ML080370565

Post Exam Comments and Technical References (Folder 1)

ML080370565
Person / Time
Site:	Indian Point
Issue date:	01/31/2008
From:	Davis S Entergy Nuclear Indian Point 2
To:	NRC Region 1
Hansell S
Shared Package
ML071150011	List: IR 05000247/2007301 ML071170096 ML080370072 ML080370565
References
50-247/07-301
Download: ML080370565 (32)

Text

Attachment 4 Comments on Indian Point 2 January 2008 Initial License Examination Facility Representative: J Page 1 of 8

Attachment 4 Question 19 The on-shift RO while takmg manual logs has noticed an incorrect value he logged on the previous reading and that the reading is mof specification.

In accordance with OAP-17, Plant Surveillance and Operator Rounds, in addition to notifylng the CRS, whch one of the following correctly describes the required actions the operator shall take to correct the log reading?

A. A single line shall be drawn through the incorrect value, the correct value logged and the change dated and initialed. The correct value should then be circled in red with a numbered explanation placed in the remarks section.

B. A single line shall be drawn through the incorrect value, the correct value logged and the change initialed and dated. A numbered explanation is then placed in the remarks section.

C. The incorrect value shall be circled in red and the correct value logged.

These changes will be initialed and dated.

D. The incorrect value shall be circled in red and the correct value, with an explanation, placed in the remarks section. These changes will be initialed and dated.

Answer: A Reference(s): OAP-17 Rev. 04,0AP-5Rev.01.

Comment:

The stem of the question is not clear regarding which reading is out of specification. There are two possible answers depending on the candidates interpretation of the stem. Three out of eight candidates asked questions of the proctor as to which reading was out of specification, indicating that the stem of the question is unclear.

The stem indicates the reading is out of specification, but it is not clear if the incorrect earlier recorded reading was recorded out of specification and was actually in specification or if the reading was recorded as in specification and actually was out of specification, Page 2 of 8

Attachment 4 Question 19 (continued)

Case #1 If the reading was logged incorrectly out of specification, but the actual reading was in specification the operator is required to single line and correct the reading and note in the log of the incorrect observation of the instrument in question on the logs he took. Therefore the correct answer would be B.

Case #2 If the earlier reading was logged incorrectly in specification, but the actual reading was not in specification, the operator is required to single line the entry, red circle the actual reading, and log the explanation. Therefore the correct answer would be A.

References:

OAP-017 Recornmenda tion:

Recommend accepting both answers A and B depending on the candidates interpretation of the stem of the question.

Attachment 4 Question 57 The plant is operating at 100% power with the following indications and alarm SJF (1-5) "Instrument Air Low Pressure"just came into alarm.

Based on this, select the choice that best completes the following statement:

"The IA compressors (1) be running and hiahest PI-I 144 Instrument Air Header Pressure would be expected to indicate (2) .

A. (1) will (2) 95psig B. (1) will (2) 90 psig C. (1) will not (2) 95 psig D. (1) will not (2) 90 psig Answer: B Reference(s): 2-ARP-SJF Rev. 35 Comment:

The stem of the question does not cleaily state the time frame "etween the alarm actuation and the operator observing the Instrument Air pressure indication. The stem also implies that indications will be provided and no indications were given.

The instrument that provides the Instrument Air Low pressure alarm, PC-13443, can reset as high as 1OOpsig (Reference WO IP2-06-00054). PI- 1144R (CCR) will be reading differently at the moment of actuation than local indicator PI- 1144 due to capillary tubing to the CCR. PT-1144 alarm actuation will occur ahead of a pneumatic signal that is developed on 15' in 480V room and read on 53' in the CCR.

The stem of the question is unclear regarding referenced indications and time specified between alarm actuation and observation of Instrument Air pressure. Additionally, the Instrument Air Low Pressure alarm could still be illuminated up to 1OOpsig. Therefore, the highest expected pressure would be 95psig.

Page 4 of 8

Attachment 4 Question 57 (continued)

References:

Drawing 1999MC3516 ARP SJF WO IP2-06-00054 PM No. 1518 Data sheet Recommendation:

Recommend accepting both answers A and B, as both answers are possible.

Page 5 of 8

Attachment 4 Question 72 Given the following conditions:

-The Unit is in Mode 1

- 90% power and stable.

