Latest revision as of 05:54, 13 March 2020

Text

Feb Exam 05000327/2008301, & 05000328/2008301 Final Simulator JPMs
	ML080720575
Person / Time
Site:	Sequoyah
Issue date:	01/31/2008
From:	; - No Known Affiliation
To:	; NRC/RGN-II
References
	JPM 57AP2, Rev 3 IR-08-301
	Download: ML080720575 (411)
	v • d • e

{{#Wiki_filter:, .' .... :...

                                           ~ (;~.!;(i ";:,:,;.:/,.: .....,."'.'- ,.;.'.' *.*.;::;:S?;{;:)/:/X~~~i9t;;~);-i:.~~
              .*':,,*'.:,,*,t . ,.... ".:.,;..:. '.,:",;..
                                                                                                                     "/"

JPM 57AP2 Page 1 of 10 Rev 3 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 8.1.a JPM 57-AP2 Respond to High Containment Pressure, Place RHR Spray in Service PREPAREDI REVISE'D BY: Date/ VALIDATED BY:

Datel APPROVED BY: Datel (Operations Training Manager)

CONCURRED: ** Date/ (Operations Representative)

Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual ste.p changes that do not affect the flow of the JPM.

               ** Operations Concurrence re*quired for new JPMs and changes that affect the flow of the JPM(if not driven by a procedure revision).

JPM 57AP2 Page 2 of 10 Rev 3 I NUCLEAR TRAINING REVISION/USAGE LOG Revision Description Pages Prepared/ Number Of Revision V Date Affected Revised By: 0 Initial issue Y 12/3/01 All L. Pauley Used in 2000 NRC initial exam as 57AP 1 Revised to latest revision of FR-Z.1 N 8/20/02 4 J P Kearney 2 Made back into simulator JPM (was set up to be run in Y 8/4/05 All MG Croteau actual MCR). Set up for current IC and procedure revision. Updated references, wrote and referenced SCENS file N 10/20105 3,4 JJ Tricoglou 3 Reworded turnover information, referenced FR-Z.1 rev 4,10 17, revised instructions, added handout sheet, modified standards wording. v- Specify if the JPM change will require another validation (Y or N). See cover sheet for criteria. -

JPM 57AP2 Page 3 of 10 Rev 3 SEQUOYAH NUCLEAR PLANT ROISRO JOB PERFORMANCE MEASURE Task: Respond to High Containment Pressure, Place RHR Spray in Service Note: This JPM satisfies Simulator Manipulation "IN13". JAITA task # : 3110160601 (RO) KIA Ratings: 022000 A3.01 (4.1 - 4.4) 022000 A4.04 (3.1 -3.20 026000 GA13 (3.6 - 3.6) 026000 GAg (3.6 - 3.6) Task Standard: Attempt to establish one train of RHR spray in service per FR-Z.1. Evaluation Method: Simulator __ X_ _ In-Plant .:..-

====="==================================================================

Performer: NAME Start Time _ Performance Rating: SAT UNSAT Performance Time Finish Time _ Evaluator: SIGNATURE DATE

=======================================================================

COMMENTS

JPM 57AP2 Page 4 of 10 Rev 3 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Sequenced steps identified by an "s"

2. Any UNSAT requires comments

3. Initialize simulator in IC#176. If Ie 176 is not available the reset to IC #24 and complete substeps below.

a. Activate MF # TH01A at 350/0.

b. Activate MFs # CH01 A thru D at 70%(-10.2 psid)

c. Complete the actions of ES-1.3, Sump Swapover. Stop RCPs.

d. Activate Override ZDIHS6393A OPEN, to prevent FCV-63-93 from closing.

e. Activate Override ZDIHS7241A CLOSE*, to prevent FCV-72-41 from opening.

4. Activate the following, as necessary, to prevent nuisance alarms:

AN:OVRN[96] to OFF, prevents Turbine Zero Speed alarm

   * *AN:OVRN[214] to OFF, prevents Saturation Monitor alarm

AN:OVRN[304] to OFF, prevents MFP Lo NPSH
AN:OVRN[2155] to OFF, prevents SG Pressure Lo

5. Insert Remote Function RHR14 ON, places power on FCV-63-1.

6. FREEZE the simulator until the operator is ready to commence task.

7. Console operator will need to acknowledge alarms* not associated with JPM.

8. Ensure operator performs the following required actions for SELF-CHECKING;

a. Identifies the correct unit, train, component, etc.

b. Reviews the intended action and expected response.

c. Compares the actual response to the expected response.

Validation Time: CR. 8 mins Local - - - - - Tools/Equipment/Procedures Needed: FR-Z.1, step 13

References:

Reference Title Rev No. FR-Z.1 Hi h Containment Pressure 17

===========,===============================================================================

READ TO OPERATOR Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. Unit 1 has experienced a reactor trip and Safety Injection in conjunction with a large break LOCA.

2. The crew has been monitoring step 13 of FR-Z.1 since FR-Z.1 was implemented.

3. 1 hour has elapsed since the accident.

