEM LEAKAGE

PAGE NO.

91 of 152

Rev. 15

Enclosure 14 - Page 17 of 23

Startup of ND Pumps

AP/l/A15500/19

UNIT 1

I

ACT I ON/ EXPECTED RESPONSE

RESPONSE NOT OBTAINED

1

60.

Open the following:

Dispatch operator to open affected

valve(s):

1ND-18 (B ND Hx Bypass)

- 1ND-34 (A 8. B ND Hx Bypass)

- 1NI-178B (Train B ND To C 8. D CL)

- 1ND-15B (Train B ND To Hot Leg Isol).

-

- IND-18 (aux bldg, 733+8, LL-52, room

732, ND heat exchanger room 18)

- 1NI-178B (aux bldg, 733+6. "-52,

room

730, BIT room 6 ft west of "-52,

3 ft

from reactor bldg wall)

732, ND Hx room 1B).

-

e !ND-lSB (aux bldg, 733.~8, LL-57, room

61.

Check if either of the following are

believed to have occurred:

- Air entrainment in ND System

- Voiding of NC System.

Perform the following:

NOTE

Makeup options using

IND-35 (ND TO FWST

Isol) cannot be used,

since it must be closed

prior to starting ND

pump.

-

a. IF AT ANY TIME NC level drops when

ND pump is started, THEN makeup as

required PER Enclosure 3 (NC

System Makeup During Loss of ND).

-

b. GOmStep64

NOTE

Makeup options using IND-35 (ND To FWST Isol) cannot be used, since it must

be closed prior to starting ND pump.

-

62.

Initiate makeup PER Enclosure 3 (NC

System Makeup During Loss of ND)

prior to starting ND pump, to avoid

losing level when pump is started.

LOSS OF ND OR ND SYSTEM LEAKAGE

PAGE NO.

92 of 152

Enclosure 14 - Page 18 of 23

Startup of ND Pumps

APll/A/5500/19

Rev. 15

UNIT 1

I

RESPONSE NOT OBTAINED

ACTION/EXPECTED RESPONSE

I

-

63. E voiding has occurred, THEN restore

cooling slowly in next steps, to avoid

rapid loss of level due to void collapse.

-

64.

Check core exit T/Cs -AVAILABLE.

---

GO TO Step 66.

-

65.

Check subcooling based on core exit

Perform the following:

TKs- GREATER THAN 0' F.

a. E core exit TCs indicate less tinan

200" F, THEN GO TO Step 66.

-

b. Raise makeup flow rate.

-

c. E makeup flow inadequate, THEN use

different or multiple makeup flowpaths

in Enclosure 3 (NC System Makeup

During Loss of ND).

d. E IND-35 (ND To FWST Isol) is used

for makeup, THEN ensure 1ND-35 is

closed prior to starting ND pump.

e. Attempt to restore subcooling based on

core exit T/Cs to greater than 0" F.

-

f. E subcooling restored, THEN GO TO

Step 66.

-

g. E

FWST level less than 20 inches,

~

_

THEN GO TO Step 66.

h. E subcooling cannot be restored,

THEN perform the following:

-

1) Open 1FW-27A (FWST Supply To

ND).

-

2) E

IFW-27A will not open, THEN

dispatch operator to open and

standby 1FW-27A (aux bldg. 695

pipechase, GG-52. 5 ft from north

wall).

-

3)

m S t e p 67.

AP/l/A/5500/19

UNIT 1

-

66.

Check 1 FW-27A (FWST Supply To ND) -

CLOSED.

ND pump.

-

Ensure 1FW-27A closed prior to starting

-- -

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 19 of 23

Startup of ND Pumps

PAGE NO.

93 Of 152

Rev. 15

-

67.

Do not continue until 1ND-9 (E ND Pump

Discharge Isol) throttled 2 turns open.

ACTION/EXPECTEO RESPONSE

I

RESPONSE NOT OBTAINED

-

68.

Establish communications with

operators at 1ND-9 (B ND Pump

Discharge Isol).

-

69.

Check NC level -GREATER THAN

10 INCHES.

-

Attempt to raise level.

-

70.

Check IND-17 (B ND Hx To Letdown Hx)

-

IF ND letdown in service, THEN:

- CLOSED.

Anticipate a step rise in letdown flow

- when ND pump is started in next step.

WHEN ND pump is started, THEN

- -

immediately throttle letdown flow as

required to maintain stable NC pressure

and level.

CAUTION

Starting an ND pump may result in a level drop due to shrink or the

release of trapped air.

-

71.

Start 16 ND Pump.

-

72.

Have operators &&,!open

1ND-9 (6 ND

Pump Discharge Isol) until ND flow is

1000 GPM - 1500 GPM.

-

I

LOSS OF ND OR ND SYSTEM LEAKAGE

-

73.

Check 1FW-27A (FWST Supply To ND) -

CLOSED.

Perform the following:

a.

control room operation of 1Fw-27A

-

is unavailable, THEN locally operate

IFW-27A in next steps.

-

74.

Check NC level -

4 INCHES.

b. IF AT ANY TIME FWST level goes

-

below 20 inches, THEN close

IFW-27A.

NOTE

1FW-27A (FWST Stlpply

To ND) can be throt:;ed

in the open direction only

(seals in on closed

direction).

c.

core exit TICS available, THEN:

-~

WHEN subcooling based on core exit

T/Cs is greater than 0" F, THEN

throttle or close 1FW-27A while

ensuring NC level is maintained.

d. E core exit TICS unavailable, THEN

throttle or close 1 FW-27A while

ensuring NC level is maintained.

-

GREATER THAN

Perform the following:

a. Stop ND pump.

-

b. Evaluate need to vent ND pump suction

PER Enclosure 2 (Venting of ND

Pumps and Suction Piping).

c. Makeup to the NC System PER

Enclosure 3 (NC System Makeup

During Loss of ND) until NC level is

greater than 10 inches.

d. WHEN conditions established to start

ND pump, THEN RETURN

Step 1

e. RETURN To Step in effect in body of

this procedure.

-

APll/A/5500/19

UNIT 1

I '

I

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 14 - Page 21 of 23

Startup of ND PumDs

PAGE NO.

95 of 152

Rev. 15

r

1

I

'

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

I

-

75.

Slowly throttle close IND-34 (A 8 B ND

Hx Bypass) until a drop in ND flow is

observed.

-

76.

Have operators open, backseat, and lock

1ND-9 (B ND Pump Discharge Isol).

77.

Throttle the following as necessary to

maintain stable NC temperature:

- IND-14 (B ND Hx Outlet)

- 1ND-34 (A & B ND Hx Bypass)

78.

-

79.

-

80.

-

Check NC temperature based on core

exit TIC'S - LESS THAN 200" F.

Reduce KC flow to 18 ND HX as required

to control NC temperature.

_ _ _ _ _

IF AT ANY TIME cooldown is required,

THEN REFER TO Unit 1 Data Book Curve

1.6 b (Heatup and Cooldown Limits for

LTOP).

GO TO Step 80.

_--

ACTION/EXPECTED RESPONSE

81.

Check feed and bleed cooling .

INITIATED.

RESPONSE NOT OBTAINED

I

-_

GO TO Step 82.

-

a. Initiate cooldown to 200°F on core exit

TIC'S.

b. WHEN NC temperature is less than

200° F on core exit TIC'S, THEN

perform the following:

CAUTION

Failure to stop makeup to NC System prior to closing Pzr PORVs

may cause low temperature over pressure concern.

-

1) Stop or reduce makeup to NC

System.

2) E PORV (s) not required open as

vent path, AND makeup to NC

System stopped, THEN:

_. a) Close PZR PORVs.

-

b) Place closed Pzr PORVs in

"AUTO.

-

3) Control ND flow to maintain NC

System subcooled.

-

82.

Ensure ND flow greater than 1500 GPM.

-

83.

Dispatch operator to reclose breaker

IEMXBl - 2C (1B ND Pump & Hx Miniflow

lsol Motor (1ND-678)).

-

84.

Ensure IND-676 (6 ND Pump 8 B Hx

Miniflow) remains closed.

-- -

-9

LOSS OF ND OR ND SYSTEM LEAKAGE

PAGE NO.

96 Of 152

Rev. 15

Enclosure 14 - Page 22 of 23

APlllN5500119

UNIT 1

-,

Startup of ND Pumps

_- -

LOSS OF ND OR ND SYSTEM LEAKAGE

-

Enclosure 14 - Page 23 of 23

Startup of ND Pumps

PAGENO.

97 Of 152

Rev. 15

AP/l/A/5500/19

UNIT 1

I

RESPONSE NOT OBTAINED

ACTIONlEXPECTEO .RESPONSE

I

85.

air entrainment may have occurred on

the idle train, THEN:

-

a. Remove noncondensible gases from

idle ND Hx PER Enclosure 15 (Idle ND

Train Hx Flush).

-

b. Ensure idle train vented PER Enclosure

2 (Venting of ND Pumps and

Suction Piping).

-

86.

RETURN

step in effect in body of this

procedure.

RO

REFERENCE

Radioactive Liquid Effluent Monitoring Instrumentation

16.11.2

16.1 1 RADIOLOGICAL EFFLUENT CONTROLS

16.1 1.2 Radioactive Liquid Effluent Monitoring Instrumentation

R

COMMITMENT

The radioactive liquid effluent monitoring instrumentation channels

shown in Table 16.1 1.2-1 shall be OPERABLE with their Alarflrip

Setpoints set to ensure that the limits of SLC 16.1 1.1 are not

exceeded.

AND

The AlarMrip Setpoints of these channels shall be determined and

adjusted in accordance with the methodology and parameters in the

OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY

At all times.

..

- A

CONDITION

A.

One or more radioactive

liquid effluent monitoring

channels Alarm/Trip

setpoint less

conservative than

required.

B.

One or more radioactive

liquid effluent monitoring

instrument channels

REQUIRED ACTION

A.l

Suspend the release of

radioactive liquid effluents

monitored by the affected

channel.

-

A.2

Declare the channel

-

A.3

Adjust setpoint to within

limit.

6.1

Enter the Remedial Action

specified in Table 16.1 1.2-

1 for the channel(s).'

COMPLETION TIME

Immediately

...

McGuire Units 1 and 2

16.1 1.2-1

(continued)

Revision 23

REMEDIAL ACTIONS (continu

T

CONDITION

C.

One channel inoperable

~

-~ -

-

Radioactive Liquid Effluent Monitoring Instrumentation

-

16.11.2

REQUIRED ACTION

C.1 .I Analyze two independent

samples per TR 16.11 .I .l.

AND

C.1.2 Perform independent

verification of the dischargc

line valving.

AND

C.1.3.1 Perform independent

vsrification of manual

portion of the computer

input for the release rate

calculations performed by

computer.

2.1.3.2Perform independent

verification of entire

release rate calculations

for calculations performed

manually.

AND

>.I .4 Restore channel to

OPERABLE status.

2.2

Suspend the release of

radioactive effluents via

this pathway.

...

McGuire Units 1 and 2

16.1 1.2-2

COMPLETION TIME

Prior to initiating a

release

Prior to initiating a

release

Prior to initiating a

release

Prior to initiating a

release

14 days

rnmediately

continued)

Revision 23

Radioactive Liquid Effluent Monitoring Instrumentation

16.11.2

REMEDIAL ACTIONS (continue

CONDITION

D.

One channel inoperable.

. - .

E.

One or more channels

REQUIRED ACTION

D.l

D.2

Perform an analysis of grat

samples for radioactivity at

a lower limit of detection

per Table 16.1 1 .I -1.

Restore the channel to

OPERABLE status.

E.1

Perform an analysis of grab

samples for radioactivity at

a lower limit of detection

Der Table 16.1 1 .I -1.

E.2

Restore the channel to

OPERABLE status.

.-

McGuire Units I and 2

16.1 1.2-3

COMPLETION TIME

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

during releases

when secondary

specific activity is

> 0.01 pCi/gm DOSE

EQUIVALENT 1-131

3nce per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

juring releases

!!hen secofidary

specific activity is

5 0.01 pCi/gm DOSE

EQUIVALENT 1-131

30 days

lnce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

juring releases

10 days

continued)

Revision 23

Radioactive Liquid Effluent Monitoring Instrumentation

16.11.2

-

REMEDIAL ACTIONS (continue

,'

CONDITION

F.

One or more flow rate

measurement channels

G.

RC minimum flow

interlock inoperable.

H.

Required Action and

associated Completion

Time of Condition C, D.

E, F, or G not met.

REOUIRED ACTION

Estimate the flow rate of

the release.

-.2

Restore the channel to

OPERABLE status.

.I

Verify that the number of

pumps providing dilution is

greater than or equal to the

number of pumps required.

\\ND

i.2

Restore the channel to

OPERABLE status.

1.1

Explain why the

inoperability was not

corrected within the

specified Completion Time

in the Annual Radioactive

Effluent Release Report.

McGuire Units 1 and 2

16.1 1.2-4

COMPLETION TIME

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

during releases

30 days

3nce per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

juring releases

30 days

n the next

icheduled Annual

qadioactive Effluent

jelease Report

Revision 23

TEST

TR 16.1 1.2.1 Perform CHANNEL CHECK.

Perform CHANNEL CHECK.

~~

~

~~

TR 16.1 1.2.3 Perform SOURCE CHECK.

TR 16.1 1.2.4 Perform SOURCE CHECK.

TR 16.1 1 ,2,5 ----------------.----------------NOTES--------------------------------

1. For Instrument 1, the COT shall also demonstrate that

automatic isolation of the pathway occurs if the

instrument indicates measured levels above the

AlarmlTrip Setpoint.

2. For Instruments 1 and 2, the COT shall also

demonstrate that control room alarm annunciation

occurs if the instrument indicates measured levels

above the Alarmnrip Setpoint; circuit failure and, a

downscale failure.

...........................................................................

Perform CHANNEL OPERATIONAL TEST.

TR 16.1 1.2.6 Perform a CHANNEL CALIBRATION.

FREQUENCY

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

during periods of

release

Prior to each

release

31 days

32 days

18 months

(continued)

.-

McGuire Units 1 and 2

16.1 1.2-5

Revision 23

Radioactive Liquid Effluent Monitoring Instrumentation

-

16.11.2

TESTING REQUIREMENTS (continued)

TEST

TR 16.1 1 2.7 ----------------------------NOTE--------------------------------------

The initial CHANNEL CALIBRATION shall be performed

using standards certified by the National Institute of

Standards and Technology (NIST) or using standards

obtained from suppliers that participate in measurement

assurance activities with NIST. These standards shall

permit calibrating the system over its intended range of

energy and measurement range. For subsequent

CHANNEL CALIBRATION, sources that have been

related to the initial calibration shall be used.

Perform a CHANNEL CALIBRATION.

___________________________.____________---~------------------------------

FREQUENCY

24 months

McGuire Units 1 and 2

16.1 1.2-6

Revision 23

,--...

..,..;

RADIO CTIVE

Radioactive Liquid Effluent Monitoring Instrumentation

16.11.2

TABLE 16.11.2-1

.IQUID EFFLUENT MONITORING INSTRUMENTATION

INSTRUMEN?

1.

Radioactivity Monitors Providing Alarm And Automatic

Termination 01 Release

a.

Waste Liquid Elfluent Line (EMF-49)

b.

EMF-49 Minimum Flow Device

c.

Containment Ventilation Unit Condensate Line

(EMF-44)

d.

EMF-44 Minimum Flow Device

2.

Radioactivity Monitors Providing Alarm But Not

Automatic Termination of Release

a. Conventional Waste Water Treatment Line

or Turbine Building Sump to RC (EMF-31)

.. .

b. EMF-31 Minimum Flow Device

3. Continuous Composite Samplers

a.

Containment Ventilation Unit Condensate Line

b.

Conventional Waste Water Treatment Line

c.

Turbine Building Sump to RC

c -

...

McGuire Units 1 and 2

16.1 1.2-7

MINIMUM

CHANNELS

0 PER ABLE

1 per station

1 per stalion

1

f

1

1 per Station

1

REMEDIAL

ACTION

A, C. H

C. H

A. E. H

E. H

A. D. H

D, H

E. H

TESTING

REQUIREMENTS

TR 16.11.2.1

TR 16.11.2.3

TR 16.11.2.5

TR 16.11.2.7

TR 16.11.2.5

TR 16.11.2.7

TR 16.:1.2.1

TR 16.11.2.4

TR 16.11.2.5

TR 16.11.2.7

TR 16.11.2.5

TR 16.11.2.1

TR 16.11.2.4

TR 16.11.2.5

TR 16.11.2.7

TR 16.11.2.5

TR 16.11.2.7

7

TR 16.11.2.2

TR 16.11.2.5

TR 16.11.2.6

TR 16.11.2.2

I

TR 16.1 1.2.5

TR 16.11.2.6

TR 16.11.2.2

TR 16.11.2.6

(Continued)

Revision 23

~~

.

..,I.

Radioactive Liquid Effluent Monitorina Instrumentation . .A$$

/'--*

4.

Flow Rate Measurement Devices

..,.

a.

Waste Liquid Effluent Line

b.

Containment Ventilation Unit Condensate Line

c.

Conventional Waste Water Treatment Line

d.

Turbine Building Sump to RC

5.

RC Minimum Flow Interlock (1)

1 per station

1

1 per station

1

1 per station

. . -;i

' :.A

.,,,,

. . . ,.: j: ..;

. .

. . .

. .

.

./,,

,

.

,

. ...

.I ,

E . .; ..

TR 16.11.2.2

TR 16.11.2.5

TR 16.11.2.6

TR 16.11.2.2

TR 16.11.2.5

TR 16.11.2.6

TR 16.11.2.2

TR 16.11.2.5

TR 16.11.2.6

TR 16.11.2.2

TR 16.11.2.6

TR 16.11.2.5

NOTES:

1,

Minimum flow dilution is assured by an interlock which terminates waste liquid release if the number of RC pumps

running falls below lhe number of pumps required for dilution. The required number of RC pumps for dilution is

determined per station procedures.

BASES

The radioactive liquid effluent instrumentation is provided to monitor and control, as

applicable, the releases of radioactive materials in liquid effluents during actual or potential

releases of liquid effluents. The Alarflrip Setpoints of these instruments shali be

calculated and adjusted in accordance with the methodology and parameters in the ODCM

to ensure that the Alarflrip will occur prior to exceeding the limits stated in SLC 16.1 1 .I.

The OPERABILITY and use of this instrumentation is consistent with the requirements of

General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR'Part 50. The Turbine

Building Sump to RC Discharge Flow Measurement and Sampler Devices are for monitoring

only and-do not alarm or have any controls that require a quarterly COT.

REFERENCES

1. McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

2. 10 CFR Part 50, Appendix A

McGuire Units I and 2

16.1 1.2-8

Revision 23

.-

REACTOR TRIP OR SAFETY INJECTION

PAGE NO.

I

E PI1 lA/SOOO/E-0

UNIT 1

Enclosure 3 - Page 1 of 3

Uncontrolled NC System Cooldown

I

. , , RESPONSE NOT OBTAINEO

ACTION/EXPECTED RESPONSE

%heck steam dump valves -CLOSED.

I

- 1.

Close steam dump valves as follows:

-

a. Place "STEAM DUMP'SELECT" in

-

b.

steam pressure mode.

steam dumps still open, THEN place

"STM PRESS CONTROLLER" in

manual and close.

c.

steam dumps still open, THEN select

"OFF RESET" on the following

switcnes:

"STEAM DUMP INTLK BYPASS

-

CHANNEL A

- "STEAM DUMP INTLK BYPASS

CHANNELB".

-

2.

Check all SM PORV(s) -CLOSED.

Perform the following:

a. Close affected SM PORV manual

loader.

b. E SM PORV can not be closed. THEN:

- 1) Close its isolation valve

-

2) E SM PORV isolation valve can not

be closed, THEN dispatch operator

to close SM PORV isolation valve.

-

- 3.

Check MSR "RESET" light - LIT.

Perform the following on MSR controls:

-

a. Depress "SYSTEM MANUAL"

-

b. Depress "RESET".

REACTOR TRIP OR SAFETY INJECTION

PAGE NO.

33 of 34

Rev. 18

Enclosure 3 - Page 2 of 3

Uncontrolled NC System Cooldown

P111N5000/-0

UNIT 1

I

. RESPONSE NOT OBTAINED

ACTION/EXPECTED RESPONSE

-

4. 'Check any NC pump -ON.

Perform the following:

-

a.

any NC T-Cold is still going down,

---

THEN GO TO Step 6.

-

b. IF cooldown stopped, THEN exit this

enclosure.

-

5.

Check NC T-Ave -GOING DOWN.

_ -

IF cooldown stopped, THEN exit this

,

I

enclosure.

6.

Control feed flow as follows:

a.

SIG NIR level is less than 11%

(32% ACC) in all S/Gs,

feed flow to achieve the following:

throttle

- Minimize cooldown

- Maintain total feed flow greater than

450 GPM.

b. WHEN N/R level is greater than 11%

(32% ACC) in at least one SIG. THEN

throttle feed flow further to:

- Minimize cooldown

-Maintain at least one S/G N/R level

- greater than 11% (32% ACC).

-

7.

Check MSlVs - ANY OPEN

-

8.

Close 1SM-15 (SM To 2nd Stage MSR).

Perform the following:

-

a. Close MSlV bypass valves

-

b. Exit this enclosure.

ACTION/EXPECTED RESPONSE

9.

Check any NC pump - ON.

Perform the following:

-

,

EPll/A/5000/E-0

UNIT 1

REACTOR TRIP OR SAFETY INJECTION

Enclosure 3 - Page 3 of 3

Uncontrolled NC System Cooldown

PAGE NO

34 of 34

Rev. 18

-

10.

Check NC T-Ave -GOING DOWN.

-

11.

Notify Control room SRO that cooldown

is continuing.

12. E

cooldown continues, THEN close:

- All MSlVs

- All MSlV bypass valves.

-

a.

any NC T-Cold is still going.down,

THEN GO TO Step 11.

____

-

b.

cooldown stopped, THEN exit this

enclosure.

_ -

IF cooldown stopped, THEN exit this

enclosure.

Duke Power Company

(1) ID No."EP/l/A/500Q/

ES-1.1

(R0441)

PROCEDURE PROCESS RECORD

Revwon No. 016

PREPARATION

I

~

ONLY

(2) Station

McGuire Nuclear Station

(3) Procedure Title

(4) Prepared 8);

Weiner,Michael R

Date September 20,2002

Safety Injection Termination

-l

(5) Requires NSD 228 Appicability Determination? If Applicability Determination is required. attach NSD 228 documenfatior

@ Yes

0

No

(New procedure or revision with major changes)

(Revision with minor changes)

No

(To

(6) Reviewed By

(QR)

Cross-Disciplinary Review By

Reactivity Mgmt. Review By

(OR) N A d A Date

Mgmt. Involvement Review By

(OPS Supt.) NAJrt'

Date

(7) Additional Reviews

Reviewed By

D.tte

Reviewed By

Date

(8) Temporary Approval (ifnecessaM

BY

(OSM/QR) Date

BY

(OR)

(9) Approved By

Date

PERFORMANCE (Compare wifh Conlrol Copy every 14 calendar days while work is beingperfomed.)

(10) Compared with Control Copy

Dale

Compared with Control Copy

Date

Compared with Control Copy

Date

(1 1) Date(s) Performed

Work Order Number (WO#)

COMPLETION

(12) Procedure Complelion Verification

0

Yes 0 NA

0 Yes

NA

0 Yes 0

NA

0

Yes 0

NA

0

Yes 0

NA

Verified By

-

Date

(1 3) Procedure Completion Approved

-

__ Date

(1 4) Remarks (Arlach addilionalpage's. ;/necessary.)