-All Tavg channels are approximately3 F higher than Tref.

Which one of the following modes on the Rod Control System Bank Selector Switch will provide the FASTEST rod speed if rod motion is demanded?

A. Control Bank "A" B. Shutdown Bank "A" C. Automatic D. Manual Answer: B Reference(s): SD 16.1 Rev. 4 Comment:

The stem of the question states that the plant is in MODE 1 at 90 % power. Answers A and B would be violations of the Unit 2 Core Operating Limit Report (COLR) and Technical Specification for Control Bank Overlap Limits and Control and Shutdown Bank Insertion Limit. Answers A and B would not be permitted for the conditions stated in the stem of the question.

In AUTO (with conditions provided) the demand would be 8 stepdmin. answer C. With operator action in MANUAL the rods will step in at 66 steps/min, leading the candidate to select answer D.

References:

Unit 2 T e c h c a l Specifications3.1.5,3.1.6 Graph WC-6 (COLR)

Recommendation:

Change the answer to this question from B to D.

Page 6 of 8

Attachment 4 Question 86 Given the following plant conditions:

-Unit 2 has experienced a Loss of All AC Power ECA-0.0 is being implemented and the team has reached the step to BLACK START the Gas Turbines per the applicable SOP.

Based on these conditions, which of the following choices contains a correct combination Of:

(1) What is an action which would have been taken prior to power restoration (2) What is the first 480V load started or verified started when an AC power train is restored?

A. (1) Place ALL ECCS (Emergency Core Cooling System) pumps in PULLOUT.

(2) A SW pump on the essential header.

B. (1) Place selected, but not all, ECCS (Emergency Core Cooling System pumps in PULLOUT.

(2) An AFW pump.

C. (1) Locally trip all running EDGs (2) A SW pump on the essential header.

D. (1) Remotely trip all running EDGs (2) An AFW pump.

Answer: C Reference(s): 2-ECA-0.0 Rev. 0,2-S0P 27.5.3 Rev. 11.

Comment:

FSAR Section 6.2 states, at IP2, the emergency core cooling hnction is performed by the safety injection system. Therefore, whenever the term emergency core cooling system or ECCS is referred to in the document it is synonymous with the safety injection system. The words all ECCS pumps in answer A, refers to the Safety Injection (SI) and Residual Heat Removal (RHR) pumps Page 7 of 8

Attachment 4 Question 86 (continued)

RNO step 5.a.2.c and RNO step 7.b.3 direct the blackstart of the Gas Turbines. The direction to blackstart the Gas Turbines is dependent on offsite power not being readily available. The direction to blackstart the Gas Turbines in step 5 RNO would only be done if offsite power is not readily available. Regardless of when the direction to blackstart the Gas Turbines is provided, step 6 would be completed prior to power restoration via the Gas Turbines.

Step 6 of ECA-0.0 places all components, except Service Water Pumps, that could automatically start in pullout. The SI and RHR pumps are a subset of the components placed in pullout. Therefore answer A is also correct.

Reference:

2-ECA-0.0 2-ECA-0.0 Background Document UFSAR section 6.2 Recommendation:

Recommend accepting both A and C as correct answers.

Page 8 of 8 (cont.)

Reference Material

NO:OAP-017 Rev: 4 PLANT SURVEILLANCE AND OPERATOR ROUNDS Page 6 of 41 cr 4.1.10.3 Data to be corrected SHALL be lined out, initialed and the correct entry noted.

4.1.10.4 Missed readings or deviations from the accepted time intervals SHALL be noted and explained in the Remarks Section and reported to the CRS.

4.1 . I 0 5 Each comment in the Remarks Section which is used to explain the reason(s) for an abnormal reading and describes any subsequent actions, should have a number assigned to correlate the remark with the abnormal data.

4.1.10.6 E the conditions exist past the end of a shift, subsequent shifts' remarks may reference an earlier shift the same day.

4.1.10.7 The person recording data SHALL sign the log sheet at the end of each shift upon being relieved on shift by another operator UNLESS they are an official watch station trainee.

4.1.10.8 IF log sheet readings are taken by an individual other than the person assigned the watch, the second individual SHALL sign the additional signature block UNLESS they are an official watch station trainee they are a NPO who is giving the CCR data from their field surveillance log.