INITIATING CUES:

1. The US directs you to perform FR-Z.1, Step 13 to initiate one train of RHR spray.

2. Inform the US when Step 13 has been completed.

JPM 57AP2 Page 5 of 10 Rev 3 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 1.: Obtain copy of appropriate procedure. - SAT Cue: After operator locates FR-Z.1 procedure, provide a copy of - UNSAT FR-Z.1 marked up as appropriate. Start Time- - STANDARD: Operator obtains a copy of FR-Z.1 (begin at Step 13). COMMENTS: STEP 2.: [FR-Z.1, Step 13] MONITOR if RHR Spray should be placed in - SAT service.

                                                                                     -    UNSAT CHECK Containment press greater than 9.5 psid.

STANDARD: Operator checks PDIS-30-42 through 45 and determines that pressure is greater than 9.5. COMMENTS: STEP 3.: CHECK at least 1 hour has elapsed since beginning of accident. - SAT Cue: IF asked, 1 hour has elapsed since beginning of accident. - UNSAT STANDARD: Operator determines from initiating cues (or asks US) that 1 hour has elapsed. COMMENTS: STEP 4.: CHECK RHR suction ALIGNED to containment sump. - SAT Cue: If asked, ES-1.3 has been completed. - UNSAT STANDARD: Operator check FCV-63-72 and 73 open AND FCV-74-3 and 21 closed. OR asks US if ES-1.3 "Transfer to RHR Containment Sump" has been completed. COMMENTS:

JPM 57AP2 Page 6 of 10 Rev 3 Job Performance Checklist STEP/STAN DARD SAT/UNSAT STEP 5.: CHECK at least one CCP AND one SI pump RUNNING. - SAT STANDARD: Operator ensures at least one CCP is running as indicated by red - UNSAT light on 1-HS-62-1 04A or 1-HS-62-1 08A LIT. AND Ensures at least one SI pump is running as indicated by red lights on 1-HS-63-1 OA or 1-HS-63-15A "LIT". COMMENTS: STEP 6.: [13.b]CHECK both RHR pumps RUNNING. - SAT STANDARD: Operator checks that both RHR pumps are running as indicated by red - UNSAT lights on 1-HS-74~10Aand 1-HS-20A "LIT". COMMENTS: STEP 7.: [13.c] ESTABLISH Train B RHR spray: - SAT

1. CHECK Train B RHR pump RUNNING.

                                                                                          -   UNSAT STANDARD: Operator checks that 1B-B RHR pump is running as indicated by red light on 1-HS-74-20A "LIT".

COMMENTS: STEP 8.: [13.c.2)] ENSURE RHR crosstie FCV-74-35 CLOSED. - SAT STAN'DARD: Operator verifies FCV-74-35 in the CLOSE position as indicated by - UNSAT 1-HS-74-35A green light ON and red light off. COMMENT.S: STEP 9.: [13.c.3)] CLOSE RHR Injection FGV-63-94. - SAT

                                                                                            -  UNSAT STANDARD: Operator places handswitch 1-HS-63-94A for RHR injection FCV-63-94 in the CLOSE position.                                           Critical Step COMMENTS:

JPM 57AP2 Page 7 of 10 Rev 3 Job Performance Checklist STEP/STANDARD SAT/UNSAT NOTE: This is the alternate path. - SAT STEP 10.: [13.c.4)] OPEN RHR Spray FCV-72-41. - UNSAT NOTE: FCV-72-41 will NOT open the operator must go to the RNO and align the A train RHR spray. STANDARD: Operator places handswitch1-HS-72-41A for RHR injection FCV 41 in the OPEN position and recognizes that the green light stays ON and the red light is OFF, goes to RNO column. COMMENTS: NOTE: The following steps are from FR-Z.1, step 13.c RNO - SAT STEP 11.: [13.c RNO a)] ENSURE RHR Spray FCV-72-41 CLOSED. - UNSAT STANDARD: Operator verifies FCV-72-41 is closed as indicated by green light ON and red light OFF on 1-HS-72-41A. COMMENTS: STEP 12.: [13.c RNO b)] IF RHR aligned for cold leg recirculation, THEN - SAT ENSURE FCV-63-94 OPEN.

                                                                                     -   UNSAT STANDARD: Operator places handswitch 1-HS-63-94A for RHR injection FCV-63-94 in the OPEN position.                                       Critical Step COMMENTS:

STEP 13.: [13.c RNO c)] ESTABLISH Train A RHR spray: - SAT (1) ENSURE RHR crosstie FCV-74~33 CLOSED.

                                                                                      -   UNSAT STANDARD: Operator verifies RHR crosstie FCV-74-33 in the CLOSE position as indicated by green light LIT on handswitch 1-HS-74-33A.

COMMENTS:

JPM 57AP2 Page 8 of 10 Rev 3 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 14.: [13.c RNO c)(2)] CLOSE RHR Injection FCV-63-93. - SAT

                                                                                    -    UNSAT STANDARD: Operator places handswitch 1-HS-63-93A for RHR injection FCV-63-93 in the CLOSE position.

Critical COMMENTS: Step STEP 15.: OPEN RHR spray FCV-72-40. - SAT STANDARD: Operator places handswitch 1-HS-72-40A for FCV-72-40 in the - UNSAT OPEN position. Critical Step COMMENTS: STEP 16.: [13.d] MONITOR containment pressure greaterthan 4 psig. - SAT

                                                                                     -    UNSAT STANDARD:       Operator checks PDIS-30-42 through 45 and determines that pressure is greater 4 psig and continues to the next step.