Check lists and/or blanks initialed. signed, dated, or filled in NA. as appropriat"?

Required enclosures attached?

Data sheets attached. completed. dated and signed?

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

Prccedure requirements met?

M N'S

SAFETY INJECTION TERMINATION

EP/I/A/50001ES-1 .I

I

UNIT1

-

PAGE NO.

1 Of 49

Rev. 16

I '

I

A. Purp'ose

This procedure'provides the necessary instructions to terminate safety injection and

stabilize plant conditions,

13. -toms

or Entry Conditions

This procedure is entered from:

e EP/l/A/5000/E-O (Reactor Trip Or Safety Injection), Step 35, EP/l/A/5000/E-I (Loss Of

Reactor Or Secondary Coolant), Step 7, and EP/I/A/5000/E-2 (Faulted Steam Generator

Isolation). Step 12 when specified termination criteria are satisfied.

EP11/A/5000/FR-H.I (Response To Loss Of Secondary Heat Sink). Step 50. after

secondary heat sink has been reestablished and S/I has been terminated.

PAGE NO.

2 Of 49

Rev. 16

IT

SAFETY INJECTION TERMINATION

EPll/A/5000/ES-1. I

UNIT 1

I'

I

ACTlONlEXPECTED RESPONSE

RESPONSE NOT OBTAINED

1

I

1

C. Operator Actions

-

1.

Monitor foldout page.

2.

Reset the following:

a. SII.

-

b. Sequencers

-

c. Phase A Isolation

-

d. Phase B Isolation

3.

IF AT ANY TIME a BIO signal occurs,

THEN restart SI1 equipment previously

on. '-

-

a. Perform the following:

-

1) Dispatch operator to open reactor

trip breakers.

-

2) Reset SI.

b. Dispatch operator to open breaker for

affected sequencer DC control power:

A Train - IEVDA Breaker 6

B Train - IEVDD Breaker 8.

-

I

R

SAFETY INJECTION TERMINATION

EP/1/A/SOOO/ES-1 .1

UNIT 1

PAGE NO.

3 Of 49

Rev. 16

ACTION/EXPECTED RESPONSE

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

Isol)

RESPONSE NOT OBTAINED

- IVI-1608 (E Ess Hdr Cont Outside

Isol)

- 1VI-1508 (Lwr Cont Non Ess Cont

Outside Isol).

-

b. Check VI header pressure - GREATER

THAN 85 PSIG.

I

,

b. Perform the following:

1) Align N2 to all PORVs by

opening:

- 1NI-430A (Emerg N2 From CLA

INI-431B (Ernerg N2 From CLA

To INC-326 & 368).

TO 1 NC-34A)

-

2) Restore VI PER AP/I/A/5500/22

(Loss Of VI).

-

5.

Stop all but one NV pump.

-

6.

Check NC pressure - STABLE OR GOING

UP.

Perform the following:

-

a. Ensure Pzr spray valves are closed

-

b.

NC pressure is still going down,

THEN GO TO EP/I/A/5000/ES-1.2

(Post LOCA Cooldown And

Depressurization).

SAFETY INJECTION TERMINATION

PAGE NO.

UNIT 1

Rev. 16

1

EP/1/A/5000/ES-1,1

4 of 49

t

I L

I

-1 -

I

ACT1 ON/EXPECTEO RESPONSE

RESPONSE NOT O E T A l N E D

7. ..Isolate NV S/I flowpath:

-

a. Check NV pump - SUCTION ALIGNED

TO FWST.

a. E suction aligned to discharge of ND

pumps in S/I Recirc mode, m:

EP/I/A/5000/G-l (Generic

Enclosures), Enclosure 18

(Aligning Normal Charging With

NV Recirc Path Isolated).

- 1) Realign charging pEJ

I ,

-

2) a m s t e p 9

b. Check NV pumps miniflow valves -

b. Perform the following:

OPEN:

-

1) Open valves.

-

2) E both valves open, THEN GO TO

3) E either valve closed, THEN:

a) Dispatch operator to open

- 1 NV-150B (NV Pumps Recirculation)

- INV-15lA (NV Pumps Recirculation).

Step 7.c.

valve(s):

- INV-1508 (aux bldg, 716+8,

"-55, room 627, NV pump

room I A , west of pump motor)

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

"-55,

room 627, NV pump

room IA, west of pump

motor).

-

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 1NV-1508 and

INV-151A open, THEN charging

flow may be throttled to less

than 60 GPM.

-

d) a m S t e p 9

SAFETY INJECTION TERMINATION

EP/1/A/5000/ES-1 .I

Rev. 16

I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

1

7. (Continued)

c. Close the following valves:

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

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

8.

Establish charging:

-

a. Check VI header pressure - GREATER

THAN 60 PSIG.

c. Dispatch operator to close valve(s):

-

0 INI-9A (aux bldg. 733~12,

JJ-52,

room 730, VCT hallway 1 ft south of

JJ-52)

-

w 1NI-108 (aux bldg, 733t4, JJ-51,

room 730, VCT hallway 1 ft south of

JJ-51).

a. Perform the following:

1) Dispatch operators to perform the

following and standby:

- Loosen lock nut and throttle

handwheel on INV-238

(Charging Line Flow Control) (aux

bldg, 716~3, -54.

room 629,

PD Pump room) to maintain

6-10 GPM seal injection flow to

each NC pump.

- Loosen lock nut and close

handwheel on INV-241 (Seal Inj

Flow Control) (aux bldg. 716t.9,

-52,

room 603, above BW

pumps).

(RNO continued on next page)

EP/1/Af5000/ES-1.1

UNIT 1

I

1

I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

1

8. (Continued)

PAGE NO.

6 of 49

Rev. 16

ff

SAFETY INJECTION TERMINATION

2) WHEN 1 NV-241 .is locally closed,

-

AND 1 NV-238 is locally throttled,

T":

a) Open the following:

- 1 NV-244A (Charging Line

Cont Outside Isol)

- I NV-2456 (Charging Line

Cent Outside {sol).

b) ci: 1 NV-244A or 1 NV-245E

closed, f"

dispatch operator

to open valve(s):

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

"-52,

room 603, above BW

- 1 NV-2455 (aux bldg, 716+11,

"-52.

room 603, west of EW

pumps)

pumps).

-

c) Place 1 NV-238 (Charging Line

Flow Control) controller in

manual and fully open.

-

d) Place 1NV-241 (Seal Inj Flow

Control) manual loader fully

open.

3) IF AT ANY TIME charging flow is

required to be controlled in

subsequent steps.-

have

dispatched operators locally adjust

flow rate as follows:

Slowly throttle handwheel on

-

1 NV-241.

- Throttle handwheel on 1 NV-238

while maintaining NC pump seal

iniection flow.

- M'aintain charging flow less than

175 GPM.

4) GOTO Step 9

-

f I

SAFETY INJECTION TERMINATION

PAGE NO.

PI1 lAl5000lES- 1.1

7

Of 49

Rev. 16

UNIT 1

I

-

ACTION/EXPECTEO RESPONSE

RESPONSE NOT OBTAINED

8. (Continued)

-

b. Throttle.1NV-238 (Charging Line Flow

Control) to maintain 6-10 GPM seal

injection flow to each NC pump.

-

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

d. Open the following valves:

d. Dispatch operator to open valve(s):

- INV-244A (Charging Line Cont

Outside Isol)

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

-52,

room 603, above BW pumps)

- INV-245B (Charging Line Con1

- INV-2458 (aux bldg, 716+11, -52,

room 603, west of BW pumps).

Outside Isol).

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

NC pump seal injection flow.

- Maintain charging flow less than

175 GPM.

f f

SAFETY INJECTION TERMINATION

PAGE NO.

EP~1~A/5000/ES-l.l

8 of 49

Rev. 16

UNIT 1

-

ACT1 ON/EXPECTED RESPONSE

I

RESPONSE NOT OBTAINED

1

-

9. .pontrol charging flow as required to

maintain stable Pzr level.

Perform the following:

-

a. Attempt to stabilize Pzr level by raising

charging flow (maximum 175 GPM).

-

b. IF Pzr level stabilizes or is going up,

THEN GO TO Step 10.

__--

c. IF Pzr level continues to go down,

T":

1) Oper; the following:

INI-9A (NC Cold Leg Inj From

INI-108 (NC Cold Leg Inj From

-

NV)

-

NV).

2) Close the following:

Outside Isol)

Outside Isol).

INV-244A (Charging Line Cont

INV-245B (Charging Line Cont

-

3) a

EP/I/A/5000/ES-1.2 (Post

LOCA Cooldown And

Depressurization)

I I

SAFETY INJECTION TERMINATION

PAGE NO.

EP/I/N5000/ES-l .I

9 Of 49

Rev. 16

UNIT 1

1

ACTION/EXPECTED RESPONSE

RESPONSE NOT O B T A I N E D

I

I O . ,?heck if NI pumps should be stopped:

a. Check NC pressure -

a. Perform the following:

I

- STABLE OR GOING UP

- GREATER THAN 1600 PSIG.

-

1)

Pzr level is going down, THEN

attempt to stabilize Pzr level by

raising charging flow (maximum

175 GPM).

2) E T-Ave less than 350" F prior to

event,

NC pressure stable or

going up, THEN GO TO Step 10.b.

-

I

1) Close Pzr spray valves.

I

e. Check if main steamlines intact:

-

e.

any S/G is faulted, THEN do not

- All S/G pressures - STABLE OR

continue until faulted SIG

depressurization stops or NC pressure

-GOING UP

starts going up.

- All S/GS

~ PRESSURIZED

If Pzr heaters are off, NC pressure may go down slowly due to ambient losses

and Pzr spray bypass flow. This may be considered "stable" pressure.

f.

Check NC pressure - STABLE OR

I I

- GOING UP.

I

-

f.

EP/I/A/5000/ES-1.2 (Post

LOCA Cooldown And

I

Depressurization).

I

I I

SAFETY INJECTION TERMINATION

PAGE NO.

EP/1/A/5000/ES-1 1

10 of 49

Rev. 16

UNIT 1

\\ \\

I

A C T I O N I E X P E C T f O RESPONSE

RESPOllSE NOT OBTAINED

I

10 .(Continued)

-

g. Check NC pressure - GREATER THAN

g. Perform the following:

1600 PSIG.

NOTE

The intent of the next

step is to see if NC

pressure will recover

to above the shutoff

head of the NI pumps

(1600 PSIG). If

pressure is

recovering, this step

will wait to see if SI

termination should be

completed in this EP.

1) 00 not continue until one of the

following is met:

- NC pressure goes above

1600 PSIG.

- NC pressure stabilizes below

1600 PSIG.

NC pressure starts going down

-

2)

NC pressure goes above

-

1600 PSIG. THEN GO TO

Step 10.h.

3) IF NC pressure remains below

1600 PSIG, THEN GO TO

EP/l/A/5000/ES-I .2 (Post LOCA

Cooldown And Depressurization).

-

h. Stop NI pumps.

11.

Check if ND pumps should be stopped:

-

a. Check NO pumps suction -ALIGNED

-

a. GOTAStep 12

TO FWST.

-

b. Stop ND pumps.

I

M NS

I I EP/lIA/5000/ES-1.1

x

SAFETY INJECTION TERMINATION

PAGE NO.

I

110f49

1

Rev. 16

UNIT 1

J

I

ACTfON/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

I

12. ,Check SA flow not required:

a. NC subcooling based on core exit T/Cs

a. Perform the following:

-

- GREATER THAN 0" F.

1) Raise SI flow to restore subcoolina

u

as follows:

Start one or more S/I pumps

- . necessary, THEN realign NV

S/l flow path:

' I

-

a)

suction aligned to VCT,

THEN realign to FWST or to

discharge of NO pumps in SI1

Recirc mode.

b) Realign discharge as follows:

(1) Open the following:

0 INI-9A (NC Cold Leg

- Inj From NV)

1NI-1OB (NC Cold Leg

-

Inj From NV).

(2) Close the following:

- 1 NV-244A (Charging

Line Cont Outside Isol)

1 NV-2458 (Charging

Line Cont Outside

-

Isol).

Reactor Or Secondary Coolant).

-

2)

EP/l/A/5000/E-I (LOSS Of

b. Pzr level - GREATER THAN 11 %

b. Perform the following:

-

(29% ACC).

-

1) Control charging flow to maintain

Pzr level.

-

2)

Pzr level can be maintained with

normal charging, THEN GO TO

3) Raise SII flow to restore level as

follows:

- Start one or more S/i pumps,

-

a)

suction aligned to VCT,

THEN realign to FWST or to

discharge of ND pumps in S/I

Recirc mode.

b) Realign discharge as follows:

(1) Open the following:

INI-9A (NC Cold Leg

(2) Close the following:

- 1 NV-244A (Charging

- INV-2455 (Charging

Line Cont Outside Isol)

Line Cont Outside

-

4) a EP/I/A/5000/E-l (LOSS

Of

Reactor Or Secondary Coolant).

EPll/AJ5000/ES-1.1

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINEO

1

13. ..Check if NS pumps should be stopped:

a. Any NSpump - ON.

a. Perform the following:

-

1) IF AT ANY TIME while in this

procedure an NS pump starts,

THEN perform Step 13.

-

2) a m s t e p 14.

b. Containment pressure - LESS THAN

b. Perform the following:

-

1) E NS pump suction has been

aligned for Cold Leg Recirc, THEN

--

GO TO Step 14.

2) IF AT ANY TIME containment

pressure is less than 2 PSIG, AND

NS pump suction is still aligned to

FWST, THEN perform Step 13.

-

3) ==Step

14.

-

c. Check operating NS pump($ suction -

-

c. G O m S t e p 14.

ALIGNED TO FWST.

-

d. Check operating NS purnp(s) - HAVE

REMAINED RUNNING SINCE INITIAL

PHASE '2 SIGNAL.

-

d. E NS pump@) had been previously

been stopped and restarted, THEN GO

-

TO Step 14.

e. Reset Containment Spray.

-

f. Stop NS pumps.

g. Close the following:

- INS-29A (A NS Pump Disch Cont

Outside Isol)

INS-158 (8 NS Pump Disch Cont

Outside Isol)

- INS-12'2 (6 NS Pump Disch Cont

Outside Isol).

SAFETY INJECTION TERMINATION

"

PAGE NO.

EP/1/A/5000/ES-1.1

14 Of 49

Rev. f6

ACT I ONlEXPECTED RESPONSE

RESPONSE NOT O B T A I N E D

1

7

14.

~ Check steam dumps as follows:

a. Check condenser available:

a. Perform the following:

- "C-9 COND AVAILABLE FOR

-

1) E

SM PORV Reset lights are lit,

---

THEN GO TO Step 14.9.

STEAM DUMP" status light (13-18) -

I IT

LI I .

MSlVs on intact S/Gs - OPEN

-

2) E any SIG pressure is less than

775 PSIG, OR is faulted, THEN:

-

a) Ensure NC System

depressurized to less than

1955 PSIG.

-

b) Ensure Lo:v Pressure Steamline

Isolation signal is blocked.

c) Maintain NC pressure less than

1955 PSIG.

-

3) Reset Main Steam Isolation.

-

4) Close SM PORV manual loaders.

-

5) Select "MANUAL" on "SM PORV

MODE SELECT".

-

6) Reset SM PORVs.

-

7) Request STA to assist in monitoring

NC pressure and temperature.

CAUTION

If Pzr is solid,

lowering intact

SIG pressures

too rapidly can

cause a loss of

NC subcooling.

NOTE

Quickly stabilizing NC

temperature will help

prevent overfilling

Pzr.

-

8) Manually operate intact S/G(s) SM

PORVs as required to stabilize NC

T-Hots.

(RNO continued on next page)

'.

SAFETY INJECTION TERMINATION

"

PAGE NO.

EPlllN5000lES-1 .I

15 Of 49

UNIT 1

Rev. 16

I

RESPONSE NOT O B T A I N E D

ACTIONIEXPECTED RESPONSE

14. (Continued)

9)

NC pressure starts dropping,

THEN perform !he following as

required to maintain stable NC

pressure:

Raise charging flow.

Operate Pzr heaters

10) IF AT ANY TIME all of the

following conditions are met:

-

All intact SIG pressures are at

-

1100 PSIG.

- NC T-Hots are stable

- Pzr steam bubble exists.

THEN SM PORVs may be

selected to auto as follows:

-

a) Place "SM PORV MODE

SELECT SWITCH" to "AUTO",

-

b) Slowly throttle intact S/G SM

PORV manual loaders fully

open.

-

11) G O m S t e p 14.9.

b. 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.

-

c. Check"P-12 LO-LO TAVG" status light

-

c. Place steam dumps in bypass interlock.

(ISI-18) - DARK.

-

d. Control steam dumps to maintain NC

T-Hots - STABLE.

e. IF AT ANY TIME "STEAM HEADER

PRESSURE is at 1092 PSIG AND

auto control desired, THEN perform the

following:

-

1) Ensure "STM PRESS

CONTROLLER setpoint at

1092 PSlG (pot setting of 8.4).

2) Place,"STM PRESS

CONTROLLER" in auto

-

3) Ensure steam dumps open as

required to control "STEAM

HEADER PRESSURE at

1092 PSIG.

-

f. GO To Step 15.

-

g. Place "STM PRESS CONTROLLER" in

manual and close.

-

h. Place "STEAM DUMP SELECT" in

steam pressure mode.

I

SAFETY INJECTION TERMINATION

PAGE NO.

EP/1/N5000/ES-l. 1

16 Of 49

Rev. 16

I '

I

1 -

c

ACTIONIEXPECTEO RESPONSE

RESPONSE NOT OBTAINED

1

-

15.

Check NC T-Hots -STABLE

16.

Check if letdown can be established:

-

a. Pzr level - GREATER THAN 25%

(50% ACC).

Control steam flow and total feed flow as

required to stabilize NC T-Hots.

-

a. Perform the following:

I

1) W

m

Pzr level goes above 25%

(50% ACC). THEN perform Step 16.

-

2) Observe Note prior to Step 17 and

G

o

T o Step 17.

- - . .-,

SAFETY INJECTION TERMINATION

EPl1lAl50001ES-1 .I

170f49 11

UNIT 1

Rev. 16

J

r

I

ACTIONIEXPECTEO RESPONSE

I

RESPONSE NOT OBTAlNED

I J

16. (Continued)

-

b. Check ND pumps - OFF.

b. Perform the following:

f ) E VI pressure is greater than

60 PSIG, THEN:

a) Close one of the following

valves:

IKC-149 (A KF Hx Outlet

Flow)

-

IKC-156 (B KF Hx Outlet

Flow).

-

b) WHEN aligning KC in next

steps, THEN throttle KC flow to

ND Hx to 2000 GPM instead of

isolating flow to ND Hx.

c) m m S t e p 16.c

-

2)

VI pressure is less than 60 PSIG,

T":

a) IF AT ANY TIME while in this

procedure, VI pressure is

restored, THEN perform Step 16.

-

b) Observe Note prior to Step 17

and GO

Step 17.

-

c. Open the following:

- IKC-1A (Trn A Aux Bldg Non Ess

Ret Isol)

IKC-2B (Trn B Aux Bldg Non Ess

Ret Isol).

-

d. Monitor the following while aligning KC

to aux bldg non essential header:

KC surge tank levels

-

KC System flow.

-

I I

I

EP/l/A/500O/ES-l.l

UNIT 1

SAFETY iNJECTlON TERMINATidN

.

PAGE NO. '

18 of 49

Rev. 16

ACTION/EXPECTEO RESPONSE

g. Perform the following concurrently:

- Close 1KC-56A (KC To A ND Hx).

- As flow goes down, open IKC-5OA

(Trn A Aux Bldg Non Ess Sup Isol).

RESPONSE NOT OBTAINED

-

h. Check IKC-2B -OPEN.

h. E IKC-2B will not open, THEN perform

the following:

-

1) Close 1KC-818 (KC To B ND Hx).

-

2)

Step 16.j.

i. Perform the following concurrently:

- Close 1KC-81B (KC To B ND Hx).

As flow goes down, open IKC-538

(Trn B Aux Bldg Non Ess Sup Isol).

-

j.

Reset modulating valves using reset

buttons on RN control board.

UNIT 1

EP/l/A/SOOO/ES-I. 1

ACTION/EXPECTED RESPONSE

I

PAGE NO.

19 of 49

Rev. 16

..

SAFETY INJECTION TERMINATION

RESPONSE NOT OBTAINEO

I

-

16.' (Continued)

k. Check:

k. Perform the following:

- 1EMF-51A (Containment Train A (Hi

Range)) - LESS THAN 25 RlHR

-

1) Establish excess letdown to NCDT

PER EP/I/A/5000/G-l (Generic

~~

Enclosures), Enclosure 2

- IEMF-51B (Containment Train B (Hi

(Establishing Excess Letdown).

Range)) - LESS THAN 25 R/HR.

-

2) Notify station management to

evaluate performing Step 16 I with

high activity levels in the NC

System.

,

I

-

3) Observe Note prior to Step 17 and

_ _

GO TO Step 17.

-

I.

Establish letdown PER

-

I.

Establish excess letdown PER

Enclosures), Enclosure 2

(Establishing Excess Letdown)

EP/l/A/5000/G-1 (Generic

EP/I/A/5000/G-I (Generic

Enclosures), Enclosure 1

(Establishing Normal Letdown).

NOTE

A boric acid flow control pot setting of 6.5 ensures VCT makeup is greater than

cold shutdown boron concentration.

17.

Check VCT makeup control system:

-

a. Ensure makeup set for greater than NC

shutdown boron concentration.

-

b. Ensure NC System makeup controller in

"AUTO".

-

c. Place NC System makeup switch to

"START"

SAFETY INJECTION TERMINATION

20 of 49

Rev. 16

ACT1 ONIEXPECTED RESPONSE

RESPONSE NOT OBTAINED

1

18. ,C\\lign NV pump suction to VCT:

-

a. Check NV pump - SUCTION ALIGNED

a. Perform the following:

TO FWST.

-

1) Notify station management to

evaluate proper VCT alignment.

-

2) a m s t e p 19

b. Open the following:

- INV-14;A (VCT Outlet Isol)

- 1NV-142B (VCT Outlet Isol)

c. Close the following:

- INV-221A (NV Pumps Suct From

FWST)

- INV-2228 (NV Pumps Suct From

FWST).

-

19.

Maintain Pzr pressure stable using Pzr

heaters and normal Pzr spray.

IF normal spray not available, THEN

stabilize Pzr pressure as follows:

-

a.

letdown in service, THEN use NV

aux spray PER EP/l/A/500O/G-l

(Generic Enclosures), Enclosure 3

(Establishing NV Aux Spray).

-

b. E letdown isolated

NV aux spray

not effective, THEN use one Pzr PORV.

20.

Control intact SIG levels:

-

a. Check NIR level in any intact SIG -

GREATER THAN 11% (32% ACC).

-

a. Maintain total feed flow greater than

450 GPM until at least one intact SIG

NIR level greater than 11% (32% ACC).

-

b. Throttle feed flow to maintain all intact

SIG NIR levels between 11%

(32% ACC) and 50%.

-

b.

NIR level in any intact SIG continues

to go up in an uncontrolled manner,

THEN stop feed flow to that SIG.

SAFETY INJECTION TERMINATION

PAGE NO.