4.2 Plant Surveillance 4.2.1 For logkeeping purposes, a new day SHALL start on each midnight shift. A new surveillance log SHALL be initiated on this shift.

4.2.2 Operators SHALL be knowledgeable of the equipment parameters that are logged and the significance of each parameter. In particular, operators should be alert for trends or the absence of expected trends.

The CRS SHALL be consulted when questions arise.

1 PLANT SURVEILLANCE AND OPERATOR ROUNDS 1 NO:OAP-017 Page 7 of 41 4.2.3 Tech Spec, TRM or ODCM itemdlimits are specified in miscellaneous field, special instruction and/or background document.

4.2.4 Entries required by Technical Specifications, Technical Requirements Manual (TRM) or other licensing commitments SHALL NOT be omitted. In cases where this is unavoidable, the CRS SHALL be contacted immediately. The CRS SHALL ensure appropriate actions in accordance with Tech Spec or TRM Specifications are taken.

4.2.5 Log points that do NOT have a specific MODE, as shown in applicability of the Background section or in miscellaneous field, special instruction and/or background document for each log point, are taken in all modes.

4.2.6 Only SM or CRS may authorize precluding surveillance readings.

The reason for the exceptions and the SM/CRS approval SHALL be documented in the appropriate log.

4.2.7 -

IF surveillance log entries are NOT to be taken, THEN the watchstander SHALL indicate so in the entry space and document the reason as a comment.

4.2.8 Any readings outside of Normal range should be logged first, questioned, corrected E feasible.

4.2.9 -

IF the only instrument installed to record a given parameter is out of service, THEN data should be recorded using alternate method AND noted in the comments (for paper logs - remarks) section.

4.2.9.1 A Temporary Alteration (TA) may need to be implemented for the temporary instrument in addition to a procedure revision or temporary procedure change (TPC).

4.2.9.2 The SM SHALL approve the use of an alternate indication source.

4.2.9.3 WHEN Technical Specification readings are involved, THEN the alternate source indication instruments SHALL have the same accuracy or better.

4.2.10 Conditions and readings out of range or Min/Max SHALL be promptly brought to the attention of the CRS. Additionally, these readings, SHALL be circled in red (in eSOMS the reading will be red and underlined) and a comment provided as follows:

0 Reason for the condition or reading 0 Corrective action, when performed or attempted

I I j I 1 I j j

I I

j I

I jI j

I I I I

I j j

I I

i I

i I

1 I

I I

m-11 I

I I

I I

I I

!I I

- - = q C I

I 1 I I

8.S "I I

NO: 2-ARP-SJF Rev: 35 COOLING WATER AND AIR Page 21 of 43 3

INPUT DEVICE:

i I 1-5 INST AIR LOW PRESS S ETPOlNT: 90 psig 1.o CAUSES 1.I Low Instrument Air pressure in all headers except Turbine Hall.

2.0 A UT0MAT IC ACT IONS 2.1 Instrument Air Compressors in AUTO should have started when pressure decreased to 95 psig.

3.0 SUBSEQUENT ACTIONS 3.1 CHECK the pressure of the Instrument Air Header AND DIRECT NPO to CHECK the Instrument Air Compressor(s).

3.2 the Instrument Air pressure is less than 90 psig, THEN perform the following:

3.2.1 DIRECT NPO to VERIFY Instrument Air Compressor(s) are running in AUTO.

3.2.1.1 IF NOT running in AUTO, THEN START Instrument Air Compressor(s) in HAND.

3.2.2 GO TO 2-AOP-AIR-I, (Air System Malfunctions).

4 .O REFERENCES

4.1 Drawings

0 9321-2036, 205797, 9321-3233, 9321-3134 Sheet 6 4.2 Technical Specifications:

0 None

Indian P o i n t E n e r g y C e n t e r I P 2 Information Copy - R e v 0

E 1 of 11 WORK ORDER # IP2-06-00054 01/16/2008 16

42 I1111111111111111111111111111111I1 llI1111111 l 1111l1 lIlIII1 l 11 Problem / Work Requested:

ALARM CAME IN -15# EARLY. PI-1144 AT SAME: TAP WAS 114PSIG. VERIFY ALARM SETPOINT ON DEVICE.