This completes Step 13 and the JPM COMMENTS: STEP 17.: Communicates with SRO and informs him RHR spray status. - SAT

                                                                                      -   UNSAT STANDARD: Operator informs SRO that the Train A RHR spray has been placed in service in accordance with FR-Z.1 and that FCV-72-41 failed to open.

Stop Time__ COMMENTS: END OF JPM

ECCS Simplified Drawing v r*-***:::~----l C T

                                                                                                                                                                               ...........[.. _...._.
                .                           *............................................................_     ~          _.-             -           _.-     _.-..---  -                 l
                                      **    L **
                                                   ._11 r

LCV. r-I LCV ~ LCV 62-132~ 62-135 . . LJ ~ 62.136 LCV~ ..----1-*----* 62-133

                                                                                                                                              £ :

FCV:

                                                                                                                                                                                           *------------1 L--         ~ ~_ _~            Charging

74-12:

                                                                                                                                                          ..                               *I I

I I I

RHR

I FCV~ 11
I 63-1 ~

I

I :

j

                                                                                                         "------i Hot Legs
                                                                                  ~,   Loops

- - --~.FCV Hot Legs Cold Legs Hot Legs : 1&3

     ~63-6
                   *.Loops
                   ~1 &3';""

FCV 63-156

                                       .I1
                    ........... 1'---1r~---1'

[j63_22 FCV Loops

                                                                  ~~.~~.1', ~~.

Fev 63-172 FCV i FCV

                                   . .~~. r~_ .                                                                                 :i £

i

_i FCV-74-24

                                            ~FCV_63-5
                                            +-~        . _-- - _._- - _.__._- - - - _. _-_._. _-_.__. _-- . _ ._._.------------.;,-----------------------------------------_._--------_._-----~--_ . -

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO T*RAINEE: I will explain the initial conditions, a.nd state the task to be performed. All control room steps shall be performed for this .JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have com*pleted your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. Unit 1 has experienced a reactor trip and Safety Injection in conjunction with a large break LOCA.

2. The crew has been monitoring step 13 of FR-Z.1 since FR-Z.1 was implemented.

3. 1 hour has elapsed since the accident.

INITIATING CUES:

1. The US directs you to performFR-Z.1, Step 13 to initiate one train of RHR spray.

2. Inform the US when Step 13 has been completed.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL FUNCTION RESTORATION PROCEDURE FR-Z.1 HIGH CONTAINMENT PRESSURE Revision 17 QUALITY RELATED PREPARED/PROOFREAD BY: -- D. - A. - PORTER RESPONSIBLE ORGANIZATION: -OPERATIONS APPROVED BY:

            - - -w.  -T.-LEARY EFFECTIVE DATE: 05/31/07 REVISION DESCRIPTION:  Updated ES-1.3 step number reference in Step 5.c RNO.

This procedure contains a Handout Page (2 copies).

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 HANDOUT Page 1 of 1 STEP I ACTION

1. MONITOR RWST level greater than 27%.

4.d (if any S/G is faulted and air return fans are NOT running) RNO WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment air return fans running.

6. MONITOR containment air return fans:

WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment air return fans running.

10. IF all S/Gs Faulted, RNO. THEN CONTROL feed flow at greater than or equal to 25 gpm to each S/G.

12. MONITOR if hydrogen igniters and recombiners should be turned on:

12.a WHEN hydrogen analyzers have been in ANALYZE for at least 5 minutes, RNO THEN CHECK if hydrogen igniters and recombiners are required. 12.d WHEN ice condenser AHU breakers are open, THEN ENERGIZE hydrogen igniters (if hydrogen concentration less than 6%).

13. MONITOR if RHR spray should be placed in service:

Containment pressure greater than 9.5 psig AND at least 1 hour has elapsed since beginni~g of accident AND RHR suction ALIGNED to containment sump AND at least one CCP AND one SI pump RUNNING.

13.d. (if RHR spray in service) RNO WHEN Containment pressure is less than 4 psig, THEN REMOVE RHR spray from service.

14. MONITOR if containment spray should be stopped:

(containment pressure less than 2.0 psig) 14.c (if containment spray suction aligned to sump) RNO WHEN directed by TSC, THEN STOP containment spray. 1a of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 HANDOUT Page 1 of 1 STEP i ACTION

1. MONITOR RWST level greater than 27%.

4.d (if any S/G is faulted and air return fans are NOT running) RNO WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment air return fans running.

6. MONITOR containment air return fans:

WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment air return fans running.

10. IF all S/Gs Faulted, RNO. THEN CONTROL feed flow at greater than or equal to 25 gpm to each S/G.

12. MONITOR if hydrogen igniters and recombiners should be turned on:

12.a WHEN hydrogen analyzers have been in ANALYZE for at least 5 minutes, RNO THEN CHECK if hydrogen igniters and recombiners are required. 12.d WHEN ice condenser AHU breakers are open, THEN ENERGIZE hydrogen igniters (if hydrogen concentration less than 6%).