21 of 49

EP/1/AI5000/ES-1 .I

Rev. 16

I

RESPONSE NOT O B T A I N E D

ACTIONIEXPECTEO RESPONSE

1

21. %Check NC pump cooling:

a. Check KC aligned to reactor bldg non

essential header from one of the

following trains:

a. Perform one of the following based on

seal injection status:

A train:

NC pump seal injection

established, THEN:

1) Align KC

EP/l/A/5000/G-l

(Generic Enclosures), Enclosure

14 (Reestablishing KC To

Thsrmal Barriers).

-

- IKC-230A (Trn A Rx Bldg Non Ess

- 1 KC,-?A (Tm A Rx Bldg Non Ess

SUP ISOl) - OPEN

Ret Isol) - OPEN

2) _G_c\\

Step 22.

-

A train KC pumps - ON.

-

IF NC pump seal injection has also

B train:

-

been lost, THEN:

1 KC-228B (Tm B Rx Bldg Non Ess

-

SUP 1501) - OPEN

IKC-188 (Trn B Rx Bldg Non Ess

-

Ret Isol) - OPEN

B train KC pumps - ON.

-

NOTE

NCpumpseal

cooldown will occur

as the entire NC

System is cooled

down.

- 1) Maintain NC pump seal injection

and thermal barrier cooling

isolated.

2) G O m S t e p 22

-

I

I1

I

EP/l/A/5000/ES-l.l

UNIT 1

SAFETY INJECTION TERMINATION

PAGE NO.

22 Of 49

Rev. 16

I

ACTIONIEXPECTED RESPONSE

1

21 :<(Continued)

b. Check following valves - OPEN:

- 1 KC-394A (A NC Pump Therm Bar

- IKC-345A (C NC Pump Therm Bar

- IKC-425A (NC Pumps Ret Hdr Cont

Outside Isol)

- IKC-364B (B NC Pump Therm Bar

Otlt)

RESPONSE NOT OBTAINED

- IKC-4138 (D NC Pump Therm Bar

Otlt)

1KC-338B (NC Pump Sup Hdr Cont

Outside Isol)

-

- IKC-4248 (NC Pumps Ret Hdr Cont

Inside Isol).

-

c. Check NC pump seal injection flow -

GREATER THAN 6 GPM.

b. Perform one of the'following based on

seal injection status:

IF NC pump seal injection

established, THEN:

-

1) Align KC PER EP/l/A/5000/G-I

(Generic Enclosures), Enclosure

14 (Reestablishing KC To

Thermal Barriers).

2) m a

Step 22.

-

IF NC pump seal injection has also

been lost, THEN:

NOTE

NCpumpseal

cooldown will occur

as the entire NC

System is cooled

down.

-

1) Maintain NC pump seal injection

and thermal barrier cooling

isolated.

-

2) a m s t e p 2 2

c. Perform one of the following based on

seal injection status:

- E seal injection flow exists, THEN

throttle 1 NV-241 (Seal Inj Flow

Control) and INV-238 (Charging Line

Flow Control) to establish normal flow

rates.

IF seal injection flow has been lost,

THEN reestablish PER

APll/A/5500/12 (Loss of Letdown,

Charging or Seal Injection).

- -

EP/l/A/500O/ES-l .I

UNIT 1

22. .Check if NC pump seal return flow

should be established:

-

a. Check NC pump seal injection flow -

GREATER THAN 6 GPM.

SAFETY INJECTION TERMINATION

PAGE NO.

I

23 of 49

Rev. 16

b. Check:

, ,

- IEMF-51A (Containment Train A (Hi

Range)) - LESS THAN 25 RlHR

ACTIONIEXPECTED RESPONSE

- IEMF-51B (Containment Train B (Hi

Range)) - LESS THAN 25 RIHR.

RESPONSE NOT OBTAINED

1

c. Check KC aux bldg non essential

header valves- OPEN:

- IKC-50A (Trn A Aux Bldg Non Ess

sup Isol)

- IKC-1A (Trn A Aux Bldg Non Ess

Ret Isol)

- IKC-538 (Trn B Aux Bldg Non Ess

-sup Isol)

- 1 KC-2B (Trn B Aux Bldg Non Ess

Ret Isol).

d. Open the following:

- INV-94AC (NC Pumps Seal Ret Cont

Inside Isol)

- 1 NV-958 (NC Pumps Seal Ret Cont

Outside Isol).

23.

Check IETA and IETB - ENERGIZED BY

OFFSITE POWER.

-

a. Perform the following:

-

1) WHEN seal injection established,

THEN complete Step 22.

2) a n s t e p 23.

-

6. Perfoivi the foilowing:

1) Notify station management to

- evaluate performing Steps 22.c

through 22.d with high activity levels

in the NC System.

2) G O n S t e p 23.

-

c. Perform the following:

1) Notify station management to

evaluate performing Step 22.d

without KC to seal water HX.

-

2) G O m S t e p 23

-

REFER TO AP/l/N5500/07 (Loss Of

Electrical Power) while continuing with

this procedure.

SAFETY INJECTION TERMINATION

PAGE NO.

E?l1lA/5000/ES-1 .I

24 of 49

Rev. 16

UNIT 1

ACTION/EXPECTED RESPONSE

RESPONSE NOT O B T A I N E D

-

24

%Check NC pump status -AT LEAST ONE

ON.

Perform the following:

a Check if NC pump seal cooling has

been maintained

- Seal injection flow

- KC flow to thermal barner

b. E NC pump seal cooling has not been

maintained, THEN notify station

management to perform a status

evaluation prior to starting an NC pump,

c. E "REACTOR VESSE~UR LEVEL" is

less than loo%, AND any NC pump is

available to start, THEN perform the

following prior to starting an NC pump:

Raise Pzr level to greater than 90%

Raise NC subcooling based on core

exit T/Cs to greater than 36" F.

Use Pzr heaters as necessary to

saturate Pzr water.

-

NOTE

Preference should be

given to running 18 NC

Pump first, then 1A NC

Pump to provide Pzr

spray capability.

-

d. Start one NC pump PER

EP/l/A/5000/G-1 (Generic

Enclosures), Enclosure 6 (NC Pump

Startup).

-

e. Ensure Natural Circulation flow PER

Enclosure 2 (Natural Circulation

Parameters) until an NC pump can be

started.

lf

SAFETY INJECTION TERMINATION

PAGENO.

EP/I/A/5000/ES-l .I

25 of 49

Rev. 16

UNIT 1

-

i

I

25.

.check if SIR detectors should be

energized:

-

a. Check I/R channels - LESS THAN

10-10 AMPS.

ACTION/EXPECTEO RESPONSE

Check S/k'channels - ENERGIZED.

RESPONSE NOT O B T A I N E D

-

c. Transfer one "NIS RECORDER"

selector switch to a SIR channel and

the other to an I/R channel.

26.

Check if D/Gs should be stopped:

-

a. Check any DIG - ON.

-

b. Check IETA and IETB - ENERGIZED

BY OFFSITE POWER.

c. Dispatch operator to stop unloaded

D/G(s) and place in standby readiness

PER OP/l/A/6350/002 (Diesel

Generator):

- Enclosure 4.3 (1A D/G Shutdown)

- Enclosure 4.4 (18 DIG Shutdown).

a. Perform the following:

1) WHEN I/R is less than

10-10arnps. THEN perform Steps

25.b and 25.c.

-

2) GO TO Step 26

-

b. Perform the following:

- Place SIR select switches to

- Notify station management that S/R

had to be manually energized. (I/R

compensation may require

adjustment during next unit startup.)

"RESET".

-

a @=Step27

-

b. REFER

AP/l/A/5500/07 (Loss Of

Electrical Power) while continuing with

this procedure.

I

n a T r r . , n

I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

I

27.

Align nonessential plant equipment

PER:

- EP/l/A/5000/G-I (Generic Enclosures),

Enclosure 8 (Nonessential Plant

Equipment)

. .

- EP/l/A/5000/G-1 (Generic Enclosures),

Enclosure 21 (CA Storage Tank

(Water Tower) Makeup).

28.

Maintain plant conditions - STABLE:

. Pzr pressure

- .

Pzr level

-

- NC Temperatures

Intact S/G levels.

-

29.

Check MSlVs on intact SlGs -OPEN.

WHEN it is desired to establish

condenser steam dumps,

perform

the following:

-

a. IF intact S/G MSlVs required closed to

isolate leak, THEN GO TO Step 30.

-

b. E

any SIG pressure is less than

775 PSIG, THEN:

-

I ) Ensure NC System depressurized

to less than 1955 PSIG.

2) Ensure Low Pressure Steamline

- Isolation signal is blocked.

3) Maintain NC pressure less than

1955 PSIG.

-

c. Reset Main Steam Isolation

-

d. Reset MSlV Bypass Valves

-

e. Place STEAM DUMP SELECT in

steam pressure mode.

(RNO continued on next page)

!

II

I

8 ,

I

ACTION/EXPECTED RESPONSE

I

11

EP/1/A/5000/ES-1.1

i

RESPONSE NOT OBTAINED

I I

UNIT 1

- 1

11

SAFETY INJECTION TERMINATION

PAGE NO.

I'

1

-

I

29, (Continued)

-

f.

Place "STM PRESS CONTROLLER" in

manual and close.

-

g. Slowly throttle open MSlV bypass

valves on intact S/Gs to equalize

pressure across MSIVs. while ensuring

NC T-Hots are maintained stable.

h. WHEN pressure equalized, THEN:

-

1) Open all MSlVs on intact S/Gs

-

2) Close all MSlV bypass valves.

-

3) E"P-12 LO-LO TAVG" status light

(ISI-18) is lit, THEN place steam

dumps in bypass interlock.

-

4) Control steam dumps to maintain

NC T-Hots - STABLE.

5) IF AT ANY TIME "STEAM HEADER

PRESSURE" is at 1092 PSlG AND

~

auto control desired, THEN perform

the following:

-

a) Ensure "STM PRESS

CONTROLLER" setpoint at

1092 PSlG (pot setting of 8.4)

-

b) Place "STM PRESS

CONTROLLER" in auto

-

c) Ensure steam dumps open as

required to control "STEAM

HEADER PRESSURE at

1092 PSIG.

-

I

SAFETY INJECTION TERMINATION

PAGE NO.

EPll/A/5000/ES-1.1

28 of 49

UNIT 1

Rev. 16

a. NC subcooling based on core exit T/Cs

a. Perform the following:

-

- GREATER THAN 0' F.

1) Raise S/I flow to restore subcooling

as follows:

0 Start one or more S/I pumps,

necessary, THEN realign NV

SI1 flow path:

a)

suction aligned to VCT,

-

- THEN realign to FWST or to

discharge of ND pumps in S/I

Recirc mode.

b) Realign discharge as follows:

(1) Open the following:

- INI-9A (NC Cold Leg

lnj From NV)

- 1NI-1OB (NC Cold Leg

Inj From NV).

(2) Close the following.

INV-244A (Charging

Line Cont Outside Isol)

INV-245B (Charging

Line Cont Outside

-

Isol).

-

2)

EP/l/A/5000/E-I (LOSS Of

Reactor Or Secondary Coolant).

-

n

SAFETY INJECTION TERMINATION

PAGE NO.

EP/l/N5000/ES-I .I

29 Of 49

UNIT I

Rev. 16

~

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

I

30,(Continued)

-

b. Pzr level - GREATER THAN 11%

(29% ACC).

b. Perform the following:

-

1) Control charging flow to maintain

Pzr level.

-

2)

Pzr level can be maintained with

normal charging, THEN GO TO

Step 31.

3) Raise SI f l w to restore level as

follows:

Start one or more SA pumps

IF necessary, THEN realign NV

31 flow path:

-

a) E suction aligned to VCT,

THEN realign to FWST or to

discharge of ND pumps in S/I

Recirc mode.

b) Realign discharge as follows:

(1) Open the following:

-

INI-9A (NC Cold Leg

INI-1OB (NC Cold Leg

-

lnj From NV)

Inj From NV).

-

(2) Close the following:

1NV-244A (Charging

-

Line Cont Outside Isol)

- INV-24% (Charging

Line Cont Outside

Isol).

-

4) E

EP/I/A/5000/E-l (LOSS Of

Reactor Or Secondary Coolant).

n

SAFETY INJECTION TERMINATION

PAGE NO.

30 of 49

Rev. 16

I

ACT1 ON/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

1

31. Check if SIG sampling required:

-

a. EP/I/A/5000/-2 (Faulted Steam

-

a.

Step 32.

' '

Generator Isolation) - HAS BEEN

IMPLEMENTED.

-

b. Periodically sample all S/Gs for activity

PER EP/I/A/5000/G-l (Generic

Enclosures), Enclosure 9 (S/G

Sampling With S/I Signal).

-_

c. WHEN sqrpple results available, THEN

c. Perform the following:

check activity normal.

-

!

-

1) Contact station management ic'

evaluate sample results,

2) E sample indicates SGTR, THEN:

-

a) Ensure at least one NI pump on

or NV SI1 flow path aligned

(suction, discharge, isolate

normal charging).

-

b) @

EP/I/A/5000/E-3

(Stem Generator Tube

Rupture).

I

SAFETY INJECTION TERMINATION

PAGE NO.

EP/l/A/5000/ES-I. 1

31 Of 49

Rev. 16

UNIT 1

-

.

I

ACTIONIEXPECTED RESPONSE

RESPONSE NOT OBTAINED

1

32.

,Determine required plant recovery

procedure:

a. REFER TO Enclosure 3 (Plant

Realignment After S/I Termination)

and perform actions at station

management direction.

-

b. Check plant cooldown - REQUIRED.

-

c. Perform applicable steps of

OP/1 /A/6 100/003 (Controlling

Procedure For Unit Operation),

Enclosure 4.2 (Power Reduction)

-

d. Check all NC pumps - OFF

-

e.

EP/I/A/5000/ES-0.2 (Natural

Circulation Cooldown).

b. Perform the following:

-

1) Perform applicable steps of

OP/1/A!6100/003 (Controlling

Procedure For Unit Operation),

Enclosure 4.2 (Power Reductior

-

2) GO

OPll/A/6100/003

(Controlling Procedure For Unit

Operation), Enclosure 4.1 (Power

Increase).

-

d. a OP/l/A/6100/002 (Controlling

Procedure For Unit Shutdown).

PAGE NO.

32 Of 49

Rev. 16

SAFETY INJECTION TERMINATI~~

Enclosure 1 - Page 1 of 1

EPIlIAl5000/ES-l .I

1,

1

UNIT1

~

.

Foldout

1

I I '

I

1.

'$/I

Reinitiation Criteria (Applies after Step 11 in body of this procedure):

-

OR Pzr level can not be maintained greater than 11% (29% ACC), THEN:

a. Start Sll pumps and realign NV S/I flow path (suction, discharge, isolate normal charging)

b. a EP/l~A/5000/E-l (Loss Of Reactor Or Secondary Coolant).

NC subcooling based on core exit T/Cs is less than 0" F

as necessary to restore subcooling and level.

2.

Secondary lo!egrity Criteria:

any unisolated SIG pressure is going down in an uncontrolled manner,

has completely

depressurized, THEN GO TO EP/l/A/5000/E-2 (Faulted Steam Generator Isolation).

3.

SGTR Transition Criteria:

E any S/G level goes up in an uncontrolled manner,

any S/G has abnormal radiation,

w:

a. Ensure at least one NI pump on or NV S/I flow path aligned (suction, discharge, isolate

normal charging).

b. a EP/l/A/5000/E-3 (Steam Generator Tube Rupture).

4.

Cold Leg Recirc Switchover Criteria:

FWST level reaches 180 inches ("FWST LEVEL LO" alarm), THEN GO TO

EP/l/A/5000/ES-1.3 (Transfer To Cold Leg Recirc).

5.

CA Suction Sources:

-

IF CA Storage Tank (water tower) goes below 1.5 ft, THEN perform EP/l/A15000/G-1 (Generic

Enclosures), Enclosure 20 (CA Suction Source Realignment).

I

SAFETY INJECTION TERMINATION

PAGE NO.

Enclosure 2 - Page 1 of 1

EP/I/A15000/ES-l. 1

33 of 49

Natural Circulation Parameters

Rev. 16

UNIT 1

1.

2.

S

G

P

R

E

S

U

R

E

P

S

I

G

The f o l l o w i n g c o n d i t i o n s s u p p o r t o r i n d i c a t e n a t u r a l c i r c u l a t i o n flow:

NC s u b c o o l i n g - GREATER THAN 0°F

S / G p r e s s u r e s - STABLE OR G O I N G DOWN

Core e x i t T / C s - STABLE OR G O I N G DOWN

NC T-Hots - STABLE OR G O I N G DOW'N

NC T-Colds - AT SATURATION TEMPERATURE FOR S / G PRESSURE

( W I T H I N THE L I M I T S OF THE GRAPH BELOW).

__

I F N a t u r a l C i , r c u l a t i o n flow i s n o t estab!ished.

r a i s e dumping steam t o

e s t a b l i s h N a t u r a l C i r c u l a t i o n flow.

1200

1100

1000

900

800

700

600

500

400

300

200

100

0

200

250

300

350

400

4 50

500

550

600

NC T - C O L D ( ' F )

Ir

I

EP/I/A/5000/ES-l. 1

UNIT 1

SAFETY INJECTION TERMINATION

PAGE NO.

Enclosure 3 - Page 1 of 16

Plant Realionment After SI1 Termination

34 Of 49

Rev. 16

I'

I

.,

I

NOTE

The following steps restore the plant to a normal operating condition and each

For spurious S/I actuation, the ESF automatic actuation logic should be made

step shall only be performed at the discretion of station management.

operable by performing Step 12 or Mode 4 entered within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months of resetting

S/I (Tech Spec 3.3.2 and 3.0.3).

This enclosure does not address systems aligned in Cold Leg Recirc.

e This enclcsuie does not address any EMFs in trip condition.

Step order may be changed at station management direction

1.

Establish nonessential VI to containment by opening:

- IIA-508A (VI to Upper Pers Airlock Isol)

- llA-516A (VI to Lower Pers Airlock Isol)

- IVI-362A (VI To Annulus Vent Cont Isol)

- 1VI-1488 (Upp Cont Non Ess Cont Outside Isol).

2.

Restore Pzr heaters:

-

a. Place A and B heaters in manual.

-

b. Close A and B heater group supply breakers.

-

3.

Reset Containment Ventilation Isolation signal.

4.

Reopen the following containment sump and drain valves:

- IWL-64A (RB Sump Pumps Disch Cont Inside Isol)

- IWL-321A (Cont Vent Unit Drn Cont Inside Isol)

- IWL-3226 (Cont Vent Unit Drn Cont Outside Isol).

[ I

I

SAFETY INJECTION TERMINATION

PAGE NO.

EP/l/A/5000/ES-I .I

Enclosure 3 - Page 2 of 16

Plant Realignment After SA Termination

35 of 49

Rev. 16

UNIT 1

5.

%Realign RN headers to normal:

NOTE

Swapping B train RN suction to the LLI may reduce NPSH available to all RN

pumps.

a.

VI header pressure is less than 60 PSIG, AND all 4 unit 1 and unit 2 RN pumps are on,

T:

-

1) Contact station management to evaluate NPSH concerns prior to making alignments in

Step 5.

-

2) w m S t e p 6 .

b. Throttle the following valves to minimum for existing plant conditions:

- IRN-89A (RN to A KC Hx Control)

- IRN-19OB (RN To B KC Hx Control).

c. Notify Unit 2 to throttle the following valves to minimum for existing plant conditions:

- 2RN-89A (RN to A KC Hx Control)

- 2RN-190B (RN To B KC Hx Control).

d. Open the following:

- ORN-IOAC (Train 1B & 28 LLI Supply)

-

0- ORN-11 B (Train 1B & 28 LLI Supply).

-

e. Close ORN-9B (Train 18 & 28 SNSWP Supply).

f. Open the following:

- ORN-283AC (Train 18 & 28 Disch To RC)

- ORN-284B (Train 1 B & 28 Disch To RC).

-

g. Close ORN-1528 (Train 1B & 28 Disch to SNSWP)

h. Open the following:

- IRN-418 (Train B To Non Ess Hdr Isol)

1 RN-43A (Train B To Non Ess Hdr Isol).

-

I,

I

EP/l/A15000/ES-l .I

UNIT 1

SAFETY INJECTION TERMINATION

PAGE NO.

Enclosure 3 - Page 3 of 16

Plant Realignment After SI1 Termination

36 of 49

Rev. 16

5. (Continued)

i.

Notify Unit 2 RO to open the following:

- 2RN-41B (Train B To Non Ess Hdr Isol)

- 2RN-43A (Train B To Non Ess Hdr Isol).

-

j.

Open ORN-4AC (Train 1 B & 28 RC Supply).

k. Open the following RN nonessential header valves:

-

0 1RN-42A (AB Non ESS Supply Isol)

- 1 RN-638 (AB Non Ess Return Isol)

- IRN-279B (AB Vent Sys Return Isol)

- IRN-299A (AB Vent Sys Return Isol).

EP/l/A/5000/ES-I .I

UNIT 1

6.

Realign KC for normal operation:

a. Open the following:

- 1 KC-430A (Rx Bldg Drain Hdr Cont Outside Isol)

- IKC-4296 (Rx Bldg Drain Hdr Cont Inside Isol).

b.

NCDT temperature is less than or equal to 220" F, THEN open the following.

- IKC-320A (NCDT Hx Sup Hdr Cont Outside Isol)

- IKC-333A (NCDT Hx Ret Hdr Cont Outside Isol)

- IKC-3326 (NCDT Hx Ret Hdr Cont Inside Isol).

c.

NCDT temperature greater than 220" F, THEN perform the following:

I

SAFETY INJECTION TERMINATION

PAGE NO.

Enclosure 3 - Page 4 of 16

Plant Realignment After SA Termination

37 Of 49

Rev.. 16

CAUTION

Establishing KC flow rapidly to NCDT HX may cause water

hammer due to steam voiding of KC water in HX.

1) Dispatch operator to close the following valves and standby: .

- IKC-335 (NCDT Hx Ret Isol) (aux bldg, 733+14, JJ-51, room 730, 20 ft southwest of

- IKC-318 (NCDT Hx Sup Isol) (aux bldg, 733+9. JJ-50, room 730, outside door to VCT).

2) WHEN 1 KC-335 and 1 KC-31 8 are closed, THEN open the following:

- 1 KC-320A (NCDT Hx Sup Hdr Cont Outside Isol)

- IKC-333A (NCDT Hx Ret Hdr Cont Outside Isol)

- IKC-332B (NCDT Hx Ret Hdr Cont Inside Isol).

BIT, 2 ft from shield wall, above 230" mark, 1 ft from ceiling)

-

3) WHEN valves in Step 6.c.2) are opened,

reopen IKC-318.

notify dispatched operator to slowly

-

4) WHEN IKC-318 is open, THEN notify dispatched operator to slowly reopen IKC-335

II

I

SAFETY INJECTION TERMINATION

I PAGENn

'/l/A/5000/ES-1 .I

UNIT 1

Enclosure 3 - Page 5 of 16

Plant Realignment After SA Termination

38 Of 49'

Rev. 16

7. . Realign NCDT:

a. Open the following:

-

0 1 WL-2A (NCDT Pumps Disch Cont Inside Isol)

- IWL-39A (NCDT Vent Cont Inside Isol)

- IWL-1B (NCDT Pumps Disch Cont Outside Isol)

- IWL-41B (NCDT Vent Cont Outside Isol).