I Location :

Loc.Descrip: INSTRUMENT AIR NUCLEAR SERVICE HEADER PRESS CONTROL SWITCH Building / Elevation: IP2-CB-15 Equipment: INST3065-001

Description:

ITT BARTON 580A-1 PRESSURE Model # 580A-1 Serial # -

917 Reported By: OROHLA Date : 01/09/2006 Planner: SBYRNE Supervisor: RKARASI Loop : <none>

Priority : 3 System: -

IA QA Class: -

A Work Type: M ELECTIVE MAIN EQ : N

- Outage ID: NON Week/Mode: FIN Status : CLOSED Project No: <none>

Response Dep :MFIC Change of Scope YES / NO (circle one):

R e l e a s e f o r Work Supervisor to verify WO in'progress : - Date :

LCO / AOT # :

Tagout# ( s ) :

Work C o m p l e t e / Closeout Supervisor / Lead: Date :

Retest Reqd? Yes 1 No In Scope of Work Signature/Date WRT Loc: CCR:PANEL SJ Work Accepted (WCC) Yes / No New WO Number:

Signature/Date STOP THINK ACT REVIEW S e t Your T e a m m a t e s Up For Success

Indian Point Energy Center IP2 Information Copy - R e v 0 S E 8 of11 WORK ORDER # IP2-06-00054 01/16/2008 16:42 Actions Taken performed calibration check as per und out of spec, left in service/in spec. 91 psi decreasing, ...wa/sss ... fin ...1/23/06 As - Found Condition:

Indian Point Energy Center IP2 Information Copy - R e v 0

E 11 of11 WORK ORDER # IP2-06-00054 01/16/2008 16

42 PWT Plans PWT PreImplementation Review Issued By: -.

PMTSEQ#: 01 PMT GROUP: FIN SUPERVISOR/ENGINEER: 00000/00000SNSC REVIEW DATE: N/020202 PMT LIM COND: PER STEPLIST IN WORK PACKAGE CAL EQUIP: PER STEPLIST IN WORK PACKAGE TEST PREC: PER STEPLIST IN WORK PACKAGE TEST PROC:

THE FIN SUPERVISOR HAS DETERMINED THAT THE WORK PERFORMED HAS BEEN TESTED IN THE WORK PACKAGE OR WORK PLAN WITH NO ANOMALOUS CONDITION.

SAT R.Karasinski 1/23/06 FI:N SUPERVISOR / DATE TEST ACC CR:

TESTING COMPLETED IN THE WORK PACKAGE PROVIDES SATISFACTORY OPERATION OF EQUIPMENT REPAIRED WITH NO ANOMALOUS CONDITIONS.

REVIEWED: SAT R. Huron 1/23/06 SAT / UNSAT FIN SRO / DATE PWT Completion Review WE: SAT UNSAT /

SM: SAT UNSAT /

OPS PPMIS ENTRY /

TEST ENG: SAT UNSAT /

- _. ~- . __ - _._ _ ~- - ~~~ __

STOP THINK ACT REVIEW Set Your Teammates Up For Success

INSTRUMENT CALXBRATION System: 1A Location: 1SEL 480 VOLT SWGiY RM PMNo.: 1518 Loop: ~ ~ __ ~ ___. I_ Datasheet: - 5 OF-5 Manufacturer: IIT BARTON~ ------_

58OA-1 Serial No.; .__ Tag NO.:'@C%Zi%&$

Input Range: ______.__

0 TO 160 PSiG Output Range ALARM Setpaint Source: SPKN - ---_- _____ ~

Acceptance Criteria: MAXIMUM PERMISSIBLE ERROR SHALL BE NO MORE THAN: +I- 3 PSKC Test Measurement: PRESSURE I

CALIBRATION DATA Desired Outaut I I I 1 ALARM VERIFIED YES I NO 1

TEST IN!3TRUMENTS USED IN CALIBRATION - 1 PRECAUTIONS & LIMITATIONS j

j TYPE I 1 MFR. SERIALNO. i I

NEXT DUE CAL DATE 1 IF NECESSARY:

DATE OF TEST CONDITION REPORT NUMBER ITEM !

OTHERWISE NIA TECHNICIAN REVIEWED BY

Shutdown Bank Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each shutdown bank shall be within insertion limits specified in the COLR.

APPLICABILITY: MODES Iand 2.

ACT10NS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more shutdown A.l .I Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> banks not within limits. limits; specified in the COLR.

OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.