13. MONITOR if RHR spray should be placed in service:

Containment pressure greater than 9.5 psig AND at least 1 hour has elapsed since beginning of accident AND RHR suction ALIGNED to containment sump AND at least one CCP AND one SI pump RUNNING.

13.d. (if RHR spray in service) RNO WHEN Containment pressure is less than 4 psig, THEN REMOVE RHR spray from service.

14. MONITOR if containment spray should be stopped:

(containment pressure less than 2.0 psig) 14.c (if containment spray suction aligned to sump) RNO WHEN directed by TSC, THEN STOP containment spray. 1b of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 1.0 PURPOSE This procedure provides actions to respond to a high containment pressure. 2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 ENTRY CONDITIONS FR-O Status Trees:

F-O.5, Containment RED condition:

Containment pressure greater than or equal to 12.0 psig.

F-O.5, Containment ORANGE condition:

Containment pressure less than 12.0 psig AND Containment pressure greater than or equal to 2.8 psig. 3.0 OPERATOR ACTIONS Page 2 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED NOTE If this procedure has been entered for an orange path and performance of ECA-1.1 (Loss of RHR Sump Recirculation) is required, FR-Z.1 may be performed concurrently with ECA-1.1.

1. MONITOR RWST level IF ES-1.3 has NOT been entered, greater than 27%. THEN GO TO ES-1.3, Transfer to RHR Containment Sump.

2. VERIFY Phase B valves CLOSED: IF 1-FCV-32-110 (2-FCV-32-111) &

is NOT closed, Panel 6K PHASE B GREEN THEN PERFORM EA-32-3, Isolating Panel 6L PHASE B GREEN. Non-Essential Air to Containment. IF other valves NOT closed AND flow path is NOT necessary, THEN CLOSE valves.

3. ENSURE RCPs STOPPED.

Page 3 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

4. DETERMINE if this procedure should be exited:

a. CHECK for faulted S/G: a. GO TO Step 5.

Any S/G pressure DROPPING in an uncontrolled manner OR

            . Any S/G pressure less than 140 psig.

b. CHECK containment pressure b. GO TO Step 5.

=--

less than 12 psig.

c. IF containment pressure is

c. CHECK at least one containment greater than 2.8 psig, spray pump RUNNING and THEN delivering flow. GO TO Step 5.

d. WHEN 10 minutes have elapsed

d. CHECK at least one containment from Phase B actuation, air return fan RUNNING. THEN ENSURE air return fans RUNNING.

e. RETURN to procedure and step in effect.

Page 4 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

5. VERIFY containment spray operation:

a. CHECK RHR sump recirculation a. IF ECA-1.1 , Loss of RHR Sump capability AVAILABLE. Recirculation, is IN EFFECT, THEN PERFORM the following:

1) OPERATE containment spray as directed by ECA-1.1.

2) GO TO Step 6.

b. VERIFY containment spray pumps b. IF containment pressure is RUNNING. greater than 2.8 psig, THEN START containment spray pumps.

c. CHECK RWST level c. IF any of following conditions met:

greater than 27%.

RWST level less than or equal to 8%

OR

containment sump level greater than 560/0, THEN PERFORM the following:

1) ENSURE cntmt spray pump suction aligned for sump recirc USING ES-1.3, Transfer to RHR Containment Sump, Step 21.

2) GO TO Substep 5.e.

(step continued on next page) Page 5 of 16

SQN FR-Z.1 HIGH CONTAINMENT PRESSURE Rev. 17 . ISTEP I I ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

5. d. VERIFY containment spray suction d. ALIGN valves as necessary.

ALIGNED to RWST:

FCV-72-22 OPEN
FCV-72-21 OPEN.

e. VERIFY containment spray discharge e. OPEN valves for running valves OPEN: containment spray pumps.

FCV-72-39
FCV-72-2.

f. VERIFY containment spray recirc f. CLOSE valves as necessary.

valves CLOSED:

FCV-72-34
FCV-72-13.

g. VERIFY containment spray flow g. IF NO train of containment spray greater than 4750 gpm is available, on each train. THEN PERFORM the following:

1) CONTINUE efforts to restore at least one train of containment spray.

2) NOTIFY TSC to evaluate restoring normal containment cooling USING EA-30-4, Restoring Containment Coolers.

Page 6 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 I STEP I I ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

6. MONITOR containment air return fans:

WHEN at least 10 minutes have elapsed from Phase B, THEN ENSURE containment air return fans RUNNING.

7. VERIFY containment ventilation dampers CLOSE dampers.

CLOSED: Panel 6K CNTMT VENT GREEN Panel6L CNTMT VENT GREEN.

8. VERIFY Phase A valves CLOSED: IF flow path NOT necessary, THEN Panel 6K PHASE A GREEN CLOSE valves.

Panel6L PHASE A GREEN.

9. VERIFY MSIVs and MSIV bypass valves CLOSE valves.

CLOSED. IF any MSIV CANNOT be closed, THEN CLOSE MSIV locally USING EA-1-1, Closing MSIVs Locally. Page 7 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 I STEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

10. DETERMINE if any S/G Intact: IF all S/Gs Faulted, THEN

a. CHECK at least one S/G pressure: PERFORM the following:

CONTROLLED or RISING 1) CONTROL feed flow at greater than or equal to 25 gpm to each S/G.