-

b. Place in normal operation pfiJ

OP/1/A/6500/001 (Liquid Waste System), Enclosure 4.1

(NCDT Operation).

8.

desired, THEN secure KC pumps not needed as follows:

a. E desired to secure A Train KC pumps, THEN:

1) Open:

-

a) IKC-185 (Trn B Rx Bldg Non Ess Ret Isol).

-

b) IKC-228B (Trn B Rx Bldg Non Ess Sup Isol).

2) Close:

-

a) IKC-230A (Trn A Rx Bldg Non Ess Sup Isol).

-

b) IKC-3A (Tm A Rx Bldg Non Ess Ret Isol).

-

3) Place IKC-51A (Train A Recirc Isol) in "CLOSE".

-

4) Ensure IKC-51A is closed.

5) Stop the following:

- 1 A l KC Pump

- IA2KCPump.

--

I

SAFETY INJECTION TERMINATION

PAGE NO.

EP/l/A/500O/ES-l .I

Enclosure 3 - Page 6 of 16

39 Of 49

UNIT 1

Plant Realianment After SA Termination

Rev. 16

I'

I

-

I

8. (Continued)

b. E desired to secure B Train KC pumps, m:

1) Open:

-

a) IKC-3A (Tm A Rx Bldg Non Ess Ret Isol).

-

b) IKC-230A (Tm A Rx Bldg Non Ess Sup Isol)

2) Close:

-

a) IKC-228B (Trn B Rx Bldg Non Ess Sup Isol).

-

b) IKC-18P. (Trn B Rx Bldg Non Ess Ret Isol).

-

3) Place IKC-54B (Train B Recirc Isol) in "CLOSE".

-

4) Ensure IKC-54B is closed.

5) Stop the following:

- 1B1 KC Pump

- 1B2 KC Pump.

9.

Depress "SS RESET" for the following valves:

- 1NI-185A (RB Sump To Train A ND & NS)

- INI-1848 (RE Sump To Train B ND 8. NS).

10.

Realign FWST:

a. Open the following:

- 1 FW-33A (FWST To Recirc Pumps)

- IFW-49B (FWST To Recirc Pumps).

-

b. E FWST Recirc Pump is required for recirc,

start pump

EP/1/A/5000/ES-1.1

UNIT 1

11.

PRT intact, THEN realign as follows:

a. Open the following:

- INC-54A (N2 To PRT Cont Inside Isol)

- INC-568 (PRT Spray Cont Outside Isol)

- INC-53B (N2 To PRT Cont Outside Isol).

-

b. Establish normal conditions PER OP/1/A/6150/004 (Pressurizer Relief Tank), Enclosure 4.1

(Establishing PRT Norma! Operation Conditions).

I

SAFETY INJECTION TERMINATION

PAGE NO.

Enclosure 3 - Page 7 of 16

Plant Realignment After SA Termination

40 of 49

Rev. 16

I

SAFETY INJECTION TERMINATION

PAGE NO.

EP/1/A/5000/ES-1.1

Enclosure 3 - Page 8 of 16

41 of 49

UNIT 1

Plant Realignment After S/I Termination

Rev. 16

12. .Restore ESF Automatic Actuation Logic to operable (Tech Spec 3.3.2):

-

a. Ensure all S/G N/R levels less than 83% (P14).

b. Dispatch operator to shutdown both M/G sets as follows:

-

1) Open both "GENERATOR CIRCUIT BREAKER CONTROL" switches.

-

2) Open both "MOTOR CIRCUIT BREAKER CONTROL" switches.

c. Ensure all S/I signals cleared (just having S/I reset is not adequate):

- High containment pressure

- Pzr low pressure

- Any inadvertent S/I signal.

-

d. E possible, THEN ensure all Reactor Trip signals cleared (first out alarms dark).

e. Reset P-4 logic as follows:

-

1) Close 1A Reactor Trip breaker.

-

2) Open 1A Reactor Trip breaker.

-

3) Close 1B Reactor Trip breaker.

-

4) Open 1B Reactor Trip breaker.

-

f.

Ensure "AUTO SI BLOCKED status light (ISI-18) - DARK.

g. Return OAC Monitor Light Programs to normal as follows:

1) Enter turn on code "MONL".

-

2) Select "UNLATCH for "SAFETY INJECTION TRAIN LATCH".

-

3) Select "UNLATCH" for "CONTAINMENT SPRAY TRAIN LATCH".

rl

I

PAGE NO.

42 of 49

Rev. 16

SAFETY INJECTION TERMINATION

Enclosure 3 - Page 9 of 16

Plant Realignment After S/I Termination

UNIT 1

EP/l//V5000/ES-I .I

1

I

1

13.

Establish CF to S/Gs as follows:

-

a. E

a Feedwater Isolation signal has occurred due to high high doghouse IevelIJ

P-14,

THEN ensure condition is clear prior to performing Step 13.

-

b. Ensure Step 12 completed

-

c. Ensure aux steam is being supplied by Unit 2 or Aux Boiler per EP/1/N5000/G-1 (Generic

Enclosures), Enclosure 8 (Nonessential Plant Equipment).

-

d. E

all condensate booster pumps are off,=

establish CM and CF flow=

OP/l/A/E250/0@1 (Condensate And Feedwater System), Enclosure 4.2 (CM System Hot

Restart).

-

e. E

any condensate booster pump is o n , M establish CF flow~OP/I/A/6250/001

(Condensate And Feedwater System), Enclosure 4.1 7 (CF Pump Startup).

14. WHEN CA no longer required, THEN stop CA pumps and return to normal PER

OP/I/A/6250/002 (Auxiliary Feedwater System):

- Enclosure 4.2 (Manual Operation of 1A/ 1B CA Pumps)

- Enclosure 4.4 (Manual Operation of #I TD CA Pump)

15.

Reestablish NC sample as follows:

-

a. Notify Primary Chemistry that NC sample valves will be reopened

b. Open the following:

- 1 NM-22A (A NC Loop Cont Inside Isol)

- INM-26B (NC Loop Sample Cont Outside Isol)

c. Request Primary Chemistry to perform the following:

-

1) Obtain NC System sample.

-

2) Determine NC boron concentration.

-

3) Perform isotopic analysis PER Station Chemistry Manual requirements.

~ _ _

I t

I

SAFETY INJECTION TERMINATION

PAGE NO.

43 of 49

Rev. 16

Enclosure 3 - Page 10 of 16

Plant Realignment After S/I Termination

EP/1/N5000/ES-1.1

UNIT1

I'

.

I

16.

Establish NIR containment pressure indication:

-

a. Open 1 NSSV5551 (Unit 1 Cont NR Press Outside Isol)

-

b. Open 1NSSV5550 (Unit 1 Cont NR Press Inside Isol).

17.

Establish containment radiation monitor sampling:

a. Open the following.

- IMISV-5580 (EMF 38,39,40 Inlet Cont Outside !sol)

- IMISV-5582 (EAIF 38.39,40 Outlet Cont Outside Isol)

- 1 MISV-5581 (EMF 38,39,40 Inlet Cont Inside Isol)

- IMISV-5583 (EMF 38.39,40 Outlet Cont Inside Isol).

-

b. Start EMF -38,39,40 sample blower.

-

18.

Return Containment Ventilation Systems to normal PER OP/1/A/6~0/001 (Containment

Ventilation System), Enclosure 4.5 (Realignment of Containment Ventilation Systems

Following SI).

-

19.

Evaluate restoring VQ capability

Addition System).

OP/l/N6450/017

(Containment Air Release And

-

20.

Return VCNC to normal operation PER OP/O/A16450/011 (Control Area VentilationlChilled

Water System), Enclosure 4.7 (Realignment of VCNC After a 810 or SI).

UNIT 1

EP/l/A/5000/ES-l.l

21.

Return VA to normal as follows:

I

3

SAFETY INJECTION TERMINATION

PAGE NO.

44 of 49

Rev. 16

Enclosure 3 - Page 1 1 of 16

Plant Realignment After SI1 Termination

a. Dispatch operator to local VA Filtered Exhaust panels to return VA to pre&

status by

resetting:

-

- ABFXFIA

- ABFXF 1B

- ABFXF2A

-

b. Return VA to normal o p e r a t i o n w OP/OIN6450/003 (Auxiliary Building Ventilation System),

Enclosure 4.1 (Aux Building Ventila!ion Fans and Counting Room Filter Unit Startup and

Normal Operation).

22.

Return TSC and Computer Room ventilation to normal operation as follows:

-

a. Dispatch operator to close 1 EMXA-RlOE (OTSC Normal Supply To MCC-SMXE).

b. WHEN breaker is closed, THEN notify Maintenance to return the following to normal:

- TSC ventilation

- Computer Room ventilation.

23.

Dispatch operator to reset and close the following breakers:

- 1 EMXB-7B (NI Trace Heating Pnlbd 1 ETHB)

- 1 EMXC-SB (Emergency AC Lighting Pnlbd No. ELA-I)

- 1 EMXD-56 (Emergency AC Lighting Pnlbd No. ELB-1).

I

EP/llN5000/ES-1.1

I'

I

-

I

-I-

I

SAFETY INJECTION TERMINATION

PAGE NO.

45 of 49

Rev. 16

Enclosure 3 - Page 12 of 16

24. =

CA pumps stopped per Step 14, T"

establish S/G sample and blowdown as

follows:

-

vital battery charger EVCC is being powered from Unit 2.THJ3

depress "STOP" on

associated Unit 1 "EVCC BATT CHARGER.

I

CAUTION

Establishing blowdown with NC pumps off may cause uncontrolled

cooldown.

a. E

all NC pumps off, THEN perform the following:

-

1) Contact station management to evaluate need to establish blowdown

-

2) =blowdown

is requlredm any NC pump is started,T"cornplete

Step 24.b.

-

3) w m S t e p 2 5 .

-

b. WHEN S/G blowdown and sample are desired.=

align PER OP/l/N6250/008 (Steam

Generator Blowdown), Enclosure 4.1 (Establishing BB).

-

25. E

FWST level is low, THEN refill PER OP/l/A/6200/014 (Refueling Water System), Enclosure

4.2 (FWST Makeup Using Reactor Makeup Blender During Modes 1-5 or While Defueled).

-

26.

Return KF to normal operation PER OP/I/A/6200/005 (Spent Fuel Cooling System),

Enclosure 4.1 (KF Pumps Operation).

27.

Realign vital battery chargers as follows:

-

a. Determine which battery chargers are actually being powered from Unit 2

b. Open battery charger M contactors as follows:

-

vital battery charger EVCA is being powered from Unit 2

,

m

depress "STOP" on

associated Unit 1 "EVCA B A R CHARGER".

I

- Evital battery charger EVCB is being powered from Unit 2

.

m

depress "STOP" on

associated Unit 1 "EVCB BATT CHARGER".

- -

IF vital battery charger EVCD is being powered from Unit 2,-

depress "STOP" on

associated Unit 1 "EVCD BATT CHARGER".

28. E

"POSITIVE RATE TRIP" bistable light on PR drawers is lit, THEN reset N/I channels as

follows:

-

a. On PR drawers, turn and hold "RATE MODE" switches to "RESET".

-

b. Check "POSITIVE RATE TRIP" bistable lights - DARK.

-

c. Release switches to."NORMAL"

-

29.

Reset steam dumps C7A logic.

-

30. E

H2 Igniters are off, THEN GO TO Step 32.

31.

Turn off H2 Igniters as follows:

-

a. Contact station management to determine if adequate core cooling has existed for this entire

event.

b. E

adequate core cooling has existed for this entire event,=:

_. -

WHEN containment pressure is less that 0.25 P S I G , u turn H2 Igniters off.

-

c. E

Inadequate core cooling has existed during this event,=

turn H2 Igniters off 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

after adequate core cooling established.

32. WHEN H2 Igniters are off, THEN realign N F

a. Open the following:

- 1 NF-228A (RB Glycol Supply Cont Outside Isol)

- 1 NF-234A (RE Glycol Return Cont Outside Isol)

- INF-233B (RB Glycol Return Cont Inside Isol).

-

b. Restart pumps and chiller u n i t s m OP/l/A/6200/008 A (Ice Condenser Refrigeration

System), Enclosure 4.1 (NF System Startup).

I I

I

EPlllA/5000/ES-1,1

UNIT 1

-

I

SAFETY INJECTION TERMINATION

PAGE NO.

Enclosure 3 - Page 14 of 16

47 Of 49

Plant Realignment After SI1 Termination

Rev. 16

I

33. <E

a Phase B Isolation has occurred, THEN perform the following:

-

a. Ensure Containment Spray reset.

-

b. Ensure Phase B Isolation reset.

CAUTION

If NS pumps have been off for more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , restarting NS

pump prior to draining NS header in next step, may result in NS

piping failure in reactor bldg annulus (water hammer concern).

-

c. Restore NS System operability PER OP/1/A/6200/007 (Containment Spray System),

Enclosure 4.5 (NS System 0perability.Restoration).

-

d. Realign Phase B valves listed in EP/I/A/5000/G-l (Generic Enclosures), Enclosure 12

(Phase B Valve Checklist) to normal.

e. Align VX equipment as follows:

-

1) Reset VX System resets.

-

2) Stop ti2 Skimmer fans

-

3) Stop Containment Air Return fans.

4) Close the following dampers:

- IVX-2B (IB H2 Skimmer Fan Is01 Test A)

- IVX-1A (IA H2 Skimmer Fan Is01 Test A)

- IRAF-D-4 (1B Cont Air Ret Fan To Lwr Cont Test A)

- IRAF-D-2 (IA Cont Air Ret Fan To Lwr Cont Test A),

I

SAFETY INJECTION TERMINATION

PAGE NO.

EP/I/A/5000/ES-l .I

Enclosure 3 - Page 15 of 16

48 of 49

UNIT 1

Plant Realignment After SI1 Termination

Rev. 16

I

33..(Continued)

5) Restore VX DIP switches to service as follows:

-

a) Obtain HVAC test switch key #I89 from key locker.

NOTE

VX test switches used in following steps should only be operated in

clockwise direction. Key switches are in "OFF" when notched section

of the switch is in the twelve o'clock position.

-

b) Place "UNIT 1 VX SYSTEM TEST SELECT TRAIN A" switch to "IVXIA" pos m.

-

c) Depress "UNIT 1 VX SYS TRA;N A RESET" pushbutton.

-

d) Return "UNIT 1 VX SYSTEM TEST SELECT TRAIN A" switch to OFF.

-

e) Place "UNIT 1 VX SYSTEM TEST SELECT TRAIN B" switch to "IVX2B" position.

-

f)

Depress "UNIT 1 VX SYS TRAIN B RESET" pushbutton.

-

g) Return "UNIT 1 VX SYSTEM TEST SELECT TRAIN E" switch to "OFF".

6) Dispatch operator to shutdown both H2 Recombiners as follows:

-

a) Reduce KW output to zero.

-

b) Turn power off.

Shutdown VE System PER OP/l/A/6450/002 (Annulus Ventilation System), Enclosure 4.2

(VE Startup For Recirculation and Shutdown).

-

f.

rl

I

,

I

-

1. 1

SAFETY INJECTION TERMINATION

PAGE NO.

EP/I/A/500O/ES-I. 1

Enclosure 3 - Page 16 of 16

49 Of 49

UNIT1

.

Plant Realianrnent After SA Termination

Rev. 16

I

34. .E

both trains RN are running, @it is desired to stop one train of RN, THEN secure as

follows:

a. Check if conditions allow stopping one train of RN:

- All CA pumps - OFF

- CA pumps are no longer required to maintain S/G level

- Train related KC pumps - OFF

- Train related D/G - OFF

- Train related NS pump - OFF

- Cooling to operating VC train from RN - CAN BE MAINTAINED

- Cooling to other operating RN loads - CAN BE MAINTAINED

- Station management concurs that RN pump may be stopped.

-

b. Do not continue until all conditions above are met to secure one train

c. Stop desired train of RN as follows:

E desire to stop 1A RN pump, THEN stop as follows:

-

1) Place control switch for IRN-86A (A KC Hx Inlet Isol) in "MAN".

2) Perform the following concurrently:

- Close IRN-86A.

-

0 Prior to 1 RN-86A going full closed, stop TA RN Pump.

-

3) Place control switch for 1 RN-86A in "AUTO'.

desire to stop 1B RN pump, THEN stop as follows:

-

1) Place control switch for IRN-1878 (B KC Hx Inlet Isol) in "MAN".

2) Perform the following concurrently:

- Close 1RN-187B.

- Prior to 1RN-1878 going full closed, stop 18 RN Pump.

-

3) Place control switch for 1RN-187B in "AUTO.

RN.

Duke Power Company

(1) ID NO. AP/llA/5500/21

(R06 97)

PROCEDURE PROCESS RECORD

Revision No

7

- PREPARATION

INFORMATION ONLY

(2) Station

McGuire Nuclear Station

(3) Procedure Title

Loss Of

KC Or KC System e k a g e

(4) Prepared By

Philip A. Thompson

Date September 7,1999

...,~'

(5) Requires 10CFR50.59 evaluation?

[SI Yes

N o

(New procedure or revision with major changes)

(Revision with minor changes)

0

No

(To

(6) Reviewed By

(QR)

Cross-Disciplinary Review By

Reactivity Mgmt. Review By

(7) Additional Reviews

Reviewed By

Date

Reviewed By

Dale

(8) Temporary Approval (ifnecessary)

BY

(SRO/QR) Date

BY

(OR) Date

(9) Approved By

Date

9-rc;. 79

PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)

(10) Compared with Control Copy

Date

Compared with Control Copy

Date

Compared with Control Copy

Date

(1 1 ) Date(s) Performed

Work Order Number (WO#)

COMPLETION

(12, ProceaJrc Complet on Veriflcai on

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

0

Yes 0 N/A Listed enclosures attached?

0 Yes 0 N/A Data sheets attached. completed, dated and signed?

Yes 0

N/A Charls, graphs, etc. attached, dated, identified, and marked?

0

Yes 0 N/A Procedure requirements met?

Verified By

Date

(1 3) Procedure Completion Approved

(14) Remarks (attach addilionalpages. ifnecessary.)

I

)

.

I I1

I

i

I 1

,

LOSS OF KC OR KC SYSTEM LEAKAGE

5

SAGE NO.

AP/l/N5500721

1 of 80

UNIT1

Rev. 7

h

I ]

A. Purpose

The purpose of this procedure is to identify actions required in the event of a loss of KC, or

leakage on the KC System.

LOSS OF KC OR KC SYSTEM LEAKAGE

r

APll /PJ5500/2

1

UNIT I

PAGE NO.

2 Of 80

Rev. 7

S. Svmptoms

ACT ION/E XPECTED RESPONSE

Y'O KC HX A INLET FLOW" computer alarm

"LO KC HX B INLET FLOW" computer alarm

Low flow alarms on components supplied by KC

High temperature alarms on components supplied by KC

Low level or level going down in KC Surge Tank

Abnormal KC p i m p F!ow

"LO KC SURGE TANK COMPARTMENT A LEVEL" computer alarm

"LO KC SURGE TANK COMPARTMENT E3 LEVEL" computer alarm

"KC SURGE TANK ABNORMAL LEVEL" alarm.

RESPONSE NOT O B T A I N E D

C. ODerator Actions

-

1.

Monitor foldout page.

-

2.

Check any KC pump -ON.

-

3.

Announce occurrence on paging system.

-

4. Secure any dilution in progress.

-

5.

Check both train's KC Surge Tank level -

STABLE OR GOING UP.

Isolate all letdown:

Normal letdown

Excess letdown

- ND letdown.

-

_ -

IF Surge Tank level trend indicates a KC

System leak, THEN GO TO Step 8.

1 I

I

' 1

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO.

APl1 lN5500l2 1

3 of 80

UNIT1

Rev. 7

4

..::.

1

I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

-

a. Check standby KC Surge Tank Level

GREATER THAN 2 FT.

a. Perform the following:

1) lniliate YM makeup lo KC Surge

Tank as follows:

a) Dispatch operator lo open lhe

following valves as required to

maintain KC Surge Tank level:

To makeup to 1A KC Surge

tank, open: 1 KC-1 07 (YM

Makeup to 1A KC Surge

Tank) (aux bldg, 767+2,

JJ-57. under grating, between

KC surge tanks)

To makeup to 1 B KC Surge

Tank, open: IKC-111 (YM

Makeup to 16 KC Surge

Tank) (aux bldg. 767+2,

JJ-58, under grating, between

KC surge tanks).

-

b) Adjust makeup rate as required

to prevent overflow of KC Surge

Tank (approximately 8.5 ft).

-

2) IF AT ANY TIME it is determined

that YM makeuo is inadeauate,

-

THEN align R N Makeup to KC PER

Enclosure 3 (Aligning RN Makeup

to KC Surge Tank) as required.

3) Do not continue until surge tank

level is greater than 2 11.

-

b. Start standby KC train PER one of the

following:

- To start A Train , cO

Enclosure 4

(Startup of 1A KC Train)

- To start B Train , cO To Enclosure 5

(Startup of 1 B KC Train).

7.

GO TO Step 38.

I - --

I I I

I

AP/l/A/5500/21

UNIT1

I

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO,

4 of 80

Rev. 7

I

A C T ION/EXPECTED RESPONSE

. k? y

.., ...

RESPONSE NOT OBTAINED

9.

Initiate YM makeup to KC Surge Tank as

follows:

a. Immediately dispatch operator lo open

the following valves as required to

maintain KC Surge Tank level:

- To makeup 1A KC Surge tank, open:

1KC-107 (YM Makeup to 1A KC

Surge Ta'nk) (aux bldg, 767+2, JJ-57,

under grating, belween KC surge

tanks)

- To makeup 1 B KC Surge tank, open:

1 KC-1 11 (YM Makeup to 16 KC

Surge Tank) (aux bldg. 767+2, JJ-58,

under grating, belween KC surge

tanks).

-

b. Adjust makeup rate as required to

prevent overflow of KC Surge Tank

(approximately 8.5 ft).

- 10.

IF AT ANY TIME it is determined that YM

makeup is inadequate to restore or

stabilize KC surge tank level,

immediately align RN Makeup to KC PER

Enclosure 3 (Aligning RN Makeup to

KC Surge Tank) as required.

1

-

GO TO Step 16.

--

Check both train's KC surge tank level -

-

GREATER THAN 3 FT.

I

LOSS OF KC OR KC SYSTEM LEAKAGE

r

PAGE NO.

AP/I /N5500/21

5 Of 00

Rev. 7

.'

-\\

NOTE

The following OAC points may be used to determine level drop in next s.tep.

These points are also displayed on the KC system graphic:

MlP1317 (1ATrain KCsurgetanklevel rate)

MlP1318 (16 Train KC surge tank level rate)

A 0.10 ftfmin level drop in one train's surge tank equals approximately 50 GPM

leak.

UNIT I

I

-

IF level is dropping faster than 0.10

ft/min, THEN GO TO Step 16.

-

12.

Check both trains KC surge tank level

-

drop - LESS THAN OR EQUAL TO 0.10

FT/M I N .

I

ACTION/EXPECTEO RESPONSE

NOTE

The next step allows maintaining current KC system alignment for small leaks

that should be within the capacity of noma1 makeup. Allowing level to drop to

2 ft allows more time for operators to locally align makeup, prior to taking action

to isolate KC headers.

RESPONSE NOT OBTAINED

13.

Do not continue until at least one of the

following occurs:

- KC makeup has been locally opened

from RN.

-

- . Either train's KC Surge Tank level is less

than or equal to 2 ft.

- Both KC surge tank levels are stable 01

going up.

- 14.