A.2 Restore shutdown banks 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to within limits.

B. Required Action and B. 1 Be in MODE 3 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

INDIAN POINT 2 3.1.5 - 1 Amendment No. 238

Control Bank Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Control Bank Insertion Limits LCO 3.1.6 Control banks shall be within the insertion, sequence, and overlap limits specified in the COLR.

APPLICABILITY: MODE I ,

MODE 2 with kfi21.O ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank insertion A.l .I Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limits not met. limits specified in the COLR.

A.1.2 Initiate boration to restore Ihour SDM to within limit.

A.2 Restore control bank(s) to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> within limits.

B. Control bank sequence B.l .I Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or overlap limits not met. limits specified in the COLR.

B.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.

INDIAN POINT 2 3.1.6 1- Amendment No. 238

Indian Point Unit 2 Cycle 18 COLR Page 3 of 11 NOTE The Technical Specification references shown next to each Factor Limit in this COLR, are there to identify the corresponding sections in the Technical Specifications, that refer to the COLR.

The data presented in this report applies to Cvcle 18 ONLY and may NOT be used for other cycles of operation. Any technical change to this document requires a Safety Evaluation to be performed in accordance with 10 CFR 50.59.

TS 2.0 Safetv Limits (SLs)

In MODE .Iand 2, the combination of thermal power level, pressurizer pressure, and highest loop average coolant temperature SHALL not exceed the limits shown in Figure 1.

The safety limit is exceeded if the point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.

TS 3.1.1 Shutdown Margin (SDM)

The shutdown margin SHALL be greater than or equal to 1.3% A u k .

TS 3.1.3 Moderator TemDerature Coefficient (MTC)

The MTC upper limit SHALL be 0.0 Ak/k/"F at hot zero power The MTC lower limit SHALL be 2 -36.5 pcm/F @ 300 ppm

-> -43.0 pcm/F @ 60 ppm

-> -45.5 pcrn/F @ 0 ppm Reference Graph RV-12 for cycle specific predicted MTC.

TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn when the reactor is in MODE 1 and MODE 2. Shutdown Banks with a group step counter demand position 2 221 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.

Indian Point Unit 2 Cycle 18 COLR Page 4 of 11 TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE 1 and MODE 2 with kefi 2 1.O are as indicated in Figure 2. Control Bank Insertion Limits iapply to the step counter demand position.

TS 3.2.1 Heat Flux Hot Channel Factor (Fa(Z))

NOTE K(Z) is the fraction given in Figure 3 AND Z is the core height location of FQ.

IF P > .5, FQ(Z) 5 (2.50 / P) x K(Z)

IF P I .5, FQ(Z) 5 (5.00 ) x K(Z)

TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor F$-I NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.

~ ~~

F t ~ H 1 . 7 0{ 1 + 0 . 3 ( 1 - P ) }

TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)

Methodoloav)

The Indicated limit is the Target Band; i.e., the Target k 5%

The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 4, as required by TS 3.2.3.

Indian Point Unit 2 Cycle 18 COLR Page 9 of 11 Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 100 Step Overlap (Page 1 of 1)

LL" 200 175 150 z 125 0

I-v) 0 n 100 Y

z ma 75 50 25 0

0 10 20 30 40 50 60 70 80 90 100 Power Level (Percent of Rated Power)

LOSS OF ALL AC POWER

+ * . * . * . e . * . . * * * * . . .

• 4 * . t ~ * * * * * * * . . . . 4 * . .

t

+

CAUTION e The l o a d on t h e d i e s e l g e n e r a t o r s should remain l e s s t h a n 1650 KW b u t may be i n c r e a s e d t o 2000 KW f o r a maximum o f 2 hrs i n any 24 hr p e r i o d .

e.. * . . * . . * . .

• 2 e * . e . . * *

• e t e * .

• e . . *

• e e e e . *

5. T r y To Restore Power t o Any 480V Bus:

a . E n e r g i z e 480V bus w i t h d i e s e l generator:

1) Check d i e s e l g e n e r a t o r ( s 1 - 1) Emergency s t a r t d i e s e l RUNNING generatort s 1:

a ) Manually a c t u a t e SI.

2 ) V e r i f y 480V bus - 2 ) M a n u a l l y e n e r g i z e 480V bus AUTOMAT1CALLY EN ERG1 ZED from r u n n i n g d j e s e l generator.