AND

2) OPEN MD AFW pump recirc valves

Greater than 140 psig. FCV-3-400 and -401 as necessary.

3) GO TO Step 12.

CAUTION Isolating all S/Gs will result in a loss of secondary heat sink.

11. DETERMINE if any S/G Faulted:

a. CHECK S/G pressures: a. GO TO Step 12.

Any S/G pressure DROPPING in an uncontrolled manner OR
Any S/G pressure less than 140 psig.

b. ISOLATE feed flow to affected S/G:

MFW

AFW Page 8 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

12. MONITOR if hydrogen igniters and recombiners should be turned on:

a. DISPATCH personnel to open ice condenser AHU breakers USING EA-201-1, 480 V Board Room Breaker Alignments.

b. CHECK hydrogen concentration b. PERFORM the following:

measurement AVAILABLE:

1) DISPATCH operator to place

Hydrogen analyzers hydrogen analyzers in service have been in ANALYZE USING Appendix D. (also for at least 5 minutes. contained in ES-0.5)

2) WHEN hydrogen analyzers have been in ANALYZE for at least 5 minutes, THEN PERFORM substeps 12.c through 12.e.

3) GO TO Step 13.

c. CHECK containment hydrogen concentration less than 6%.

c. CONSULT TSC.

GO TO Step 13.

                                                                                  =---

d. WHEN ice condenser AHU breakers have been opened, THEN

                                                                               =---

ENERGIZE hydrogen igniters USING Appendix D, Placing Hydrogen Analyzers and Igniters In Service. (Step continued on next page.) Page 9 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 I STEP I I ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

12. e. CHECK containment hydrogen e. PLACE hydrogen recombiners in concentration less than 0.5%. service USING EA-268-1, Placing Hydrogen Recombiners in Service.

IF hydrogen recombiners NOT available, THEN CONSULT TSC.

13. MONITOR if RHR spray should be placed in service:

a. CHECK the following: a. GO TO Step 14.

Containment pressure greater than 9.5 psig AND At least 1 hour has elapsed since beginning of accident AND RHR suction ALIGNED to containment sump AND At least one CCP AND one SI pump RUNNING. (Step continued on next page.)' Page 10 of 16

SQN FR-Z.1 HIGH CONTAINMENT PRESSURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

13. b. CHECK both RHR pumps RUNNING. b. IF only one RHR pump running, THEN PERFORM the following:

1) ENSURE only one CCP RUNNING (same train as running RHR pump preferred).

2) PLACE non-operating CCP in PULL TO LOCK.

3) ENSURE only one SI pump RUNNING (same train as running RHR pump preferred).

4) PLACE non-operating SI pump in PULL TO LOCK.

(Step continued on next page.) Page 11 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

13. c. ESTABLISH Train B RHR spray: c. IF Train B RHR spray CANNOT be established,

1) CHECK Train B RHR pump THEN RUNNING. PERFORM the following:

2) ENSURE RHR crosstie a) ENSURE RHR spray FCV-72-41 FCV-74-35 CLOSED. CLOSED.

3) CLOSE RHR injection b) IF RHR aligned for cold leg FCV-63-94. recirculation, THEN

4) OPEN RHR spray FCV-72-41. ENSURE FCV-63-94 OPEN.

c) ESTABLISH Train A RHR spray: (1) ENSURE RHR crosstie FCV-74-33 CLOSED. (2) CLOSE RHR injection FCV-63-93. (3) OPEN RHR spray FCV-72-40. IF Train A RHR spray. CANNOT be established, THEN PERFORM the following: a) CLOSE RHR spray FCV-72-40. b) IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 OPEN. (Step continued on next page.) Page 12 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

13. d. MONITOR containment pressure d. WHEN containment pressure is greater than 4 psig. less than 4 psig, THEN PERFORM the following:

1) ENSURE FCV-72-40 and FCV-72-41 CLOSED.

2) IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 and FCV-63-94 OPEN.

3) IF ECCS is aligned for hot leg recirculation, THEN ENSURE RHR crosstie valves FCV-74-33 and FCV-74-35 aligned as required by ES-1 .4.

Page 13 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

14. MONITOR if containment spray should be stopped:

a. CHECK any containment spray pump a. GO TO Step 15.

RUNNING.

b. CHECK containment pressure b. GO TO Step 15.

less than 2.0 psig.

c. CHECK containment spray suction c. NOTIFY TSC to determine aligned to RWST. when one or both trains of cntmt spray should be stopped.

WHEN directed by TSC, THEN PERFORM Substeps 14.d through 14.f. GO TO Step 15.

d. RESET Containment Spray.

e. STOP containment spray pumps and PLACE in A-AUTO.

f. CLOSE containment spray discharge valves:

FCV-72-39, Train A
FCV-72-2, Train B.