Check KC surge tank level on both

train(s) - STABLE OR GOING UP.

-

IF KC surge tank level is still going down

in an uncontrolled manner, THEN:

a. E

level goes below 2 11, THEN ensure

foldout page item 1 is implemented

-

b. GO TO Step 16.

-

LOSS OF KC OR KC SYSTEM LEAKAGE

APll/A/550dl21

I

' 1

PAGE NO.

6 Of 80

Rev. 7

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

-

15.

Step 35.

RESPONSE NOT O B T A I N E D

1

16.

Isolate 1 A KC Train from 1 B KC Train as

follows:

-

a. Check any 1A KC Train Pump

RUNNING.

a. GO TO Step 16.1.

-

b. GO TO Step 16.f.

b. Check the following valves - OPEN:

-

- 1 KC-3A (Tm A Rx Bldg Non Ess Ret

!SGl)

- 1 KC-230A (Trn A Rx Bldg Non Ess

c. Close the following valves:

-

1) 1 KC-53B (Trn B Aux Bldg Non Ess

sup !sol).

sup Isol).

-

2) 1 KC-2B (Tm B Aux 6ldg Non Ess

Ret Isol).

-

3) 1 KC-228B (Trn B Rx Bldg Non Ess

-

4) 1 KC-18B (Tm 6 Rx Bldg Non Ess

Re! Iso!).

sup Isol).

d.

1 A KC Surge Tank level stabilizes,

AND 1 B KC Surge tank level continues

to go down, THEN leak is on 1 B

Essential header.

-

d. WHEN valves in Step 16.c are closed,

-

THEN check 1 A KC Surge Tank level -

GOING DOWN.

- e. Q m S t e p 17.

1.

Close the following valves:

- 1) 1 KC-50A (Tm A Aux Bldg Non Ess

sup Isol).

-

2)

1 KC-1 A (Tm A Aux Bldg Non Ess

Ret Isol).

-

3) 1 KC-230A (Trn A Rx Bldg Non Ess

sup Isol).

-

4) 1 KC-3A (Trn A Rx Bldg Non Ess

Ret Isol).

-

PAGE NO.

Rev. 7

r

LOSS OF KC OR KC SYSTEM LEAKAGE

APllIA/5500/21

7 Of 80

UNIT 1

- 17.

Check Unit 2 KC Surge Tank level.

STABLE.

.

L

!

>

18.

-

ACTION/EXPECTED RESPONSE

Check KC pumps - AT LEAST ONE

RUNNING.

RESPONSE NOT OBTAINED

1

-

IF Unit 2 KC Surge Tank level is going up

in an uncontrolled manner, THEN:

a. Have Rad Lzlaste Chemis!ry check KC

alignment for:

- NB and WL evaporators

- WG system

b.

Unit 2, THEN:

KC drain tank pumps are aligned lo

- Dispatch operator to align drain tank

to Unit 1 PER_ OP/l/A/6400/005

(Component Cooling Water System),

Enclosure 4.8 (Swapping KC Drain

Tank Discharge to Unit 1 KC Surge

Tank).

- Have Work Control SRO evaluate

any KC drain operation in progress or

olher potential KC drain paths.

WHEN KC Surge Tank Level greater than

2 ft,

start one KC Train PER one of

the following:

- -

IF desired to start 1A KC Train, AND 1A

KC Surqe Tank is qreater than 2 ft.

__-_

THEN GO TO Encrosure 4 (Startup of

1 A KC Train).

- -

IF desired to starl 1 B KC Train. AND 1 B

KC Surae Tank is arealer than 2 ft.

---

THEN 60 TO Encrosure 5 (Slarlup Of

1 E KC Train).

LOSS OF KC OR KC SYSTEM LEAKAG'E

r

APl1 IN550012 1

Rev. 7

I

UNIT I

ACT IONIEXPECTED RESPONSE

RESPONSE NOT O B T A I N E D

1

NOTE

The next step allows waiting to see if KC Surge Tank levels can be stabilized

using makeup, prior to taking actions to isolate KC headers. If level can be

stabilized using makeup, header with leak may be left in service.

21.

Do not continue until one of the

following is met:

- Either train's KC Surge Tank level is less

than 3 ft.

- - Makeup to the KC Surge Tank has been

initiated using RN.

Both KC Surge Tank levels are stable or

going up.

-

22.

RETURN To Step 19.

I II

I

..

M N S

AP/l/N550012 1

UNIT I

I

PAGE NO.

9 Of 80

Rev. 7

/

LOSS OF KC OR KC SYSTEM LEAKAGE

ACTION/EXPECTED RESPONSE

23.

IF. AT ANY TIME leak is known to be on

an Essential header, THEN perform one

of the following:

RESPONSE NOT OBTAINED

NOTE . -

IF leak on 16 Train, THEN GO TO

Enclosure 4 (Startup of 1 A KC Train).

The enclosure used in next step will also isolate Essential header with leak

-

, I

IF leak on 1A Train, THEN GO TO

Enclosure 5 (Startup of 1 B KC Train).

- -

;, : j, I

I

._

-

LOSSOFKCOR KCSYSTEMLEAKAGE

t

PAGE NO.

AP11lA/5500/2 1

10 of 80

Rev. 7

P

ACTION/EXPECTEO RESPONSE

RESPONSE NOT OBTAINED

24.

Check if leak is on Reactor Bldg

Non-essential header as follows:

- Containmerit Floor and Equipment

Sumps level - GOING UP

- Leak is known to be on the Reactor Bldg

Non-essential header.

Perform the following:

a. E Containment Floor and Equipment

pumps are off, THEN GO TO Step 26

-

b. Stop Containment Floor and Equipment

pumps.

c. Check if Containment Floor and

Equipment sump level is going up.

sump level indicates a leak in

containment, THEN GO TO Step 27.

-

d.

-

e. E sump level is normal, THEN GO TO

Step 26.

-

25.

Step 27.

26.

Attempt to isolate leak by isolating KC

Aux Bldg Non-essential header as

follows:

a. Isolate letdown as follows:

1) Close:

- 1 NV-458A (75 GPM UD Orifice

Outlet Cont Isol)

- 1 NV-457A (45 GPM UD Orifice

Outlet Con1 Isol)

- 1 NV-35A (Variable UD Orifice

Outlet Cont Isol).

- 2) Check ND - IN SERVICE PRIOR TO

EVENT.

-

3) Close INV-121 (ND Letdown

Control).

- b. Close all NM valves located on 1 MC-8

(vertical board).

-

2)

To Step 26.b.

-

1

LOSS OF KC OR KC SYSTEM LEAKAGE '

AP/l/A/5500/21

c,

UNIT 1

PAGE NO.

Rev. 7

1 1 Of 80

'.....-

ACTION/EXPECTED RESPONSE

26. (Continued)

c. Close the following:

-

1 ) 1 KC-SOA (Trn A Aux Bldg Non Ess

sup Isol).

RESPONSE NOT 0BTA.INED

-

2) 1 KC-lA (Trn A Aux Bldg Non Ess

Ret Isol).

-

3) 1 KC-53B (Trn B Aux Bldg Non Ess

s u p !so:),.

-

4) 1 KC-26 (Trn B Aux Bldg Non Ess

Ret Isol).

d. Evaluate whether leak is isolated based

on:

- Surge Tank(s) level trend

Amount of makeup established

IF KC surge lank level is going up,

AND status of leak isolation is

unknown, THEN reduce KC surge

tank makeup flow as required to

determine if leak is isolated.

-

- -

-

7

LOSS OF KC OR KC SYSTEM LEAKAGE

,+

PAGE NO.

1

APII lN55OOl2 1

12 Of 80

Rev. 7

UNIT I

26. (Continued)

-

e. Check leak,- ISOLATED.

,. '

/-?-

-

e. E

leak still exists, THEN:

I

ACT ION/EXPECTED RESPONSE

-

1) Raise KC surge lank makeup flow

as required to maintain level.

RESPONSE NOT OBTAINED

-

f.

Assume leak was on the Aux Bldg

Non-essential header.

9. Close:

- 1NV-1A (NC UD lsol To Regen Hx)

- 1 NV-2A (NC UD lsol To Regen Hx).

-

h.

Step 35.

27.

Check the following valves - CLOSED:

- 1 KC-305B (Excess UD Hx Sup Hdr Cont

Otsd Isol)

- 1 KC-3158 (Excess UD Hx Ret Hdr Con1

Ofsd Isol).

2) WHEN Surge Tank on operating

train is greater than 2 11, THEN

reopen the following valves on the

operating train:

A Train

a) 1 KC-1 A (Trn A Aux Bldg Non

Ess Ret Isol).

b) 1 KC-50A (Trn A Aux Bldg

Non Ess Sup Isol).

-

B Train

-

a) 1 KC-2B (Trn B Aux Bldg Non

Ess Ref Isol).

-

b) 1 KC-53B (Trn B Aux Bldg

Non Ess Sup Isol).

3) GO TO Step 27.

-

GO TO Step 29.

_--

r

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO.

AP/l /A/5500/2

1

13 Of 80

Rev. 7

UNIT I

I

ACTION/EXPECTED RESPONSE

I

RESPONSE NOT OBTAINED

- 28. G0.m Step 30.

29.

Attempt to isolate leak by isolating KC to

excess letdown as follows:

a. Isolate Excess Leldown by closing the

following valves:

- 1 NV-24B (C NC LOOP TO EXS UD HX

Isol)

Isol).

- 1 NV-25B IC NC LOOP To EXS UD HX

b. Close the following valves:

- 1 KC-305B (Excess UD Hx Sup Hdr

Cont Otsd Isol)

- 1 KC-3158 (Excess UD Hx Ret Hdr

Cont Otsd Isol).

c. Evaluate whether leak is isolated based

on:

- Surge Tank@) level trend

- Amount of makeup eslablished

- IF KC surge lank level is going up

&status

of leak isolation is

unknown, THEN reduce KC surge

lank makeup flow as required to

determine if leak is isolated.

-

d. Check leak - ISOLATED.

d,

leak still exisls. m:

1) Raise KC surge tank makeup flow

as required to maintain level.

-

2) GO TO Step 30

-

e. Assume leak was on excess letdown

Hx.

-

1.

GO TO Step 35.

\\

30.

Attempt to isolate leak by isolating KC to

N ~ D T

as follows:

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO.

APll lAJ5500/2 1

14 Of 80

Rev. 7

UNIT 1

a. Close the following valves:

ACT I O N / E X P E C T E D R E S P O N S E

. 1 KC-320A (NCDT Hx Sup Hdr Cont

Outside Isol)

-

R E S P O N S E NOT O B T A I N E O

- . 1 KC-333A (NCDT Hx Ret Hdr Cont

Outside Isol)

- . 1 KC-3326 (NCDT Hx Ret Hdr Cont

Inside Isbl).

b. Evaluate whether leak is isolated based

on:

- Surge Tank(s) level trend

- Amount of makeup established

- E KC surge tank level is going up,

AND status of leak isolation is

unknown,

reduce KC surge

tank makeup flow as required to

determine if leak is isolated.

-

c. Check leak - ISOLATED

d. Notify station management to evaluate

NCDT cooling:

- -

WHEN reestablishing KC to NCDT.

THEN evaluate the potential for KC

steam void in NCDT Hx.

-

e. a m s t e p 35.

c.

leak still exists, THEN:

1) Raise KC surge tank makeup flow

as required to mainlain level.

2) Reopen Ihe following valves:

- .

1 KC-320A (NCDT Hx Sup Hdr

Cont Outside Isol)

. 1 KC-333A (NCDT Hx Ret Hdr

Cont Outside Isol)

. 1 KC-332B (NCDT Hx Ret Hdr

Cont Inside Isol).

-

3) GO TO Step 31

-

MNS '

LOSS OF KC OR KC SYSTEM LEAKAGE

,T

API1lN5500121

i-\\

UNIT 1

PAGE NO.

Rev. 7

15 Of 80

31.

Check the following:

Perform one of the following:

IF leak location is believed lo be on

Reactor Bldg header,

location

unknown, MEN observe notes prior to

- -

-

a. Any NC pump - RUNNING.

-

b. Both trains KC surge tank level - ON

SCALE.

Step 34 and

Step 34.

ACT ION/EXPECTEO RESPONSE

-

c. Bolh lrains KC surge lank level.

STABLE OR GOING UP.

RESPONSE NOT O B T A I N E D

1

32.

IF AT ANY TIME KC surge tank level

starts going down, THEN perform

Step 31.

-

33.

To Step 35.

leak has been identified on an

- Essential header, THEN RETURN IQ

Step 23.

MNS I

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO,

APlllAl5500l21

I6 Of 80

Rev. 7

UNIT 1

-

ACTION/EXPECTEO RESPONSE

RESPONSE NOT O B T A I N E D

NOTE

If the leak is not stopped by isolating the KC Reactor Bldg Header, and.KC

pumps are on, then this step will immediately restore KC cooling to NC pumps,

KC cooling for NC pump motor bearings and thermal barriers will be isolated in

the next step. The foldout page provides NC pump trip criteria.

34.

Attempt to isolate leak by isolating entire

KC Reactor Bldg Header as follows:

a. Close the fdflowing valves:

-

1) 1 KC-230A (Trn A Rx 6ldg Non Ess

sup Isol).

-

2) 1 KC-3A (Trn A Rx Bldg Non Ess

Ret Isol).

-

3) 1 KC-2286 (Trn B Rx Bldg Non Ess

sup Isol).

-

4) 1 KC-1 86 (Trn B Rx Bldg Non Ess

Ret Isol).

b. Evaluate whether leak is isolated based

on:

- Surge Tank(s) level trend

- Amount of makeup established

- IF KC surge tank level is going up,

&status

of leak isolation is

unknown, THEN reduce KC surge

tank makeup flow as required to

determine if leak is isolated.

,

LOSS OF KC OR KC SYSTEM L E A K A G ~

I

PAGE NO.

170f80

APII lN5500l2 1

UNIT I

Rev. 7

c1

ACTION/EXPECTED RESPONSE

I

-

c. Check leak - ISOLATED.

RESPONSE NOT OBTAINED

..:..

.. ...

.

l-

c.

leak still exists, THEN perform the

following:

-

1) Raise KC surge tank makeup flow

as required to maintain level.

-

2) Assume leak is on the train's

Essential header with affected

surge tank level.

1A KC Pumps running, AND 1 A

KC Surge Tank level is greater than

1 ft, THEN align 1A KC train to

Reactor Eldg header as follows:

a) Close the following valves:

-

(1)

1 KC-228E (Trn E Rx Eldg

Non Ess Sup Isol).

-

(2)

1 KC-1 88 (Tm E Rx Bldg

Non Ess Ret Isol).

b) Open the following valves:

-

(1) 1 KC-3A (Trn A Rx Bldg

Non Ess Ret Isol).

-

(2)

1 KC-230A (Tm A Rx Eldg

Non Ess Sup Isol).

3)

'

(RNO continued on next page)

MNS '.

"[

UNIT1

APlllPJ5500/2 1

PAGE NO.

18 of 80

Rev. 7

r

LOSS OF KC OR KC SYSTEM LEAKAGE

(2)

1 KC-3A (Trn A Rx 6ldg

- . Non Ess Ret Isol).

b) Open the following valves:

-

(1)

1 KC-1 88 (Trn 6 Rx 6ldg

Non Ess Ret Isol).

-

(2)

1 KC-228B (Tm 6 Rx 6ldg

Non Ess Sup Isol).

ACTION/EXPECTEO RESPONSE

NOTE

The enclosure used

in next step will also

isolate Essential

header with leak. It

will also align

non-essential

headers to the intact

KC train.

5) Pedorm one of the following:

- IF leak on 1B Train, THEN GO

a

Enclosure 4 (Startup of 1A

KC Train)

IF leak on 1A Train, THEN GO

Enclosure 5 (Startup of 16

KC Train).

-

6) GO TO Step 36.

-

RESPONSE NOT OBTAINED

.

I

'

LOSS OF KC OR KC SYS ;EM LEAKAGE'

APIlIN5500I2 1

-.

UNIT 1

.

PAGE NO.

Rev. 7

19 Of 80

34. (Cohtinued)

-

d. Trip reactor:

A C T ION/EXPECTEO RESPONSE

-

e. WHEN reactor tripped, THEN stop all 4

NC Pumps.

RESPONSE NOT OBTAINED

-

1.

EP/l/N5000/E-0 (Reactor Trip

or Safety Injection), while continuing in

this AP as time and conditions allow.

, I

35.

Check KC pumps - AT LEAST ONE

WHEN KC Su

Tank Level greater than

RUNNING.

2 ft,

sti

ne KC Train PER one of

-

the following:

desired to start 1 A KC Train. AND 1 A

- KC Surge Tank is greater than 2 ft,

THEN GO TO Enciosure 4 (Startup of

1 A KC Train).

desired to start 1 B KC Train, AND 16

- KC Surge Tank is greater than 2 ft,

---

THEN GO TO Enclosure 5 (Slartup of

1 E KC Train).

\\

LOSS OF KC 3R KC SYSTEM LEAKAGE

9

PAGE NO.

20 of 00

AP/l/N5500~21

Rev. 7

UNIT 1

NOTE

Header with leak may

be left in service as

long as KC surge tank

level can be

maintained. The

decision to isolate leak

should depend on size

of leak and critical

components on

associated header.

-

required to swap operating trains

of KC due to leak on an Essential

header, THEN evaluate performing

Step 23.

required to isolate the entire Aux

Bldg Non-essential header, THEN

evaluate performing Step 26.

-

(RNO continued on next page)

ACTION/EXPECTED RESPONSE

RESPONSE NOT O B T A I N E D

MNS .I

LOSS OF KC OR KC SYSTEM L E A K A G ~

APll /A/5500/2 1

UNIT 1

PAGENO.

21 Of 80

Rev. 7

NOTE.

If cooling to NC pumps

will be isolated, it is

preferable to wait until

NC pumps are already

shutdown.

required to isolate KC 10 just the

NC pumps, THEN:

1 ) Ensure NC pump trip criteria on

foldout is monitored.

2) Evaluate closing the following

-

a) 1 KC-338B (NC Pump Sup Hdr

Cent Outside Isol).

-

b) 1 KC-425A (NC Pumps Ret

Hdr Cont Outside Isol).

-

c) 1 KC-4248 (NC Pumps Ret

Hdr Cont Inside Isol).

-

valves:

ACTION/EXPECTEO RESPONSE

required to isolate entire Reactor

- Bldg Non-essential header, MEN

observe notes prior lo Step 34 and

evaluate performing Step 34.

RESPONSE NOT OBTAINED

-

b. Determine individual component that is

leaking.

-

37. WHEN leaking individual component is

isolated, @ i f an isolated KC

nonessential header is determined to be

intact, m e v a l u a t e placing affected

KC header back in service PER

Enclosure 9 (Reopening KC Headers).

LOSS OF KC OR KC SYSTEM LEAKAGE

r

PAGE NO.

AP/l /A/5500/2 1

22 Of 80

UNIT I

Rev. 7

-_

-

1) Align normal letdown PER

AP/l/N5500/12 (Loss=

ACTION/EXPECTEO RESPONSE

Letdown, Charging Or Seal

Injection).

ND is in RHR mode and ND

letdown is desired, THEN establish

IEtdOVJn from the ND System PER

OP/1/A/6200/001A (Chemical and

Volume Control System Letdown),

Enclosure 4.1 (Establishing

Letdown Flow from the ND System,

Charging Flow, and Seal Injection

Flow).

-

2)

-

b. E KC is aligned to the Reactor Bldg

Non-essential header, AND excess

RESPONSE NOT OBTAINED

. .

letdown is required,

establish

.,:',..

7

~ "PER

EP/1 /A/500O/G- 1 (Generic

"::

. .

, ..

. . : '

Enclosures), Enclosure.2 (Establishing ,.

.:,

I ,:

.:.;

Excess.Letdown).

..

, . "..

..

.

%

. , .:

...

. ..

'<

,

- ;

Open valves unless required closed to

39.

Check NC pump thermal barrier valves -

- 1KC-394A (A NC Pump Therm Bar Otlt)

- 1 KC-345A (C NC Pump Therm Ear Otlt)

- 1 KC-364B (B NC Pump Therm Bar Otlt)

- 1 KC-4138 (D NC Pump Therm Bar Otlt).

OPEN:

- . isok,at$ leak.

' $

Y'

4%

t .

. I

_

I

_ 1

I'

LOSS OF KC OR KC SYSTEM LEAKAGE

I

API1 /N5500/2 1

PAGE NO.

23 of 80

Rev. 7

40

-

41.

-

42.

-

43.

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

Check KC to Aux Bldg Non-essential

header - ESTABLISHED.

Perform the following:

a. Ensure all NM valves located on 1 MC-8

(vertical board) are closed.

b. Notify secondary and primary chemistry

that:

NM valves have been isolated.

KC cooling to Aux Bldg Non-essential

header is isolated.

Normal and ND letdown is isolated.

-

c. REFER

Enclosure 8 (VCT High

- Temperature Actions).

d. Notify station management to evaluate

Spent Fuel Pool cooling.

-

e. g m S t e p 4 3 .

-

I

RESPONSE NOT OBTAINED

Check NM valves (on IMC-8) -

PREVIOUSLY CLOSED BY THIS

PROCEDURE.

Notify..Chemistry to coordinate

reestablishing NM.

Evaluate KC chemistry requirements as

follows:

Notifv Primarv Chemistrv of KC makeup

-

that has occirred or is 6 progress.

- Evaluate recirculating the KC Surge

Tank volume and feed and bleed of KC

System PER OP/l/A/6400/005

(Component Cooling Water System).

GO TO Step 43.

_--

I

\\

-

r

-

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO.

AP/l/A/5500/21

24 of 80

UNIT 1

Rev. ?

ACTIONIEXPECTED RESPONSE

RESPONSE NOT OBTAINED

-

44.

Check both trains RN suction -ALIGNED

TO LLI.

Perform the following:

-

a. IE. both A and B train RN pumps are

aligned to the SNSWP, M E N GO TO

Step 45.

both of the following valves are

closed, THEN GO TO Step 45:

1 RN-41 B (Train B To Non Ess Hdr

2RN-41B (Train B To Non Ess Hdr

b.

- Isol)

ISOI). .

-

c. IE. both of the following valves are

closed, THEN GO TO Step 45:

r "

1 RN-43A (Train B To Non Ess Hdr

-

Isol)

I

2RN-43A (Train B To Non Ess Hdr

-

ISOI).

(RNO continued on next page)

I II

I

1

AP/1 lAJ550012 1

UNIT I

I

\\

I

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO.

25 of 80

Rev. 7

ACTION/EXPECTED RESPONSE

d. Contact station management to

evaluate the following:

RESPONSE NOT OBTAINED

NOTE

If train with suction

on pond is aligned

to train with

discharge to RC (via

open cross tie), or to

non-essential

header, SNSWP

may be pumped to

the lake.

Unit 1 non-essential

headers discharge

to A Train

discharge. Unit 2

non-essential

headers discharge

to B Train

discharge.

Unit 1 and 2

non-essential

headers may be

cross tied through

RN to RL tie.

- SNSWP draw down

- Alignment of RN System.

- 45.

RETURN To procedure and step in

effect.

I

II

I

1

AP/l/PJ5500/21

I 1

UNIT 1

LOSS OF KC OR KC SYSTEM LEAKAGE

,

PAGE NO.

26 of 80

Rev. 7

Enclosure 1 - Page 1 of 1

Foldout

1.