T h i s Step continued on the next page.

4 of 28

C?"C&i5,,

LOSS OF A L L AC POWER e n e r g i z e d from the following:

a ) L o c a l l y t r i p ru diesel g e n e r a t o b ) C o n t a c t Con Ed DO determi ne i f 1 3 8 K 1 3 . 8 K V power r e a d available.

c) o u t s i d e power readily availabl perform t h e f o l l 1 . D i s p a t c h #PO start a GT p o 2-SOP-27.5.3.

START OF GAS T U R B I N E 1, 2.

2. Go t o S t e p 6 . 0 CAUTIONS PRIOR STEP 6 .

d) fi o u t s i d e power i s readily available.

attempt t o manually e n e r g i z e 480V bus the following:

o 2-AOP-138KV-1. L POWER TO 6.9KV B AMD/OR 6 .

o 2-AOP-480V-1, LOSS OF 480V BUS.

This Step continued on the next page.

5 o f 2%

Qcresk,, fc, Number :

Title:

Revision Number :

LOSS OF A L L AC POWER REV. 1 I

R E S P O N S E NO

b. Check 480V busses - AT LEAST b. Go t o Step 6. OBSERVE ONE E N E R G I Z E D : CAUTIONS P R I O R TO STEP 6 .

o 2A AND 3A

- OR -

o 5A

- OR -

o 6A c . S t a r t one service water pump on the essential header t o s u p p o r t running diesel generator d . Return t o procedure and step i n e f f e c t and implement F R P s b

Q d t S L b A LOSS OF A L L AC POWER CAUTION o When power i s restored t o any 480V bus, recovery a c t i o n s shou continue s t a r t i n g with Step 24.

o I f a n SI signal e x i s t s or i f a n SI signal i s actuated during t procedure, i t should be r e s e t ( r e f e r t o Step 18b) t o permit ma loading o f equipment on a 480V bus.

o I f a d i e s e l generator i s s t a r t e d , a s e r v i c e water pump should

• s t a r t e d on the e s s e n t i a l header t o provide d i e s e l generator co

• o I f a p a r t i a l t r a i n ( b u s 2 A or bus 3Al i s energized, safeguards equipment on the energized bus including RCP seal cooling shou placed in PULLOUT or i s o l a t e d .

6. Place Followinq EauiDment Switches I n PULLOUT P o s i t i o n :

o containment spray pumps o S I pumps o FCUs o Motor-driven AFW pumps o Turning gear o i l pump o Bearing o i l pump o Turbine a u x i l i a r y o i l pomp o CCW pumps o RHR pumps

LOSS O F ALL AC POWER RESPONSE NOT OBTA

• . . . * ~ * *

• C

• t * *

• t + * + t ~ * * *

• e * * * * * * * * * * * * * .

CAUTI OY R a d i a t i o n l e v e l s and harsh environment conditions should be evaluated

+ p r i o r t o performing l o c a l a c t i o n s .

• * . * ~ . * ~ * * ~ ~ + * * * ~ + * * * * * * * * * * + * . . ~ +

• 4 * ~ ~

DisDatch Personnel To Locally Restore AC Power:

a . Emergency d i e s e l g e n e r a t o r ( s 1 per:

o 2 - SOP-27.3.1.1. 21 EMERGENCY D I E S E L GENERATOR MANUAL OPERA TI ON o 2-SOP-27.3.1.2. 22 EMERGENCY D I E S E L GENERATOR MANUAL OPERATION o 2-SOP-27.3.1.3, 23 EMERGENCY D I E S E L GENERATOR MANUAL OPERATION This S t e p contihued on the next page.

Q j e s ~ w e LOSS OF ALL AC POWER b . Check 13.8KV f e e d e r 13W92 - b. IF 13.8KV f e e d e r 13W92 EN ERG I ZED be e n e r g i z e d . THEN p e r f o r following:

1) C o n t a c t Con Ed DO determine i f IP3 f e e d e r 13W93 i s a

2) I P 3 13.8KV 13W a v a i l a b l e . THEN a t t e m restore power t o 6.