Page 14 of 16

SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

15. RETURN TO procedure and step in effect.

END Page 15 of 16

FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 17 Page 1 of 1 APPENDIX D PLACING HYDROGEN ANALYZERS AND IGNITERS IN SERVICE

1. PLACE hydrogen analyzers in service:

a. ENSURE the following switches in ANALYZE position: [M-10]

HS-43-200A, Cntmt H2 Analyzer Fan A D
HS-43-210A, Cntmt H2 Analyzer Fan B. D

b. RECORD time: _ D

c. NOTIFY Unit Supervisor of time that hydrogen analyzers were placed in ANALYZE. D NOTE The following step is performed when directed by an EOP step (after hydrogen concentration has been verified and ice condenser AHU breakers have been opened).

2. WHEN directed to energize hydrogen igniters, THEN ENSURE the following switches in ON position: [M-10]

HS-268-73, H2 Igniters Group A D
HS-268-74, H2 Igniters Group B. D END OF TEXT Page 16 of 16

JPM B.1.b Page 1 of 11 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b JPM Respond to a #1 Rep Seal Failure PREPAREDI REVISED BY: Date/ VALIDATED BY:

Date/

APPROVED BY: Date/ (Operations Training Manager) CONCURRED: ** Date/ (Operations Representative)

Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.

             ** Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM B.1.b Page 2 of 11 Rev. 0 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/ NUMBER REVISION AFFECTED REVISED BY: 0 New, modified from JPM 403 Y All v - Specify if the JPM change will require another validation (Y or N). See cover sheet for criteria.

JPM B.1.b Page 3 of 11 Rev. 0 SEQUOYAH NUCLEAR PLANT ROISRO JOB PERFORMANCE MEASURE Task: Respond to an RCP Seal Failure JAITA task:

       # 0000820501 (RO)

KIA Ratings: 003 Reactor Coolant Pump System A2.01 3.5/3.9 Task Standard:

1) Candidate determines the #1 RCP has a seal malfunction and enters AOP-R.04

2) Candidate trips reactor, removes the #1 RCP from service, and closes the seal return valve from the pump.

Evaluation Method: Simulator __X_ _ In-Plant _

=======================================================================

Performer: NAME Start Time _ Performance Rating: SAT UNSAT Performance Time Finish Time _ Evaluator: -------------_/_-- SIGNATURE DATE

=======================================================================

COMMENTS

JPM B.1.b Page 4 of 11 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Sequenced steps identified by an "s"

2. Any UNSAT requires comments

3. This task is to be performed using the simulator in IC-10, 14% power ready to roll turbine

4. Put MODE 1 sign on simulator

5. When ready to start, insert malfunction CV17A f: 0.60

6. Ensure operator performs the following required actions for SELF-CHECKING;

a. Identifies the correct unit, train, component, etc.

b. Reviews the intended action and expected response.

c. Compares the actual response to the expected response.

Validation Time: CR. 14 min Local - - - - - Tools/Equipment/Procedures Needed: AOP-R.04

References:

Reference Title Rev No.

1. AOP-R.04 Reactor Coolant Pum Malfunctions 22

=================================================================

READ TO OPERATOR Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. Unit 1 is in MODE 1 at 140/0 reactor power preparing to roll the main turbine. Currently awaiting completion of maintenance activities.

INITIATING CUES:

1. You are the OATC and are to monitor the control board and respond to conditions as required.

This JPM contains Time Critical steps

JPM B.1.b Page 5 of 11 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 1.: Obtain the appropriate procedure. SAT UNSAT STANDARD: Operator identifies window B-3, FS-62-11 REAC COOL PMPS SEAL LEAKOFF HIGH FLOW lit and uses 1-AR-M5-B to respond. Start Time__ The following 2 steps are from 1-AR-M5-B Window B-3 STEP 2.: [1] Verify High Leakoff condition on affected RCP(s) with the following SAT instruments UNSAT Pump Leakoff Instrumentation RCP 1 1-FR-62-24 RCP2 1-FR-62-24 RCP3 1-FR-62-50 RCP4 1-FR-62-50 f STANDARD: Candidate determines that #1 RCP has high Seal flow on 1-FR-62-24 or by looking at the ICS. COMMENTS: STEP 3.: [2] GO TO AOP-R.04, Reactor Coolant Pump Malfunctions. SAT UNSAT STANDARD: Candidate enters AOP-R.04 COMMENTS: The following steps are from AOP-R.04 STEP 4.: 1. DIAGNOSE the failure: SAT UNSAT STANDARD: Candidate determines Section 2.2 is the appropriate section and goes to section 2.2 COMMENTS:

JPM B.1.b Page 6 of 11 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 5.: 1. MONITOR #1 sealleakoff less than 6 gpm per pump: - SAT

FR-62-24 [RCP 1 & 2] - UNSAT
FR-62-50 [RCP 3 & 4]

STANDARD: Candidate uses 1-FR-62-24 or by looking at the ICS to determine seal flow on #1 RCP is greater than 6 gpm and goes to the RNO. COMMENTS: STEP 6.: a. MONITOR RCP lower bearing temperature and seal temperature. - SAT IF RCP lower bearing temperature OR seal temperature are rising - UNSAT uncontrolled, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required. [C.1] [C.2] STANDARD: Candidate uses 1-TI-62-3 and 1-TI-62-4 to determine lower bearing temperature and seal temperature are rising and goes to Section 2.1, Reactor Coolant Pump(s) Tripped or Shutdown Required COMMENTS: STEP 7.: 1. CHECK reactor power greater than 10% - SAT

                                                                                           -    UNSAT STANDARD:       Candidate determines reactor power is greater than 100/0 and continues to the next step.