KC header isolation criteria:

IF KC surge tank level goes below 2 ft due to KC system leak, THEN immediately isolate

gfected train PER Enclosure 2 (Isolation of KC Non-essential Headers).

2.

NC pump trip criteria:

-

IF NC pump motor bearing temperature reaches 195O F, THEN perform the following:

a. Trip the reactor

b. WHEN reactor is tripped, THEN trip all NC pumps

c.

EP/l/N5000/E-O (Reactor Trip or Safety Injection), while continuing in this

procedure as time and conditions allow.

3.

ND pump trip and flow isolation criteria (Applies if ND aligned for RHR):

-

IF KC cooling lost to either ND train's Hx, AND NC temperature is greater than 150" F, THEN

perform the following on train of ND that lost KC flow to its ND Hx:

Stop associated ND pump.

-

IF 1A ND Hx lost KC flow, THEN close:

1 ND-33 (A ND Hx Bypass)

1 ND-32 (A ND Hx To Letdown Hx).

-

IF 1 B ND Hx lost KC flow, THEN close:

1ND-18 (B ND Hx Bypass)

1ND-17 (B ND Hx To Letdown Hx).

4.

KC pump trip criteria:

KC pumps show signs of cavitation, THEN:

Trip affected pumps.

Isolate affected train PER Enclosure 2 (Isolation of KC Non-essential Headers).

5 .

VCT high temperature:

-

IF "VCT HI TEMP" alarm (1AD7-Dl) is received, THEN REFER

Enclosure 8 (VCT High

Temperature Actions).

LOSS OF KC OR KC SYSTEM LEAKAGE

,

Enclosure 2 - Page 1 of 3

Isolation of KC Non-essential Headers

APli lAJ5500/2

1

UNIT 1

-

1.

Ensure letdown is isolated.

PAGE NO,

27 of 80

Rev. 7

2.

Isolate Aux Bldg Non-essential header

from affected train:

ACTION/EXPECTED RESPONSE

E 1A KC Surge Tank is less than 2 ft,

1 A KC Pumps tripped due to

cavitation, THEN close:

RESPONSE NOT OBTAINED

1

- 1 KC-50A (Trn A Aux Bldg Non Ess

1 KC- I A (Trn A Aux Bldg Non Ess Ret

sup Isol)

Isol).

-

. 16 KC Surge Tank is less than 2 ft.

-

OR 1 B KC Pumps tripped due to

cavitation, MEN close:

1 KC-53B (Trn B Aux Bldg Non Ess

.

1 KCQB (Trn B Aux Bldg Non Ess Ret

- sup Isol)

Isol).

-

3.

Close all NM valves located on 1MC-8

(vertical board).

4.

Check both trains of KC surge tank level:

Perform the following:

a. E

surge tank level is less than 1 ft,

KC pumps have been stopped due to

cavitation, THEN GO TO Step 6.

- . Level - STABLE OR GOING UP

-

Level - ON SCALE

-

b. IF AT ANY TIME either train's KC surge

tank level goes below 1 ft,

pumps trip due to cavitation,

perform Steps 6 through 8.

-

KC

c. RETURN

step.in effect in body of

- procedure.

-

5.

RETURN

step in effect in body of

procedure.

I r,

I

71

I

LOSS OF KC 3 R KC SYSTEM LEAKAGE

,

PAGE NO.

28 of 80

Rev. ?

Enclosure 2 - Page 2 of 3

Isolation of KC Non-essential Headers

A PI 1 IN5 5 0012 1

UNIT 1

ACTlONlEXPECTED RESPONSE

1 KC-230A (Tm A Rx Bldg Non Ess

-

SUP ISOl)

RESPONSE NOT OBTAINED

1

- 1 KC-3A'(Trn A Rx Bldg Non Ess Ret

Isoi).

1 E XC Stirge Tank is less than 1 ft,

e

OR 1 B KC Pumps tripped due to

cavitation, THEN close:

1 KC-228B (Trn B Rx Bidg Non Ess

1 KC-1 8B (Trn B Rx Bldg Non Ess Ret

- sup ISOl)

Isoi).

-

Ensure NC pump trip criteria on foldout

page is monitored.

-

7.

Check either KC train surge tank level -

GREATER THAN 2 FT.

-

IF both trains of KC surge tank level are

less than 2 ft, THEN perform the

following:

a. Ensure makeup is initiated to restore

surge tank level in both trains.

b. WHEN KC surge tank level is restored

to greater than 2 ft,

Step 8.

procedure.

-

perform

c. RETURN

step in effect in body of

-

I '

1

LOSS OF KC OR KC SYSTEM LEAKAGE

,

Enclosure 2 - Page 3 of 3

Isolation of KC Non-essential Headers

A PI 1 IN5 50012 1

UNIT 1

I

RESPONSE NOT O B T A I N E D

A C T I ON / E X P E C T E 0 R f S PONS f

PAGE NO.

29 of 80

Rev. 7

NOTE

The enclosure used in next step will also isolate essential header on train with

low surge tank level and restore cooling to the intact non-essential headers.

8.

Swap KC to train with surge tank level

greater than 2 ft as follows:

. To start 1A Train,

TO Enclosure 4

- (Startup of 1A KC Train)

- To starl 1 B Train,

TO Enclosure 5

(Startup of 16 KC Train).

I /j

APll$;:l

CAUTION

RN pump must be running while RN to KC emergency makeup is open, to

prevent draining KC surge tank back to RN.

LOSS OF KC OR KC SYSTEM LEAKAGE

<

PAGE NO.

Enclosure 3 - Page 1 of 2

Aligning RN Makeup to KC Surge Tank

30 of 80

Rev. 7

1.

Align one or both of the following

flowpaths (Step 1.a or 1.b) as required:

I

1

ACT ION/EXPECTEO RESPONSE

a.

1A RN Train to 1A KC Surge Tank

makeup is desired, THEN:

RESPONSE NOT O B T A I N E D

- .I) Ensure,lA RN Pump is on

1 ) C;OmStep 1.b.

-

2) Dispatch operator to open the

following valves:

1 KC-494 (Trn A RN Emerg

Makeup to KC) (aux bldg,

733+10, " - 5 6 , in corner west of

161 KC Pump)

-

- 1 KC-496 (Trn A RN Emerg

Makeup to KC) (aux bldg,

733+10, " - 5 6 , in corner west of

1B1 KC Pump).

b.

1 B RN Train to 1 B KC Surge Tank

makeup is desired, THEN:

1) Periorm the following:

-

1) Ensure 1 B RN Pump is on.

a)

makeup using A train RN is

- desired, THEN RETURN

, Step 1.a.

b)

Step 2.

-

2) Dispatch operator to open the

following valves:

- 1 KC-499 (Trn B RN Emerg

Makeup to KC) (aux bldg,

733~10, "-56, in corner west of

1B1 KC Pump)

- 1 KC-497 (Trn B RN Emerg

Makeup to KC) (aux bldg,

733+10, "-56,

in corner west of

1B1 KC Pump).

I

,.-F==?

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO.

I

31 Of 80

Rev. 7

Enclosure 3 - Page 2 of 2

Alianinq RN Makeup to KC Surge Tank

APll /A/5500/21

UNIT I

2.

IF AT ANY TIME an RN pump trips, THEN

dispatch operator to isolate affected

trains R N to KC makeup line opened in

Step 1.

-

- 3.

Adjust makeup rate as required to

prevent overflow of KC Surge Tank

(approximately 8.5 ft).

i

LOSS OF KC OR KC SYSTEM LEAKAGE

,

PAGE NO.

Enclosure 4 - Page 1 of 17

Startup of 1A KC Train

32 of 80

Rev. 7

AP/llAJ5500/2 1

UNIT 1

r-\\

-

1.

Check IKC-56A (KC To A ND Hx) -

CLOSED.

Perform the following:

-

a. E

any 1A KC Pump is on, AND 1 A ND

pump is on, THEN GO TO Step 2.

b. E all 1 A Train KC pumps are off,

1A ND Pump off, THEN:

-

1 ) Close 1 KC-56A

2) E

NC temperature is greater than

150" F, THEN:

a) Slop 1A ND Pump.

b) Close ND cross tie valves:

- 1 ND-33 (A ND Hx Bypass)

- 1 ND-32 (A ND Hx To Letdown

Hx).

-

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

-

2.

Check 1KC-81s (KC To B ND Hx) -

CLOSED.

Perform the following:

-

a.

pump is on, THEN GO TO Step 3.

b. E

all 1 B Train KC pumps are off,

1 B ND Pump off, THEN:

any 1 B KC Pump is on, AND 1 B ND

RESPONSE NOT O B T A I N E D

1

-

1 ) Close 1 KC-81 B.

2)

-

a) Stop 1B ND Pump

b) Close ND cross tie valves:

NC temperature is greater than

150" F, THEN:

- 1 ND-18 [B ND Hx Bypass)

1ND-17 (3 ND HxTo Letdown

Hx).

-

GO TO Step 5.

- 3.

Check 1 B Train KC Pumps - OFF

---

LOSS OF KC OR KC SYSTEM LEAKAGE

,

Enclosure 4 . Page 2 of 17

Startup of 1A KC Train

APIl IN550012 1

UNlT I

PAGE NO.

33 of 80

Rev. 7

-

4.

Select "CLOSED" on 1 KC-54B (Train B

Recirc Isol).

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

GO TO Step 17.

_ _

-

5.

Check 1A Train KC Pumps -OFF.

-

RESPONSE NOT OBTAINED

Voiding of 1A train KC may be Suspected if any of the following have occurred:

1A train KC pumps were tripped due to cavitation or air entrainment.

1 B train KC pumps were tripped due to cavitation or air entrainment whiie A

train was still cross-tied to B train.

6.

IfT voiding of 1A train KC is suspected,

THEN dispatch operator to perform the

following:

- Open 1 KC-24 (1 A2 KC Pump Overflow

Isol) (aux bldg 733+3, GG-55. above KC

Pump 1A2) until a solid stream of water

is visible in sightglass then reclose valve

- 3pen 1 KC-21 (1Al KC ?ump Overflow

Isol) (aux bldg, 733, GG-55, top of KC

Pump 1 A l ) until a solid stream of water

is visible in sightglass then reclose valve

- Unlock and throttle 1 KC-6 (1 A I KC

Pump Discharge) (aux bldg, 733t7,

"-55,

west of KC Pump 1 A l ) to one

turn open.

7.

Close the following valves:

-

a. 1 KC-5OA (Tm A Aux Bldg Non Ess Sup

Isol).

-

b. 1 KC-1 A (Trn A Aux Bldg Nnn Ess Ret

Isol).

-

c. 1 KC-230A (Trn A Rx Bldg Non Ess Sup

ISOI).

-

d. 1 KC-3A (Trn A Rx Bldg Non Ess Ret

Isol).

. .~

... ..

,

-

I

I t

I

1

APllIAJ5500/21

UNIT I

LOSS OF KC OR KC SYSTEM LEAKAGE

I

PAGE NO.

34 of 80

Rev. 7

Enclosure 4 - Page 3 of 17

Startup of 1 A KC Train

-

8.

-

9.

-

10.

-

11.

-

12.

-

13.

-

14.

-

15.

-

16.

-

17.

-

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

Start 1 A RN Pump.

RESPONSE NOT O B T A I N E D

Ensure 1 RN-86A (A KC Hx Inlet Isol)

opens.

Place control switch for IKC-51A (Train

A Recirc Isol) in "AUTO".

Ensure 1 KC-51A (Train A Recirc Isol)

opens.

Start 1 A l KC Pump.

Check IKC-6 ( I A I KC Pump Discharge) -

LOCALLY THROTTLED IN STEP 6.

Perform the following:

a. Start 1 A2 KC Pump.

b. amstep 7.

-

Hat!e dispatched operator slowly throttle

open 1 KC-6 (1 A I KC Pump Discharge).

WHEN IKC-6 (1Al KC Pump Discharge)

is open, THEN start 1A2 KC Pump.

Ensure 1 KC-6 (1Al KC Pump Discharge)

is fully opened and locked.

GO TO Step 20.

_ _

Check ND Pumps - ANY ON PRIOR TO

-

ENTERING THIS PROCEDURE.

LOSS OF KC OR KC SYSEM

LEAKAGE

,

PAGENO.

1

35 Of 80

Rev 7

APll /N5506121

Enclosure 4 - Page 4 of 17

Startup of 1 A KC Train

UNIT 1

18.

Check VI pressure -GREATER THAN

Perform the following:

-

60 PSIG.

a. Dispatch operator lo close the following

._

A C T I ON / E X PE C T ED RE 5 PONS E

valves:

RESPONSE NOT O B T A I N E D

. 1KC-148 (A KF Hx inlet) (aux bldg,

750t10, MM-52, 20 ft north of door to

1A ND Hx room)

-

1KC-I55 (6 KF Hx Inlet) (aux bldg,

750+8, MM-52, 20 ft north of door lo

1A ND Hx room).

-

b. WHEN it is.desired to reestablish fuel

pool cooling, THEN:

-

1) Limit KC pump flow lo 4000 GPM

per operating KC pump in next step.

2) Dispatch operator to throttle open

the following valves as necessary:

1KC-148 (aux bldg, 750+10,

- MM-52,20 ft north of door to 1A

ND Hx room)

MM-52.20 ft north of door to 1A

ND Hx room).

IKC-155 (aux bidg, 750+8.

-

c.

Step 20.

-

- 19.

Throttle KC to KF flow as required in

subsequent steps to allow establishing

adequate KC flow to NO Hx.

I f i

I

i

I,

dNS

LOSS OF KC CR KC SYSTEM LEAKAGE

,

PAGE NO.

36 Of 80

Rev. 7

Enclosure 4 - Page 5 of 17

StartuD of 1 A KC Train

APIl/A/5500/2 1

UNIT I

ACTIONIEXPECTED RESPONSE

a. Limit KC pump flow to 4000 GPM per

operating KC pump in next step.

-

b. Open the following valves:

I

RESPONSE NOT OBTAINED

1) 1 KC-3A (Trn A Rx Bldg Non Ess

Ret Isol).

-

2) 1 KC-230A (Trn A Rx Bldg Non Ess

- s u p Isol).

c. Close the following valves:

-

1) 1 KC-228B (Trn E Rx Bldg Non Ess

-

2) 1 KC-1 8B (Trn B Rx Bldg Non Ess

Ret Isol).

sup Isol).

d. Open the following valves:

-

1) 1 KC-1 A (Trn A Aux Bldg Non Ess

Ret Isol).

-

2) 1 KC-50A (Tm A Aux Bldg Non Ess

sup Isol).

-

e. a m s t e p 25

J

i

1.

I

AP11 /N5500/2 1

UNIT I

LOSS OF KC OR KC SYSTEM LEAKAGE

I

PAGE NO.

37 Of 80

Rev. 7

Enclosure 4 - Page 6 of 17

Startup of 1A KC Train

I

ACTIONIEXPECTEO RESPONSE

I

RESPONSE NOT O B T A I N E D

\\

I

-

21.

KC header with leak - HAS BEEN

IDENTIFIED.

Perform the following:

a.

the reactor is critical, THEN GO TO

-

Step 23.

b.

the reactor is subcritical, THEN:

1 ) WHEN KC header with leak is

identified, THEN perform Step 24

-

.. -

2) m m S t e p 25.

-

22.

@ T o Step 24.

23.

Attempt to establish KC cooling to NC

pumps as follows:

a. Close the following valves:

-

1) 1 KC-2286 (Trn B Rx Bldg Non Ess

sup Isol).

-

2) 1KC-186 (Trn B Rx Bldg Non Ess

Ret Isol).

-

b. Open 1 KC-3A (Trn A Rx Bldg Non Ess

Ret Isol).

-

c. Check 1A KC Surge Tank level -

STABLE OR GOING UP.

c. E

1 A KC Surge Tank level going down

in an uncontrolled manner, THEN

perform the following:

1 ) Reclose 1 KC-3A (Trn A Rx Bldg

Non Ess Ret Isol).

2) Trip the reactor.

-

3) WHEN reactor is tripped, THEN trip

all NC pumps.

4) a m

EP/l/N5000/E-O (Reactor

Trip or Safety Injection), while

continuing in this procedure as time

and conditions allow.

-

5)

To Step 23.f

-

I t r

I

1

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO.

Enclosure 4 - Page 7 of 17

38 01 80

Rev. 7

AP/l/N5500/21

ACTION/EXPECTED RESPONSE

RESPONSE NOT O B T A I N E D

23. (Continued)

-

d. Open 1 KC-230A (Trn A Rx Bldg Non

Ess Sup lsol).

e. Check 1A train KC:

e,, E 1A KC Surge Tank level going down

in an uncontrolled manner, OR flow and

amps indicate air binding of KC pumps,

THEN perform the following:

Surge Tank Level - STABLE OR

GOING UP

-

Pump flow and amps - NORMAL

-

1.

Check KC header with leak - HAS

BEEN IDENTIFIED.

1) Reclose 1 KC-230A (Trn A Rx Bldg

Non Ess Sup Isol).

2) Reclose 1 KC-3A (Trn A Rx Bldg

Non Ess Ret Isol).

3) E KC amps and flow indicate air

binding of pumps, THEN stop 1A

train KC pumps.

-

4) Trip the reactor.

-

5) WHEN reactor is tripped, THEN trip

all NC pumps.

Trip or Safety Injection), while

continuing in this procedure as time

and conditions allow.

-

6)

TO EP/I/N5000/E-O (Reactor

7 )

1 A Train KC Pumps are off,

- THEN RETURN

Step 6.

f.

Perform the following:

-

1) WHEN KC header with leak is

-

2)

Step 25,

identified, THEN perform Step 24.

1 I 1

I

1

I 1

-

LOSS OF KC OR KC SYSTEM LEAKAGE

I

PAGE NO.

MNS ,

UNIT I

AP/l/N5500/2 1

Enclosure 4 - Page 8 of 17

39 of 80

Rev. 7

Startup of 1A KC Train

24.

Align KC as follows:

a. Monitor the following KC pump

parameters while aligning KC in this

step:

- Pump flow and amps

- KC surge tank level.

-

b. Limit KC pump flow to 4000 GPM per

operating KC pump in next step.

-

c. Check - LEAK IDENTIFIED ON 1 B KC

TRAIN ESSENTIAL HEADER.

ACiION/EXPECTEO RESPONSE

c. Perform the following:

1 ) Open the following valves unless

required closed to keep leak on

Reactor Bldg Header isolated:

I

RESPONSE NOT OBTAINED

-

a) 1 KC-3A (Trn A Rx Bldg Non Ess

Ret Isol).

-

b) 1 KC-230A (Trn A Rx Bldg Non

Ess Sup Isol).

2) Close the following valves:

-

a) 1 KC-228B (Trn B Rx Bldg Non

Ess sup Isol).

-

b) 1 KC-188 (Tm B Rx Bldg Non

Ess Ret Isol).

3) Open the following valves unless

required closed to keep leak on Aux

Bldg Non-essential Header isolated:

-

a) 1 KC-1A (Trn A Aux Bldg Non

Ess Ret Isol).

-

b) 1 KC-50A (Trn A Aux Bldg Non

Ess sup Isol).

-

4) GO TO Step 25

1 I,

I

1

ACT I ON/ EXPECT EO RESPONSE

I II

,

I

LOSS OF KC OR KC SYSTEM LEAKAGE

I

I PAGE NO. 11

RESPONSE NOT O B T A I N E D

1 1)

APIl/N5500/21

UNIT I

Enclosure 4 - Page 9 of 17

Startup of 1 A KC Train

4 0 0 f 8 0 -

1 Rev.7

(1

24. (Continued)

d. Close the following valves:

-

1 ) 1 KC-2288 (Trn B Rx Bldg Non Ess

sup Isol).

-

2) 1 KC-1 8B (Trn B Rx Bldg Non Ess

Ref Isol).

e. Open the following valves:

-

1 ) 1 KC-3A (Trn A Rx Bldg Non Ess

Ret Isol).

-

2) 1 KC-230A (Trn A Rx Bldg Non Ess

sup Isol).

1.

Close the following valves:

-

1) 1 KC-53E (Trn B Aux Bldg Non Ess

sup Isol).

-

2) 1 KC-2B (Tm B Aux Bldg Non Ess

Ret Isol).

g. Open the following valves:

-

1 ) 1KC-1A (Tm A Aux Bldg Non Ess

Ret Isol).

-

2) - 1 KC-50A (Trn A Aux Bldg Non Ess

sup Isol).

.

)'.

,

I

. . .'

i ,,.-

.*.,I

L

r

I

7

API 1 lPJ55OUl2 1

UNIT 1

LOSS OF KC OR KC SYSTEM LEAKAGE ,

PAGE NO.

41 of 80

Rev. 7

Enclosure 4 - Page 10 of 17

Startup of 1A KC Train

-

25.

Check 1B ND pump - OFF.

ACT I ON / E X PE C TE D R E S PO MS E

Perform the following:

RESPONSE NOT O B T A I N E D

-

a.

1 B train KC pumps are off, THEN

GO TO Step 28.

_ _

b.

1 A ND pump is running, THEN:

1) Stop 1B ND Pump.

2) Close ND cross tie valves:

- 1ND-18 (E ND Hx Bypass)

- 1ND-17 (E ND Hx To Letdown

Hx). .

-

3)

Step 26.

-

c. E 1 B KC surge tank is on scale, AND

can be maintained on scale for at least

15 more minutes (to allow time to swap

ND trains), THEN GO TO Step 32.

-

d.

NC temperature is greater than

150" F, THEN:

1) Slop 16 ND Pump

-

2) Close ND cross tie valves:

o 1 ND-18 (E ND Hx Bypass)

- 1 ND-17 (E ND Hx To Letdown

Hx).

-

LOSS OF KC OR KC SYSTEM LEAKAGE

,

PAGE NO.

Enclosure 4 - Page 11 of 17

Startup of 1 A KC Train

42 of 80

Rev. 7

AP111N550012 1

UNIT 1

ACTIONIEXPECTED RESPONSE

26.

-

RESPONSE NOT O B T A I N E D

Check 1 KC-81 B (KC To 6 ND Hx) -

CLOSED.

Perform the following:

a.

1 KC-50A (Trn A Aux Bldg Non ESS

Sup Isol)

1 KC-53B (Trn B Aux Bldg

Non Ess Sin" I d ' ic rlnced, THEN GO

-

.v ,.,",,

,- "."-

5 Step 27.

b.

-

1) Close 1KC-81B (KCTo B ND Hx).

-

2) a m s t e p 27.

18 ND Pump is off, THEN:

CAUTION

If NC temperature is

greater than 200" F,

then KC flow must

be maintained

greater than

2000 GPM to

operating ND train.

NOTE

1A KC PumDs will

continue to ieed 1 B ND

Hx after tripping 1 B KC

Pumps.

c. Throttle the following as required to

ensure 1A train KC pump flows will

remain less than 4000 GPM per pump

after stopping 1 B train KC pumps:

1 KC-81 B (KC TO B ND HX)

- 1 KC-56A (KC TO A ND HX)

-

KC to KF flow.

-

27.

Stop 1 B1 and 182 KC Pumps.

-

28.

Place control switch for IKC-546 (Train

B Recirc Isol) in the "CLOSE" position.

I '

I-

I

AP/1/AJ5500/2 1

I 1

UNIT I

LOSS OF KC OR KC SYSl ;M

LEAKAGE

Enclosure 4 - Page 12 of 17

Startup of 1 A KC Train

'

PAGE NO,

43 of 80

Rev. 7

-

29.

Ensure 1KC-54B (Train B Recirc Isol)

closes.