52GT/BT p e r :

o 2-SOP-ESP-001. LOC E Q U I P M E N T OPERATIO COMPENSATORY ACT1

3) IF 13.8KII feeder 1 NOT a v a i l a b l e 526 can be c l o s e d ,

b l a c k s t a r t a GT p o 2-SOP-27.5.3. BLACK OF GAS TURBINE 1. 2

4) IF a GT can _NOT be s t a r THEN p e r f o r m the foll as r e q u i r e d :

a1 Attempt t o r e s t o r e t o ASSS v i a I P 3 AR o 2-AOI-27.1.9.2, P R O V I D I N G APPEND POWER FROM UNIT b ) C o n t a c t Con Ed DO t imp1 ement 0-4087.

PROCEDURE FOR RESTORATION O f ELECTRICAL SUPPLY TO I N D I A N POINT 2 AND 3.

5) C o n t i n u e w i t h S t e p 8. WHEN power s o u r c e i s a v a i l a b l e ,

THEN d o S t e p 7c.

T h i s Step continued on the next page.

9 o f 28

LOSS OF ALL AC POWER

c. Attempt to restore power to busses per the following while continuing with Step 8:

0 2-SOP-27.1.3. OPERATION OF 1 3 . 8 K V SYSTEH o 2-SOP-27.1.4, 6900 VOLT SYSTEM.

0 2 - A O P - 1 3 8 K V - 1 . LOSS OF POWER TO 6 . 9 K V BUS 5 AND/OR 6.

0 2-AOP-13.8KV-1. LOSS OF POWER TO ANY 1 3 . 8 K V BUS o 2-AOP-480V-1. LOSS OF 480V BUS.

8. Di sDatch Personnel' To Local 1 Y Close Valves To Isolate RCP Seals_

And Place Valve Switches In CLOSED Position; o RCP seal return isolation valve outside containment:

o MOV-222 o RCP seal injection isolation valves outside containment:

o MOV-250A o MOV-2500 o MOV-250C o MOV-2500 o RCP thermal barrier CCW return isolation vaJve outside containment:

o MOV-789 10 o f 28

STEP DESCRIPTIOP TABLE FOR ECA-0.0 STEP 6 STEP: P l a c e Following Equipment S w i t c h e s I n PULLOUT P o s i t i o n :

PURPOSE: To d e f e a t a u t o m a t i c l o a d i n g o f l a r g e l o a d s on t h e a c 480V b u s If a c power c a n n o t b e r e s t o r e d from t h e c o n t r o l room. it i s necessary t o d i s p a t c h p e r s o n n e l t o l o c a l l y r e s t o r e a c power. The l o n g e r t h e d u r a t i o n of t h e a c p o w e r o u t a g e , t h e more l i k e l y a p l a n t c o n d i t i o n may d e v e l o p w h e r e i n a u t o m a t i c s t a r t of equipment upon a c power r e s t o r a t i o n may have d e t r i m e n t a l a f f e c t s on t h e r e s t o r e d a c 480V b u s . t h e a u t o m a t i c a l l y s t a r t e d e q u i p m e n t o r o t h e r p l a n t e q u i p m e n t . s u c h a s t h e RCP s e a l s .

Consequently. t h i s s t e p i n s t r u c t s t h e o p e r a t o r t o defeat automatic loading of a l l l a r g e loads p r i o r t o d i s p a t c h i n g personnel t o l o c a l l y r e s t o r e a c p o w e r - Automatic l o a d i n g i s d e f e a t e d by p l a c i n g t h e equipment switches i n t h e pullout position.

D e f e a t i n g a u t o m a t i c b l a c k o u t o r S I l o a d i n g o f a s many l a r g e l o a d s a s p r a c t i c a l i s i n t e n d e d t o a v o i d p o t e n t i a l o v e r l o a d of t h e e n e r g i z e d a c 480V b u s . T h i s a c t i o n p e r m i t s The o p e r a t o r t o e v a l u a t e t h e s t a t u s of t h e r e s t o r e d a c 480V b u s and s e q u e n c e l o a d s o n t o t h e bus c o n s i s t e n t w i t h b u s s t a t u s and p l a n r c o n d i t i o n s . A s e r v i c e w a t e r pump i s l o a d e d on t h e a c 4 8 0 v b u s t o 3 r o v i d e d i e s e l c o o l i n g s h o u l d t h e d i e s e l have s t a r t e d .