COMMENTS:

JPM B.1.b Page 7 of 11 Rev. 0 Job Performance Checklist STEP/STAN DARD SAT/UNSAT STEP 8.: 2. TRIP the reactor and GO TO E-O, Reactor Trip or Safety Injection, WHILE SAT continuing in this procedure. UNSAT After candidate completes the immediate actions, state that the SRO and another operator will perform E-O. Critical Step STANDARD: Candidate trips the reactor by placing reactor trip switch to the trip position. COMMENTS: STEP 9.: 3. STOP and LOCK OUT affected RCP(s). SAT UNSAT STANDARD: Candidate places handswitch 1-HS-68-8A to the stop position (critical). Critical Step Handswitch placed in the Pull to Lock position (non-critical). Record time pump is stopped _ COMMENTS: STEP 10.: 4. MONITOR RCP sealleakoff less than 8 gpm per pump: SAT

FR-62-24 [RCP 1 & 2] UNSAT
FR-62-50 [RCP 3 & 4]

Evaluator Note: Scale on recorder is 0-10 gpm STANDARD: Candidate determines that #1 RCP sealleakoff flow on 1-FR-62-24 is greater than 8 gpm. COMMENTS:

JPM B.1.b Page 8 of 11 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 11.: WHEN the RCP has coasted down (30 sec.), THEN SAT CLOSE affected RCP seal return FCV: [C.2] UNSAT

FCV-62-9 [RCP 1]
FCV-62-22 [RCP 2] Critical
FCV-62-35 [RCP 3] Step
FCV-62-48 [RCP 4]

STANDARD: Candidate place 1-HS-62-9 to the Close position within 5 minutes of Time stopping the RCP Critical Step Record time FCV is closed _ COMMENTS: STEP 12.: 5. PULL TO DEFEAT affected loop 1\T and T-avg: SAT

XS-68-2D (1\T)
XS-68-2M (T-avg) UNSAT STANDARD: Candidate places 1-XS-68-2D and 1-XS-68 2M to Loop 1 position and pulls each out.

COMMENTS: STEP 13.: 6. CHECK RCPs 1 and 2 RUNNING. SAT UNSAT STANDARD: Candidate determines that #1 Reactor coolant pump is not running. COMMENTS: STEP 14.: 6. RNO CLOSE affected loop's pressurizer spray valve. SAT UNSAT STANDARD: Candidate verifies Loop 1 PZR Spray Valve 1-PIC68-340D is closed. May place the controller to manual. COMMENTS:

JPM B.1.b Page 9 of 11 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 15.: 7. IF RCP Seal Tem peratures or Bearing Tem peratures are increasing SAT uncontrolled due to loss of Seal Injection, THEN EVALUATE initiating RCS cooldown. UNSAT Cue: When step addressed state "Shift Manager is evaluating the need to cooldown" STANDARD: Candidate addresses the need for the cooldown evaluation. COMMENTS: STEP 16.: 8. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix. SAT UNSAT Cue: When step addressed state "Shift Manager will evaluate EPIPs" STANDARD: Candidate addresses the step COMMENTS: STEP 17.: 9. EVALUATE the following Tech Specs for applicability: SAT

3.2.5, DNB Parameters
3.4.1.1, Reactor Coolant Loops and Coolant Circulation - Startup and UNSAT Power Operation
3.4.1 .2, Reactor Coolant System - Hot Standby
3.4.1.3, Reactor Coolant System - Shutdown
3.4.6.2, RCS Operational Leakage Cue: When step addressed state "SRO will evaluate Tech Specs" STANDARD: Candidate notifies SRO to evaluate Tech Spec.

COMMENTS:

JPM B.1.b Page 10 of 11 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 18.: 10. GO TO appropriate plant procedure. END OF SECTION SAT UNSAT Cue: To candidate "'We will stop here" STANDARD: Candidate recognizes that a transition from the AOP is required. Stop Time__ End of JPM

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. Unit 1 is in MODE 1 at 14% reactor power preparing to roll the main turbine.

Currently awaiting completion of maintenance activities. INITIATING CUES:

1. You are the OATe and are to monitor the control board and respond to conditions as required.

This JPM contains Time Critical steps

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOI PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Revision 22 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER RESPONSI BLE ORGAN IZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 12/19/2005 REVISION DESCRIPTION: Revised to clarify actions if neither RCP lower bearing temperature nor RCP seal temperature indication is available (PER 93845). Corrected inconsistency between caution in Section 2.0 and Appendix B.

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 1.0 PURPOSE This procedure provides the actions necessary to mitigate the effects of a Reactor Coolant Pump (RCP) trip below P-8 (35% power), excessive RCP seal leakage, and various RCP malfunctions. Page 2 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.0 OPERATOR ACTIONS CAUTION: Exceeding the following limitations requires trip of the affected RCP, unless RCP operation is required by FR-C.1, Inadequate Core Cooling or FR-C.2, Degraded Core Cooling:

RCP #1 Seal ~P less than 220 psid
RCP #1 Seal Temperature greater than 225°F
RCP Lower Bearing Temperature greater than 225°F
RCP Upper Motor Bearing Temperature greater than 200°F
RCP Lower Motor Bearing Temperature greater than 200°F
RCP Motor Voltage less than 5940V or greater than 7260V
RCP Motor Amps greater than 608 amps
RCP Vibration greater than 20 mils on any axis (x and/or y) [C.3]

NOTE 1: During plant startup following seal maintenance, the seal package should seat and operate normally following 24 hours of run time. NOTE 2: RCP trip criteria is also located in Appendix B. This appendix should be referred to throughout the performance of this procedure.