ACT ION/EXPECTED RESPONSE

-

30.

Check KC flow - LESS THAN

4000 GPM PER OPERATING KC PUMP.

Throttle the following as required to

reduce KC flow to less than 4000 GPM

per KC pump:

RESPONSE NOT O B T A I N E D

CAUTION

If NC temperature is

greater than 200" F,

then KC flow must be

maintained greater

than 2000 GPM to

operating ND train.

- -

IF 1A KC Pumps are feeding 1 B ND Hx

(through cross-tie), r"

throttle

1 KC-81 B (KC TO B ND Hx).

1 KC-56A (KC TO A ND Hx)

-

KC to KF flow.

-

GO TO Step 37.

-

31.

Check ND pumps - ANY ON PRIOR TO

---

ENTERING THIS PROCEDURE.

...

I r r

I

I

LOSS OF KC OR KC SYSTEM LEAKAGE

Enclosure 4 - Page 13 of 17

Startup of 1A KC Train

PAGE NO.

44 of 80

Rev. 7

ACTION/EXPECTEO RESPONSE

-

32.

Check VI Pressure -GREATER THAN OR

EQUAL TO 60 PSIG.

Perform the following:

RESPONSf NOT OBTAINED

a.

-

1) REFER

AP/l/Af5500/19 (Loss

both ND pumps are off, THEN:

Of ND Or ND System Leakage).

-

2)

Step 37.

b. E any ND pump is on, THEN use the

following as required to determine KC

lo ND Hx flowrate in next step:

NOTE

ND Hx KC outlet flow

indication fails low on

loss of VI. KC pump

flow indication and

local ND Hx KC flow

should still be

- Use change in KC pump flowrate lo

determine KC to ND Hx flowrate.

Dispatch operator to monitor KC

outlet flow for ND Hx(s) in service:

RHR HX A OUTLET FLOW

- (1 MKCFS5670) (aux bldg, 733+1.

MM-54. across hall from EAT E

next to decon sink)

(1 MKCFS5680) (aux bldg, 733+1,

JJ-55. on west side of column

JJ-55).

RHA HX 6 OUTLET FLOW

-

1 I ,

I

i

I.

MNS .

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO.

Enclosure 4 - Page 14 of 17

Startup of 1A KC Train

45 of 80

Rev. 7

APII /N5500/2 1

UNIT 1

-c

I

'1

I

ACTION/EXPECTED RESPONSE

RESPONSE NOT O B T A I N E D

1

..

If both trains of KC Aux Bldg Non-essential header isolation valves are op.en. 1A

train of KC can supply cooling to 1 E ND Hx.

33.

Establish KC to running ND train(s) and

any ND train that is to be placed in

service, as follows:

a. Check 1A ND Pump - ON.

a. Perform the following:

-

1) If: 1A ND Pump will be started,

THEN GO TO Step 33.b.

2) a To Step 33.c.

- -_-

-

b. Align KC to 1A ND Hx as follows:

-

1 ) Limit KC pump flow to 4000 GPM

per operating KC pump in next step.

-

2) Throttle open 1 KC-56A (KC To A

ND Hx) to establish 2000 GPM lo

5000 GPM KC flow to ND Hx 1A.

c. =To 33.e

-

c. Check any 1 B Train KC Pump - ON.

-

d. a

To Step 33.f

-

e. m E S t e p 34.

e. Check the following valves open:

-

. 1 KC-28 (Trn B Aux Bldg Non Ess

Ret Isol)

. 1 KC-53B (Trn B Aux Bldg Non Ess

- . 1 KC-1 A (Trn A Aux Bldg Non Ess

Ret Isol)

. 1 KC-50A (Trn A Aux Bldg Non Ess

-

sup ISOl)

-

sup ISOI).

.>.

.:

. . .

i

fr--

I

-

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO.

Enclosure 4 . Page 15 of 17

Startup of 1A KC Train

46 of 80

APIl/PJ5500/2 1

Rev. 7

UNIT I

ACT IONIEXPECTED RESPONSE

I

RESPONSE NOT O B T A I N E D

1

33. (Fontinued)

-

1.

Check 1B.ND Pump - ON.

g. Align KC lo 1 8 ND Hx as follows:

-

1) Limit KC pump flow lo 4000 GPM

per opGrating KC pump in nexl step

-

2) Throttle open 1 KC-818 (KC To B

ND Hx) to establish 2000 GPM to

5000 GPM KC flow to ND Hx 16.

- 34.

Check any ND pump - RUNNING.

1.

Perform the following:

-

1)

-

2) ==Step

34.

15 ND Pump will be started,

THEN GO TO Step 33.9.

__

GO TO one of the following enclosures

to start desired ND pump that has KC

cooling established:

- Enclosure 6 (Startup of 1A ND Train)

Enclosure 7 (Startup of 1 B ND

Train).

-

I

i

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO.

Enclosure 4 - Page 16 of 17

Startup of 1 A KC Train

47 of 80

Rev. 7

AP/1 IN550012 1

UNIT 1

L

NOTE

Operating procedure

steps to locally listen

for vibration and to

align KC may be

NIA'd.

1) Swap ND trains to the train with KC

cooling PER OP/l/N610O/S0-6

(Placing The Second ND Train In

Service).

-

2) a m s t e p 3 7

-

A C T I ON/ E X P EC T C D RE S PON 5 E

b.

NC temperature is greater than

150" F,

5 minutes, THEN GO TO one of the

following enclosures to start desired ND

pump that has KC cooling established:

will be above 150" F within

RESPONSE NOT O B T A I N E D

Enclosure 6 (Startup of 1A ND

Train)

-

OR . Enclosure 7 (Startup of i B ND

- Train).

1 It

1

I

1

\\ I

4

MNS '

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO.

Enclosure 4

~ Page 17 of 17

Startup of 1A KC Train

48 Of 80

Rev. 7

APllIN5500/2 1

UNIT 1

-

36.

Check 1B train KC pumps - OFF.

IF AT ANY TIME is is desired to stop 1 B

train KC Pumps, THEN evaluate

performing the following:

NOTE

Operating procedure

steps to locally listen for

vibration and lo align KC

may be N/A'd.

-

a. Swap ND trains to 1A train and stop 1 B

ND Pump PER OP/l/N610O/S0-6

(Placing The Second ND Train In

Service).

-

b. WHEN 16 ND Pump is off, THEN stop

KC Pumps PER Steps 26 through 30.

-

37.

Check KC System leak - HAS

OCCURRED.

-

38.

TO Step 36 in body of procedure.

_--

GO TO Step 38 in body of procedure.

-

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO.

49 of 80

Rev. 7

Enclosure 5 - Page 1 of 17

AP/llN5500/2 1

ACTION/EYPECTED RESPONSE

RESPONSE NOT OBTAINED

I_

-

1.

Check 1 KC-81 B (KC To B ND Hx)

CLOSED.

UNIT I

Startup of 1 B KC Train

2

Check 1 KC-56A (KC To A ND Hx)

CLOSED.

Perform the following:

-

a. E a n y 1B KC Pump is on, AND 1B ND

pump is on, THEN GO TO Step 2.

b. If: all 1 B Train KC pumps are off.

1 B ND Pump off, m:

-

1) Close 1 KC-81 B

2) If: NC temperature is greater than

150" F, THEN:

a) Stop 18 ND Pump.

-

b) Close ND cross tie valves:

. 1 ND-18 (B ND HX Bypass)

- . 1ND-17 (B ND Hx To Letdown

Hx).

-

Perform the following:

a. E

any 1A KC Pump is on,

1A ND

pump is on, THEN GO TO Step 3.

b. E all 1 A Train KC pumps are off,

1A ND Pump off, m:

-

1) Close 1 KC-56A.

2 )

NC temperature is greater than

160" F, THEN:

a) Stop 1A ND Pump.

b) Close ND cross tie valves:

- 1 ND-33 (A ND Hx Bypass)

1 ND-32 (A ND Hx To Letdown

Hx).

-

GO TO Step 5.

_--

-

3.

Check 1 A Train KC Pumps - OFF.

I

1

LOSS OF KC OR KC SYSTEM LEAKAGE

,I

PAGE NO.

50 of 80

Rev. 7

I

A P / l I A $ X ~ l

Enclosure 5 - Page 2 of 17

Startup of 1 B KC Train

-

4.

Select "CLOSED"

on 1KC-51A (Train A

Recirc Isol).

GO TO Step 17.

- 5.

Check 16 Train KC Pumps - OFF.

_--

AC T I ON / E X P E C T E D RE 5 PONS E

NOTE

Voiding of 1B train KC may be suspected if any of the following have occurred:

1 B train KC pumps were tripped due to Cavitation or air entrainment.

1A train K% pumps were tripped due to cavitation or air entrainment while B

train was still cross-lied to A train.

RESPONSE NOT OBTAINED

6 . E

voiding of 1B train KC is suspected,

THEN dispatch operator to perform the

following:

- Open 1 KC-30 ( I 82 KC Pump Overlfow

Isol) (aux bldg, 733+3, "-57,

lop of KC

Pump 182) until a solid stream of water

is visible in sightglass then reclose valve

- Open 1 KC-27 (1 B 1 KC Pump Overflow

Isol) (aux bldg. 733+3, "-56.

top of KC

Pump l B l ) until a solid stream of water

is visible in sightglass lhen reclose valve

- Unlock and throttle 1 KC-I 2 ( 1 61 KC

Pump Discharge) (aux bldg, 733+6,

"-57,

east of KC Pump 1 81) to one

lum open.

7.

Close the following:

-

a. 1 KC-53B (Tm B Aux Bldg Non Ess Sup

- b. 1 KC-2B (Trn B Aux Bldg Non Ess Ret

- c.

1 KC-228B (Trn B Rx Bldg Non Ess Sup

-

d. 1 KC-1 8B (Trn B Rx Bldg Nan Ess Ret

Isol).

I

4.J

I

'1

MNS .'

UNIT 1

LOSS OF KC OR KC SYSl EM LEAKAGE

Enclosure 5 . Page 3 of 17

Startup of 1 B KC Train

PAGE NO.

Rev. 7

51 Of 80

AP/l/N5500/2 1

a

-

9

-

10.

-

11.

-

12.

-

13.

-

14.

-

15.

-

16.

-

17.

-

kCT I O N / E X P E C T E O RESPONSE

RESPONSE NOT OBTAINED

Start 1B RN Pump.

Ensure 1RN-1878 (B KC Hx Inlet Isol)

opens.

Place control switch for 1KC-548 (Train

B Recirc Isol) in the "AUTO" position.

Ensure 1KC-54B (Train B Recirc Isol)

opens.

I ,

Start 1B1 KC Pump.

Check 1KC-12 (1 B1 KC Pump Discharge)

Perform the following:

a. Start 182 KC Pump.

b. m m S t e p 17.

- LOCALLY THROTTLED IN STEP 6.

-

Have dispatched operator slowly throttle

open IKC-12 (1B1 KC Pump Discharge).

WHEN 1 KC-1 2 (1 B1 KC Pump Discharge)

is open, THEN start 182 KC Pump.

Ensure IKC-12 (181 KC Pump

Discharge) is fully opened and locked.

GO TO Step 20.

Check ND pumps - ANY ON PRIOR TO

_--

ENTERING THIS PROCEDURE.

1 I1

I

.

klNS .

LOSS OF KC Oh KC SYSTEM LEAKAGE

Enclosure 5 . Page 4 of 17

PAGE NO.

52 of 80

Rev. 7

AP/l/AJ5500/2 1

ACTION/CXPECTED RESPONSE

RESPONSE NOT OBTAINED

-

18.

Check VI pressure - GREATER THAN

60 PSIG.

Perform the following:

a. Dispatch operator to close the following

valves:

. 1KC-148 (A KF Hx Inlet) (aux bldg,

750~10, MM-52, 20 ft north of door lo

1 A ND Hx room)

-

. 1KC-155 (6 KF Hx Inlet) (aux bldg,

750+8, MM-52,20 ft north of doof to

1 A NO Hx room).

-

b. WHEN it is.desired to reestablish fuel

pool cooling, THEN:

1) Limit KC pump flow to 4000 GPM

per operating KC pump in next step

-

2) Dispatch operator to throttle open

the following valves as necessary:

1KC-I48 (aux bldg, 750+10,

- MM-52,20 ft north of door to 1A

ND Hx room)

MM-52,20 ft north of door to 1 A

NO H x room).

1KC-155 (aux bldg, 750+8,

-

c. m m S t e p 20.

- 19.

Throttle KC to KF flow as required in

subsequent steps to allow establishing

adequate KC flow to ND Hx.

I i r

I

7

A PI 1 /N5 500/2 1

1 11

UNIT I

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO.

53 of 00

Rev. 7

Enclosure 5 ~ Page 5 of 17

Startup of 1 B KC Train

ACTION/EXPECTED RESPONSE

2) 1 KC-2288 (Trn B Rx Bldg Non Ess

- sup Isol).

RESPONSE NOT O B T A I N E D

1

c. Close the following valves:

1) 1 KC-230A (Trn A Rx Bldg Non Ess

- sup Isol).

2) 1 KC-3A (Tm A Rx Bldg Non Ess

Ret Isol).

-

d. Open the following valves:

1) IKC-2B (Tm B Aux Bldg Non Ess

Ret Isol).

2) 1 KC-53B (Tm B Aux Bldg Non Ess

-

- sup ISOI).

e. ==Step25

-

I I1

I

l i

AP/l/N5500/2 1

I 1

UNIT1

LOSS OF KC OR KC SYSTEM LEAKAGE

,l

PAGE NO.

54 of 80

Rev. 7

Enclosure 5 - Page 6 of 17

Startup of 1 B KC Train

I

1

I

1

-

1

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

I

RESPONSE NOT OBTAINED

-

21.

Check KC header with leak- HAS BEEN

IDENTIFIED.

Perform the following:

a.

the reactor is critical, THEN GO TO

-

Step 23.

b. E

the reactor is subcritical, I":

-

1) WHEN KC header with leak is

identified, THEN perform Step 24.

2) m m S t e p 25.

-

. ,

-

22.

CO To Step 24.

23.

Attempt to establish KC cooling to NC

pumps as follows:

a. Close the following valves:

-

1) 1 KC-230A (Trn A Rx Bldg Non Ess

sup Isol).

-

2) 1 KC-3A (Trn A Rx Bldg Non Ess

Ret Isol).

-

b. Open 1 KC-1 8B (Trn B Rx Bldg Non Ess

Ret Isol).

-

c. Check 1 B KC Surge Tank level ~

STABLE OR GOING UP.

c.

1 B KC Surge Tank level going down

in an uncontrolled manner, MEN

perform the following:

-

1) Reclose 1KC-188 (Trn B Rx Bldg

Non Ess Ret Isol).

-

2) Trip the reactor.

-

3) WHEN reactor is tripped, THEN trip

all NC pumps. .

-

4)

EP/l/A/5000/E-O (Reactor

Trip or Safety Injection), while

continuing in this procedure as time

and conditions allow.

5)

To Step 23.1.

-

I

-

LOSS OF KC OR KC SYSTEM LEAKAGE

<'

PAGE NO.

55 of 80

Enclosure 5 . Page 7 of 17

Startup of 16 KC Train

AP/l/N5500/21

Rev. 7

L.

UNIT I

3

- d. Open 1 KC-2286 (Trn 6 Rx Bldg Non

Ess Sup Isol).

e. Check 16 Train KC:

e.

1 B KC Surge Tank level going down

in an uncontrolled manner,

flow and

- Surge Tank Level - STABLE OR

amps indicate air binding of KC pumps,

GOING UP

THEN perform the following:

A C T i O N / E X P E C T E D RESPOKSE

Pump flow and amps - NORMAL

-

,

I

RLSPONSE NOT OBTAINED

-

f.

Check KC header with leak - HAS

BEEN IDENTIFIED.

1 ) Reclose 1 KC-228B (Trn B Rx Bldg

Non Ess Sup Isol).

-

2) Reclose 1 KC-1 88 (Trn B Rx Bldg

Non Ess Ret Isol).

-

3) E

KC amps and flow indicate air

binding of pumps, THEN stop 16

train KC pumps.

-

4) Trip the reactor.

-

5 ) WHEN reactor is tripped, THEN trip

all NC pumps.

-

6)

a EP/l/A/5000/E-O (Reactor

Trip or Safety Injection), while

continuing in this procedure as time

and conditions allow.

-

7)

16 Train KC Pumps are off,

THEN RETURN TO Step 6.

1.

Petform the following:

-

1) WHEN KC header with leak is

identified, THEN perform Step 24

-

2)

Step 25

"

I [ AP11$;51

PAGE NO.

56 of 80

Rev. 7

/

LOSS OF KC OR KC SYSTEM LEAKAGE

Enclosure 5 ~ Page 8 of 17

Startup of 1 B KC Train

24.

Align KC as follows:

. a. Monitor the.following KC pump

parameters while aligning KC in this

step:

- Pump flow and amps

- - KC surge tank level.

-

b. Limit KC pump flow to 4000 GPM per

operating KC,pump in next step.

-

c. Check. LEAK IDENTIFIED ON 1A KC

TRAIN ESSENTIAL HEADER.

..

c. Perform the following:

1) Open the following valves unless

required closed to keep leak on

Reactor Bldg Header isolated:

a) 1KC-18B (Tm 6 Rx Bldg Non

Ess Ret Isol).

-

b) 1 KC-2286 (Trn B Rx Bldg Non

2) Close the following valves:

a) 1 KC-230A (Trn A Rx Bldg Non

Ess Sup Isol).

Ess sup Isol).

-

b) 1 KC-3A (Trn A Rx Bldg Non Ess

Ret Isol).

3) Open the following valves unless

required closed to keep leak on Aux

Bldg Non-essential Header isolated:

a) 1 KC-26 (Trn B Aux Bldg Non

Ess Ret Isol).

-

b) 1 KC-53B (Tm E Aux Bldg Non

4) GO TO Step 25

-

Ess sup ISOI).

-

1 I I

I

1

I

MNS ,

LOSS OF KC OR KC SYSTEM L E A K A ~ E

f

PAGE NO.

57 of 80

Rev. 7

Enclosure 5 - Page 9 of 17

Startuo of 1 B KC Train

A PI 1 I N 5 50012 1

UNIT I

ACTIONIEXPECTED RESPONSE

24. (Cpnfinued)

d. Close the following valves:

- 1) 1KC-230A (Trn A Rx Eldg Non Ess

sup Isol).

RESPONSE NOT O B T A I N E D

2) 1 KC-3A (Tm A R x Bldg Non Ess

Ref Isol).

-

e. Open fhe following valves:

-

1 ) lKC-186 (Trn B Hx Bldg Non Ess

Ret Isol).

-

2) 1 KC-2286 (Tm B Rx Bldg Non Ess

1.

Close fhe following valves:

-

1) 1 KC-50A (Tm A Aux Eldg Non Ess

sup Isol).

-

2) 1 KC-1 A (Trn A Aux Bldg Non Ess

Ref Isol).

g. Open the following valves:

1) IKC-26 (Tm E Aux Bldg Non Ess

Ret Isol).

-

2) .-1KC-53B (Tm E Aux Bldg Non Ess

s u p Isol).

MNS .

LOSS OF KC OR KC SYSTEM LEAKAGE

f

PAGE NO.

Enclosure 5 - Page 10 of 17

Startup of 1 B KC Train

58 of ao

Rev. 7

APll/A/5500/2 1

UNIT I

25.

Check

<'

1A ND Pump - OFF.

-

ACTION/EXPECTED RESPONSE

Perform the following:

a.

1A train KC pumpsare off, THEN

- _-

GO TO Step 28.

b. IF 18 ND pump is running, THEN:

1) Stop 1A ND Pump.

2) Close ND cross tie valves:

. 1 ND-33 (A ND Hx Bypass)

. 1 ND-32 (A ND Hx To Letdown

Hx). .

-

3) G m S t e p 26.

-

RESPONSE NOT OBTAINED

c.

1A KC surge tank is on scale,

can be maintained on scale for at least

15 more minutes (to allow time to swap

ND trains), THEN GO TO Step 32.

NC temperature is greater than

-

d.

150" F, THEN:

1) Slop 1A ND Pump.

2) Close ND cross tie valves:

-

1 ND-33 (A ND HX Bypass)

- . IND-32 (A ND Hx To Letdown

Hx).

-

I

UNIT 1

AP/1 /N5500/2 1

-

26.

Ch,eCk 1KC-56A (KC TO A ND Hx) -

CLOSED.

LOSS OF KC OR KC SYSTEd LEAKAGE

Enclosure 5 - Page 1 1 of 17

Startup of 1 B KC Train

PAGE NO.

59 of 00

Rev. 7

-

27.

Stop KC 1Al and 1A2 Pumps.

ACT I ON / E X P E C T E 0 RE S PON S E

-

28.

Place control switch for 1 KC-51A (Train

A Recirc Isol) in the "CLOSE" position.

I

RESPONSE NOT OBTAINED

1

Perform the following:

.

-

a. E 1 KC-50A (Trn A Aux Bldg Non Ess

Sup Isol)

1 KC-53B (Trn B Aux Bldg

Non Ess Sup Isol) is closed, THEN GO

Step 27.

b. E 1 A ND Pump is off, THEN:

-

1) Close 1 KC-56A (KC To A ND Hx).

-.. 2) -0

Step 27.

CAUTION

If NC temperature is

greater than 200" F,

then KC flow must

be maintained

greater than

2000 GPM to

operating ND train.

1 B KC Pumps will

continue to feed 1A ND

Hx after tripping 1 A KC

Pumps.

NOTE

c. Throttle the following as required to

ensure 1 B train KC pump flows will

remain less than 4000 GPM per pump

after stopping 1A train KC pumps:

- 1KC-56A (KC TO A ND Hx)

1 KC-81 B (KC TO B ND Hx)

-

KC to KF flow.

-

.,.;

~

..._.

LOSS OF KC OK KC SYSTEM LEAKAG~

I

PAGE NO.

MidS ..

UNIT 1

AP111N5500121

60 of 80

Enclosure 5 - Page 12 of 17

Startup of 1 B KC Train

Rev. 7

I

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

-

29.

Ensure 1KC-51A (Train A Recirc Isol)

cld'ses.

30

-

31.

-

Check KC flow - LESS THAN

4000 GPM PER OPERATING KC PUMP.

Throttle the following as required to

reduce KC flow to less than 4000 GPM

per KC pump:

Check ND pumps - ANY ON PRIOR TO

ENTERING THIS PROCEDURE.

CAUTION

If NC temperature is

greater than 2OO0F,

then KC flow must be

maintained greater

than 2000 GPM to

operating ND train.

IF 16 KC Pumps are feeding 1A ND Hx

(through cross-tie), THEN throttle

1KC-56A (KC To A ND Hx).

- -

1 KC-81 B (KC TO B ND Hx)

-

KC to KF flow.

-

_ _

GO TO Step 37.

I ll

I

1

~

LOSS OF KC OR KC SYSTEM LEAKAGE

Enclosure 5 - Page 13 of 17

PAGE NO.

61 of 80

Rev. 7

MNS .

AP/l/N5500/21

ACTION/EXPECTED RESPONSE

-

32.

Chpck VI pressure- GREATER THAN OR

EQUAL TO 60 PSIG.

Perform the following:

a.

-

1) REFER

AP/l/A/5500/19 (Loss

-

2) GOTO Step 37.

both ND pumps are.off, m:

Of ND Or ND System Leakage).

b. E

any ND pump is on, THEN use the

following as required to determine KC

to ND Hx flowrate in next step:

NOTE

ND Hx KC outlet flow

indication fails low on

loss of VI. KC pump

flow indication and

local ND Hx KC flow

should still be

available.