D e f e a t i n g a u t o m a t i c l o a d i n g of o t h e r m a j o r equipment i n t h i s s t e p a l s o f u n c t i o n s t o p r o t e c t t h e RCP from damage when power i s r e s t o r e d . T h i s p e r m i t s t h e o p e r a t o r t o v e r i f y v a l v e a l i g n m e n t s p r i o r t o s t a r t i n g pumps.

A n o t h e r r e l a t e d c o n s i d e r a t i o n which s h o u l d be e v a l u a t e d i s t h e p o t e n t i a l ambient t e m p e r a t u r e i n t h e pump a r e a s . If t h e r e a r e any h i g h e n e r g y l i n e s i n t h e v i c i n i t y of a pump, s u c h a s a s t e a m l i n e i n t h e v i c i n i t y of t h e m o t o r - d r i v e n AFW pumps, t h e p o t e n t i a l e x i s t s t h a t t h e ambient t e m p e r a t u r e i n c r e a s e d u r i n g t h e ac power o u t a g e may exceed l i m i t a t i o n s f o r pump o p e r a t i o n . If s u c h a c o n c e r n e x i s t s , t h e sequence f o r manually l o a d i n g t h e s e components on t h e e n e r g i z e d b u s can b e m o d i f i e d t o e s t a b l i s h a m b i e n t c o o l i n g p r i o r t o s t a r t i n g t h e pump.

ACT1ONS :

Place following switches i n p u l l o u t :

Containment s p r a y pumps S I pumps FCUs M o t o r - d r i v e n AFW pumps CCW pumps RHR pumps Turning g e a r o i l pump B e a r i n g o i l pump ECA-0.0 83 Rev.

STEP DESCRIPTION TABLE FOR ECA-0.0 STEP 6 o T u r b i n e a u x i l i a r y o i l pump INSTRUMENTATION :

S w i t c h p o s i t i o n i n d i c a t i o n for:

C o n t a i n m e n t s p r a y pumps S I pumps FCUs M o t o r - d r i v e n AFW pumps CCW pumps RHR pumps T u r n i n g g e a r o i l pump B e a r i n g o i l pump T u r b i n e a u x i l i a r y o i l pump CONTROLIEQUIPMENT:

S w i t c h e s for:

C o n t a i n m e n t s p r a y pumps S I pumps FCUs M o t o r - d r i v e n AFW pumps 4

CCW pumps RHR pumps T u r n i n g g e a r o i l pump B e a r i n g o i l pump T u r b i n e a u x i l i a r y o i l pump KNOWLEDGE :

N/A ECA-0 . 0 84 Rev.

IP2 FSAR IlJPDATE 6.1.1.7 Sharina of Svstems Criterion: Reactor facilities may share systems or components if it can be shown that such sharing will not result in undue risk to the health and safety of the public. (GDC 4)

The engineered safety features at Indian Point 2 do not share systems or components with other units.

6.1.2 Related Criteria The following are criteria, which although related to all engineered safety features, are more specific to other plant features or systems, and, therefore, are discussed in other chapters, as listed.

Name Discussion Quality Standards (GDC 1) Chapter 4 Performance Standards (GDC 2) Chapter 4 Records Requirements (GDC 5) Chapter 4 Instrumentation and Control Systems (GDC 12) Chapter 7 Engineered Safety Features Protection Systems (GDC 15) Chapter 7 Emergency Power (GDC 39) Chapter 8 REFERENCES FOR SECTION 6.1

1. NRC Letter dated May 20, 1999, Jeffrey F. Harold to A. Alan Blind,

Subject:

Safety Evaluation of Generic Letter 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," for Indian Point Nuclear Generating Unit No.2 (TAC M93473).

6.2 SAFETY INJECTION SYSTEM At Indian Point Unit 2 the emergency core cooling function is performed by the safety injection system. Therefore, whenever the term "emergency core cooling system" or ECCS is referenced in the document it is synonymous with the safety injection system.

6.2.1 Desian Basis 6.2.1.I Emeraencv Core Coolinq Svstem CaDabilitv Criterion: An emergency core cooling system with the capability for accomplishing adequate emergency core cooling shall be provided. This core cooling system and the core shall be designed to prevent fuel and clad damage that would interfere with the emergency core cooling function and to limit the clad metal-water reaction to acceptable amounts for all sizes of breaks in the reactor coolant Chapter 6, Page 6 of 170 Revision 20