- Use change in KC pump flowrate to

determine KC to ND Hx flowrate.

Dispatch operator to monitor KC

outlet flow for ND Hx(s) in service:

- RHR HX A OUTLET FLOW

(1 MKCFS5670) (aux bldg, 733+1,

MM-54. across hall from EAT E

next lo decon sink)

(1 MKCFS5680) (aux bldg, 733t1,

JJ-55, on west side of column

- RHR HX E OUTLET FLOW

JJ-55).

MNS ,

LOSS OF KC OR KC SYSTEM LEAKAGE

I'

PAGE NO.

620f80

.

Rev. 7

Enclosure 5 - Page 14 of 17

Startup of 1 B KC Train

AP/l/A/5500/21

UNIT 1

\\

ACT ION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

1

"

NOTE

If both trains of KC Aux Bldg Non-essential header isolation valves are open, 1 B

train of KC can supply cooling to 1A ND Hx.

33.

Establish KC to running ND train(s) and

any ND train that is to be placed in

service, as follows:

a. Check 16 ND Pump - ON.

a. Perform the following:

-

1) ___-

THEN GO TO Step 33.b.

-

2) GO TO Step 33s.

113 ND Pump will be started,

b. Align KC to 1 B ND Hx as follows:

-

I ) Limit KC pump flow to 4000 GPM

per operating KC pump in next step.

-

2) Throttle open 1 KC-81 B (KC To B

ND Hx) to establish 2000 GPM to

5000 GPM KC flow to NO Hx 16.

c. G O T 0 33.e.

-

c. Check any 1 A Train KC Pump - ON.

-

d.

Step 33.1.

-

e. GO TO Step 34.

e. Check the following valves open:

-

. 1 KC-28 (Trn B Aux Bldg Non Ess

Ret Isol)

-

. 1 KC-538 (Tm B Aux Bldg Non Ess

-

sup Isol)

- 1 KC-1 A (Trn A Aux Bldg Non Ess

Re1 Isol)

- 1 KC-SOA (Tm A Aux Bldg Non Ess

sup Isol).

1 I,

I

_.

I

MNS I

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO.

Enclosure 5 - Page 15 of 17

StartuD of 1 B KC Train

63 of 80

Rev. 7

AP/l /N5500/2 1

UNIT 1

'U

I

I1

ACTIONIEXPCCT[D

RESPOllSE

RESPONSE NOT O B T A I N E D

1

33. (CQntinued)

-

1.

Check 1A ND Pump - ON.

g. Align KC lo 1A ND Hx as follows:

- 1) Limit KC pump flow to 4000 GPM

per opefating KC pump in next step.

-

2) Throttle open 1 KC-56A (KC To A

ND Hx) to establish 2000 GPM to

5000 GPM KC flow to ND H x 1A.

34.

Check any ND pump - RUNNING

1.

Perform the following;

1)

2)

TO Step 34.

1A ND Pump will be started,

- THEN GO TO Step 33.9.

---

-

--

GO TO one of the following enclosures

to start desired ND pump that has KC

cooling established:

. Enclosure 6 (Startup of 1 A ND Train)

Enclosure 7 (Startup of 1 B ND

Train).

-

1

I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

-

35.

Check KC flow to the operating ND

train's Hx - ESTABLISHED.

Perform the following:

a.

NC temperature is less than 150" F,

AND temperature is expected to stay

less than 150" F for at least 5 more

minutes, THEN:

NOTE

Operating procedure

steps to locally listen

for vibration and to

align KC may be

N/A'd.

-

1) Swap ND trains to the train with KC

cooling PER OPll/A/61 OO/SO-6

(Placing The Second ND Train In

Service).

-

2) G o a Step 37

b.

NC temperature is greater than

15'2" F.

5 minutes, THEN GO TO one of the

following enclosures to start desired ND

pump that has KC cooling established:

will be above 150" F within

- Enclosure 6 (Startup of 1A ND

Train)

Enclosure 7 (Startup of 1 B ND

Train).

-

AP/l/AJ5500/21

UNIT I

-

36.

Check 1A train KC pumps - OFF.

LOSS OF KC OR KC SYSTEM L E A K A G ~

,t

PAGE NO.

65 of 80

Rev. 7

Enclosure 5 - Page 17 of 17

Startup of 1 B KC Train

IF AT ANY TIME is is desired to stop 1A

train KC Pumps, THEN evaluate

performing the following:

NOTE

Operating procedure

steps to locally listen for

vibration and 10 align KC

may be N/A'd.

-

a. Swap ND trains lo 1 B train and stop 1A

(Placing The Second ND Train In

Service).

-

b. WHEN 1 A ND Pump is off, THEN stop

KC Pumps PER Steps 26 through 30.

NG Pump FER OP;I/N61 OC/SO-6

-

37.

Check KC System leak - HAS

OCCURRED.

---

GO TO Step 38 in body of procedure.

-

38.

To Step 36 in body of piocedure.

h

Y

. ..

. , ..

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO,

66 of 80

Rev. 7

.

I

J I

I AP/l$J5?1

1.

AP/I/A/5500/19 (Loss Of ND Or ND System Leakage) has been implemented, &@

additional makeup has been aligned PER AP/l/A/5500/19 (Loss Of ND Or ND System

Leakage), THEN:

-

a. Restart ND pump PER AP/l/A/5500/19 (Loss Of ND Or ND System Leakage).

-

b. m m S t e p 15.

Enclosure 6 ~ Page 1 of 3

Startup of i A ND Train

-

2.

Stop 1 B ND Pump.

'i

-

3.

Close IKC-EIB

(KC TO B ND HX).

4.

Close the following:

. 1 ND-29 (A ND Hx Outlet)

-

- 1 ND-34 (A & B ND HX Bypass)

.

1 ND-32 (A ND Hx To Leldown Hx)

-

- 1 ND-18 (B ND Hx Bypass)

.

1 ND-17 (6 ND Hx To Letdown Hx)

1 Nl-1788 (Train B ND To C & D CL)

1 ND-15B (Train B ND To Hot Leg Isol).

-

5.

Open the following valves:

1 NI-173A (Train A ND To A & 6 CL)

-

- .

1 ND-30A (Train A ND To Hot Leg Isol)

- 1 ND-33 (A ND HX Bypass).

I

-

6.

Limit KC pump flow to 4000 GPM per operating KC pump in next step:

- 7.

Throttle open IKC-56A (KC To A ND Hx) to establish 2000 GPM to 5000 GPM KC flow to ND

Hx 1A.

LOSS OF KC OR KC SYSTEM LEAKAGE

'

PAGE NO.

67 of 80

Rev. 7

Enclosure 6 - Page 2 of 3

AP11 /N5500/21

-

8.

E.1ND-35 (ND To FWST Isol) is known to be open, THEN ensure IND-35 is closed before

continuing in this procedure.

-

9.

Start 1 A ND Pump

- 10.

Ensure IND-68A (A ND Pump & A Hx Miniflow) opens.

1 1

-

Slowly throttle open IND-34 (A & B ND Hx Bypass) to obtain ND flow between 1000 to 2000

GPM.

12.

Throttle the following valves as necessary to maintain stable NC System temperature while

controlling ND flow between 1000 and 2000 GPM:

- 1 ND-29 (A ND Hx Outlet)

- 1 ND-34 (A & B ND Hx Bypass)

- -

IF NC temperature greater than 200" F, THEN maintain KC flow greater than 2000 GPM

.

- 1KC-56A (KC TO A ND Hx).

13. E desired to align ND to all 4 Cold Legs, THEN perform the following:

a. Open the following valves:

- .

1 Nl-1788 (Train B ND To C & D CL)

- 1ND-15B (Train B ND To Hot Leg Isol).

b. Throttle the following valves as necessary to maintain stable NC System temperature while

controlling ND flow greater than 2000 GPM:

- 1 ND-29 (A ND Hx Outlet)

- 1 ND-34 (A & B ND Hx Bypass)

-

NC temperature greater than 200" F, THEN maintain KC flow greater than 2000 GPM

- 1 KC-56A (KC TO A ND Hx).

t II

I

MlvS

APll/A/5500121

UNIT I

LOSS OF KC OR KC SYSTEM LEAKAGE

Enclosure 6 - Page 3 of 3

Startup of 1A ND Train

PAGE NO.

68 of 80

Rev. 7

-

14.

WHEN KC is aligned to aux building non-essential header, AND ND letdown is desired,

THEN establish letdown from the ND System

Control System Letdown), Enclosure 4.1 (Establishing Letdown Flow from the ND System,

Charging Flow, and Seal Injection Flow).

OP/1/A/6200/001A (Chemical and Volume

..

15. a one of the following steps in body of procedure:

- -

IF KC System leak has occurred, THEN GO TO Step 36 in body of procedure.

- -

IF KC System has remained intact, 'I'HEN GO TO Step 38 in body of procedure.

i a

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO.

69 of 80

Rev. 7

Enclosure 7 - Page 1 of 3

APll /N5500/2 1

1. E AP/l/A/5500/19 (Loss Of ND Or ND System Leakage) has been implemented, AND

additional makeup has been aligned PERAP/l/A/5500/19 (Loss Of ND Or ND System

Leakage), THEN:

-

a. Restart ND pump

-

b. a0 Step 15.

AP/l/A/5500/19 (Loss Of ND Or ND System Leakage).

I I.,

UNIT1

Startup of 1 B ND Train

-

2.

Stop 1A ND Pump.

-

3.

Close 1 KC-56A (KC To A ND Hx).

4.

Close the following:

- .

1 NI-173A (Train A ND To A & B CL)

- 1ND-30A (Train A ND To Hot Leg Isol)

- 1 ND-34 (A & B ND HX Bypass) .

- 1 ND-33 (A ND Hx Bypass)

1 ND-32 (A ND Hx To Letdown Hx)

- .

1 ND-17 (B ND Hx To Letdown Hx)

- 1ND-14 (B ND Hx Outlet).

-

5.

Open the following valves:

- 1 ND-18 (B ND Hx Bypass)

- 1 NI-1788 (Train B ND To C 8, D CL)

- 1ND-156 (Train B ND To Hot Leg Isol).

-

6.

Limit KC pump flow to 4000 GPM per operating KC pump in next step.

-

7. Throttle open IKC-81 B (KC To B ND Hx) to establish 2000 GPM to 5000 GPM KC flow to ND

Hx 18.

-

I

LOSS OF KC OR KC SYSTEM LEAKAGE

PAGE NO.

70 Of 80

Rev. 7

Enclosure 7 - Page 2 of 3

Startup of 1 B ND Train

APll /N5500/21

UNIT 1

-

8.

E.lND-35 (ND To FWST Isol) is known to be open, THEN ensure IND-35 is closed before .,

continuing in this procedure.

-

9.

Start 1B ND Pump.

- 10.

Ensure IND-67B (B ND Pump & B Hx Miniflow) opens.

- 11.

Slowly throttle open IND-34 (A & B ND Hx Sypass) to obtain ND flow between 1000 to 2000

GPFA.

12.

Throttle the following valves as necessary to maintain stable NC System temperature while

controlling ND flow between 1000 and 2000 GPM:

- 1ND-14 (B ND Hx Outlet)

- 1 ND-34 (A & B N D Hx Bypass)

-

N C temperature greater than 200" F, THEN maintain KC flow greater than 2000 GPM

- 1 KC-81 6 (KC TO B ND Hx).

13. E

desired to align ND to all 4 Cold Legs, THEN perform the following:

a. Open the following valves:

- -1 NI-173A (Train A ND To A & B CL)

- 1 ND-30A (Train A ND To Hot Leg Isol).

b. Throttle the following valves as necessary to maintain sta6le N C System temperature while

controlling ND flow greater than 2000 GPM:

- 1ND-14 (B ND Hx Outlet)

- 1 ND-34 (A & B N D Hx Bypass)

- -

IF N C temperature greater than 200" F, THEN maintain KC flow greater than 2000 GPM

- 1 KC-81 B (KC TO B N D Hx).

I

LOSS OF KC OR KC SYSTEM LEAKAGE

'

PAGE NO.

71 of 80

AP11 IN5500121

UNIT 1

Rev. 7

Enclosure 7 - Page 3 of 3

Startup of 1 B ND Train

-

14.

WHEN KC is aligned to aux building non-essential header, AND ND letdown is desired,

THEN establish letdown from the ND System PER OP/llA/6200/001 A (Chemical and Volume

Control System Letdown), Enclosure 4.1 (Establishing Letdown Flow from the ND System,

Charging Flow, and Seal Injection Flow).

15.

one of the following steps in body of procedure:

- E KC System leak has occurred, THEN GO TO Step 36 in body of procedure.

- -

IF KC System has remained intact, THEN GO TO Step 38 in body of procedure.

I II

I

1

MNS ..

UNIT I

AP/1 /AJ5500/2 1

LOSS OF KC OR KC SYSTEM LEAKAGE

Enclosure 8 - Page 1 of 5

VCT High Temperature Actions

PAGE NO.

72 of 80

Rev. 7

AClION/EXPECTEO RESPONSE

1

f

... ..

RESPONSE NOT OBTAINED

1

1.

lsqlate letdown as follows:

a. Close:

- 1NV-458A (75 GPM UD Orifice

Outlet Cont Isol)

- 1 NV-457A (45 GPM UD Orifice

Outlet Cont Isol)

- 1 NV-35A (Variable UD Orifice Oullel

Cont Isol).

,

I

b. Close:

1 NV-1A (NC UD lsol To Regen Hx)

-

- 1 NV-2A (NC UD IS01 TO Regen HX)

-

c. Check ND - IN SERVICE PRIOR TO

-

c. a m S l e p 2 .

EVENT.

-

d. Close INV-121 (ND Letdown Control).

-

2.

Check N Y pumps suction - ALIGNED TO

VCT.

procedure.

-

RETURN

step in effect in body of

CAUTION

VCT high temperature will degrade NC pump seal cooling and NV pump

- operation.

NOTE

A loss of KC cooling to KC aux building non-essential header causes VCT

temperature lo rise, primarily due lo NV pump recirc flow.

-

3. E restoration of KC cooling to aux

building non-essential header is

expected within next 15 minutes, THEN

exit this enclosure.

-

4.

Check excess letdown - ISOLATED.

Perform the following:

-

a. Place 1NV-276 (Excess UD Hx Ollt

3-Way Cnlrl) to "NCDT" position.

-

b.

Step 6.

1

I It

1

t

I

1

I

PAGE NO.

Rev. 7

r

MNS .'

LOSS OF KC OR KC SYSTEM LEAKAGE

73 Of 80

Enclosure 8 - Page 2 of 5

APII /N5500/2 1

UNIT1

VCT Hiah TemDerature Actions

ACTION/EXPECTED RESPONSE

5.

,

IF AT ANY TIME excess letdown must be

eGtablished, AND KC cooling still lost to

KC aux buildi,ng non-essential header,

THEN excess letdown must be aligned to

NCDT instead of VCT.

-

I

RESPONSE NOT O B T A I N E D

I

NoTE

PD Pump will not heat up VCT since it does not recirc water to VCT.

Running PD Pump instead of swapping NV lo FWST will prevent thermal

transient on NC Pumps, and allow continued operation of unit. 1A and 1 B NV

Pumps will be stopped to prevent VCT overheating.

GO TO Step 15.

---

6.

Check:

PD Pump - AVAILABLE TO RUN

- Charging flow demand - LESS THAN 90

-

GPM

1 ETA - ENERGIZED

-

- 1RN-42A (AB Non Ess Supply Isol)

OPEN.

MNS ,

LOSS OF KC OR KC SYSTEM LEAKAGE

I'

PAGE NO.

74 Of 80

Rev. 7

Enclosure 8 - Page 3 of 5

APll IN550012 1

1 1

UNIT1

VCT High Temperature Actions

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

1

GO TO Step 15

_--

7.

Start PD Pump as follows:

a. Open the following valves:

- 1 RN-63E (AB Non Ess Return Isol)

- 1 RN-64A (AB Non Ess Return Isol)

- b. Place "PD PUMP SPEED CNTRL" in

"MAN" and set for minimum speed.

-

c. Open 1NV-1047A (PD Pump

Recirculation).

-

d. Start the PD Pump.

-

e. Ensure 1 NV-1047A closes after 2

minutes.

- 1. WHEN 1NV-1047A (PD Pump

Recirculation) is closed, THEN raise

"PD PUMP SPEED CNTRL" lo

establish desired charging flow.

-

8.

Close INV-238 (Charging Line Flow

Control) while maintaining charging flow

with PD Pump.

-

9.

Stop 1A and 16 NV Pump.

- 10.

Place INV-238 (Charging Line Flow

Control) at 80% open.

I f t

I

PAGE NO.

75 of 80

Rev. 7

f

LOSSOFKCORKCSYSTEMLEAKAGE

Enclosure 8 - Page 4 of 5

AP/l/N5500/21

I 1

UNIT1

VCT Hiah Temoerature Actions

I

.,

J-.

,

I ]

I

ACT I ON / E X P E C T E D RE S P ON S E

RESPONSE NOT OBTAINED

1

NC pump seal return flow may still cause VCT heatup.

..: Y

-

1 1 .

Check VCT temperature - LESS THAN

125' F.

Perform the following:

CAUTION

NC pumps number 1

seal DIP will go

down by

approximately 100

PSlD when valves

are closed in next

step.

a. Close one of the following:

- 1 NV-94AC (NC Pumps Seal Ret Cont

Inside Isol)

OR . 1 NV-955 (NC Pumps Seal Ret Cont

Outside Isol).

b. WHEN KC restored to KC aux building

non-essential header, THEN valves

above may be reopened to align seal

return to VCT.

-

c. m m S t e p 13

- 12.

IF AT ANY TIME VCT temperature goes

above 125" F, THEN observe Note prior

toStep11 andRETURNmStep11.

13.

IF AT ANY TIME 1 A or 1 B NV Pumps

must be started, AND KC cooling still lost

to KC aux building nonessential header,

____

THEN GO TO Step 15.

-

14.

RETURN

step in effect in body of

procedure.

b 11

I

7

I

MNS ..

LOSS OF KC OR KC SYSTEM LEAKAGE '

PAGE NO.

76 Of 80

Rev. 7

Enclosure 8 - Page 5 of 5

VCT High Temperature Actions

APll lAl550Ol21

UNIT I

15.

Check Reactor - TRIPPED.

<%

-

ACTION/EXPECTEO RESPONSE

16.

Swap NV suction to FWST as follows:

RESPONSE NOT O B T A I N E D

a. Open:

I '

.

- 1 NV-221A (NV Pumps Suct From

FWST)

- 1 NV-2228 (NV Pumps Suct From

FWST).

b. Close:

- 1NV-141A (VCT Outlet Isol)

- 1NV-1428 (VCT Outlet Isol)

17.

WHEN KC cooling is restored to KC aux

building non-essential header, THEN NV

suction may be realigned to VCT as

follows:

a. Open:

- 1NV-141A (VCT Outlet Isol)

- 1NV-1428 (VCT Outlet Isol).

b. Close:

- 1 NV-221A (NV Pumps Suct From

FWST)

- 1 NV-222B (NV Pumps Suct From

FWST).

Perform the following:

a. Reduce turbine load,as required to

maintain T-Ave at T-Ref in subsequent

steps.

Downpower) as required.

-

b. REFER

AP/l/N5500/04 (Rapid

- 18.

RETURN To step in effect in body of

procedure.

I

r,

1

MNS ..

LOSS OF KC OR KC SYSTEM LEAKAGE

/

PAGE NO.

77 of a0

Rev. 7

Enclosure 9 - Page 1 of 4

UNIT I

Reooenina KC Headers

APIl lAf5500/21

1 . E

.< header to be placed in service has had a leak or experienced voiding, T":

..

NOTE

If available, it may be preferrable to fill using KC train lhat is less critical lo

plant operation.

- Evaluate performing actions to ensure header is filled and vented prior lo opening any

non-essential header isolation valves from the control room.

- -

IF necessary lo fill a voided or drained non-essential header, THEN evaluate locally slowly

cracking open supply isolation valve from one train of KC while monitoring KC pumps and

surge tank lewds.

2. E

desired to align 1A KC train to Reactor Bldg Non-essential header, THEN perform the

following:

a. Close the following valves:

-

1) 1 KC-2288 (Tm B Rx Bldg Non Ess Sup Isol).

-

2) 1 KC-1 8B (Trn B Rx Bldg Non Ess Ret Isol).

b. Open the following valves:

-

1) 1 KC-3A (Trn A Rx Bldg Non Ess Ret Isol).

-

2) 1 KC-230A (Trn A Rx Bldg Non Ess Sup Isol).

3.

desired to align 1 B KC train to Reactor Bldg Non-essential header, THEN perform the

following:

a. Close the following valves:

- 1) 1KC-230A (Tm A Rx Bldg Non Ess Sup Isol).

-

2) 1 KC-3A (Tm A Rx Bldg Non Ess Ret Isol).

b. Open the following valves:

-

1 ) 1 KC-18B (Trn B Rx Bldg Non Ess Ret Isol).

-

2) 1 KC-228B (Tm B Rx Bldg Non Ess Sup Isol).

I

.

.,

LOSS OF KC OR KC SYSTEM L E A K A G ~

r

PAGE NO.

Enclosure 9 - Page 2 of 4

UNIT 1

Reopening KC Headers

78 of 80

Rev. 7

PI1 /N5500/2 1

4.

IF desired to align just 1A KC train to Aux Bldg Non-essential header, THEN perform the

Gllbwing :

' a. Close the foilowing valves:

-

1) 1KC-536 (Tm B Aux Bldg Non Ess Sup Isol).

-

2) 1 KC-26 (Trn B Aux Bldg Non Ess Ret Isol).

b. Open the following valves:

-

1) 1 KC-1A (Trn A Aux Bldg Non Ess Ret Isol).

-

2) 1 KC-50A (Tm A Aux Bldg Non Ess Sup Isol).

,

I

5. E desired to align just 16 KC train to Aux Bldg Non-essential header, THEN perform the

following:

a. Close the following valves:

-

1) IKC-SOA (Trn A Aux 6ldg Non Ess Sup Isol).

-

2) 1 KC-I A (Trn A Aux Bldg Non Ess Ret Isol).

b. Open the following valves:

-

1 ) 1 KC-28 (Trn B Aux Bldg Non Ess Ret Isol).

-

2) IKC-536 (Trn B Aux Bldg Non Ess Sup Isol).

-

APIllN5500~2

1

UNIT 1

.?.

LOSS OF KC OR KC SYSTEM LEAKAGE

Enclosure 9 - Page 3 of 4

Reopening KC Headers

PAGE NO.

79 of 80

Rev. 7

CAUTION

Reopening Aux Bldg Non-essential header isolation valves in next step

will align operating train to opposite trains essential header and to any

loads that are opened on opposite train (ND Hx and Reactor Bldg

Non-essential header).

6.

desired to reopen both trains of Aux Bldg Non-essential header valves (to establish

normal alignment). THEN open the following valves:

A Train:

I

S

-

a. 1 KC-IA (Trn A Aux Bldg Non Ess Ret Isol).

-

b. 1 KC-50A (Trn A Aux Bldg Non Ess Sup Isol)

B Train:

-

a. 1 KC-28 (Tm B Aux Bldg Non Ess Rei Isol).

-

b. 1 KC-53B (Trn B Aux Bldg Non Ess Sup Isol)

I

4

-