1. DIAGNOSE the failure:

IF... GOTO SECTION PAGE Reactor Coolant Pump(s) tripped or shutdown required 2.1 4 RCP #1 Seal Leakoff high flow (high flow Alarm) 2.2 7 RCP #1 Seal Leakoff low flow (low flow Alarm) 2.3 13 RCP #2 Seal Leakoff high flow (high RCP standpipe level) 2.4 17 RCP #3 Seal Leakoff high flow (low RCP standpipe level) 2.5 20 RCP Motor Stator Temperature High 2.6 23 Page 3 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Coolant Pump Tripped or Shutdown Required CAUTION: A rapid drop in level and steam flow on the affected loop SIG may occur when RCP is tripped.

1. CHECK reactor power SHUT DOWN to MODE 3 within 1 hour.

greater than 10%. GO TO Step 3. NOTE: This procedure is intended to be performed concurrently with E-O, Reactor Trip or Safety Injection.

2. TRIP the reactor, and GO TO E-O, Reactor Trip or Safety Injection, WHILE continuing in this

___11"--- procedure.

3. STOP and LOCK OUT affected RCP(s).

Page 4 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Coolant Pump Tripped or Shutdown Required (cont'd) CAUTION: If the RCP seal return flow control valve (FCV) is NOT closed within 5 minutes of stopping the Rep with excessive leakoff, seal damage may occur. [C.2]

4. MONITOR RCP seal leakoff WHEN the RCP has coasted down (30 sec.),

less than 8 gpm per pump: THEN CLOSE affected RCP seal return FCV: [C.2]

FR-62-24 [RCP 1 & 2]
FCV-62-9 [RCP 1]
FR-62-50 [RCP 3 & 4]
FCV-62-22 [RCP 2]
FCV-62-35 [RCP 3]
FCV-62-48 [RCP 4]

5. PULL TO DEFEAT affected loop ~T and T-avg:

XS-68-2D (~T)
XS-68-2M (T-avg)

6. CHECK RCPs 1 and 2 RUNNING. CLOSE affected loop's pressurizer spray valve.

Page 5 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Coolant Pump Tripped or Shutdown Required (cont'd) CAUTION: Restoring seal water injection to a hot seal package could result in failure of the RCP seals. NOTE: The plant should be cooled down to reduce heat input into the pump seal package if RCP seal injection flow has been lost and cannot be restored prior to exceeding temperature limits.

7. IF RCP Seal Temperatures or Bearing Temperatures are increasing uncontrolled due to loss of Seal Injection, THEN EVALUATE initiating RCS cooldown.

8. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.

9. EVALUATE the following Tech Specs for applicability:

3.2.5, DNB Parameters
3.4.1.1, Reactor Coolant Loops and Coolant Circulation - Startup and Power Operation
3.4.1.2, Reactor Coolant System -

Hot Standby

3.4.1.3, Reactor Coolant System -

Shutdown

3.4.6.2, RCS Operational Leakage 10.

___111"--- GO TO appropriate plant procedure. END OF SECTION Page 6 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.2 RCP #1 Seal Leakoff High Flow

CAUTION: RCP bearing damage may occur if temperature exceeds 225°F.
CAUTION: If the RCP seal return flow control valve is NOT closed within 5 minutes of stopping the RCP with excessive leakoff, seal damage may occur. [C.2]

1. MONITOR #1 seal leakoff a. MONITOR RCP lower bearing less than 6 gpm per pump: temperature and seal temperature.

FR-62-24 [RCP 1 & 2] IF RCP lower bearing temperature OR seal temperature are rising
FR-62-50 [RCP 3 & 4] uncontrolled, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required. [C.1] [C.2]

                                                            ----=---

IF lower bearing temperature AND seal temperature indication are NOT available for affected RCP, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required. [C.1]

                                                            ---~

(Step continued on next page.) Page 7 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE ,. RESPONSE NOT OBTAINED 2.2 RCP #1 Seal Leakoff High Flow (cont'd)

1. (Continued) b. CHECK #1 seal leakoff flow:

IF #1 seal leakoff flow greater than 8 gpm, THEN PERFORM the following:

1) INITIATE plant shutdown at 2-5% per minute USING AOP-C.03, Emergency Shutdown.

2) WHEN reactor is tripped, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required. [C.1]

___;11-- .. IF #1 sealleakoff flow less than 8 gpm, THEN PERFORM the following:

1) CONTROL RCP seal injection flow for the affected RCP greater than or equal to 9 gpm.

2) CONTACT Engineering for recommendations WHILE continuing with this procedure.

(Step continued on next page.) Page 8 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.2 RCP #1 Seal Leakoff High Flow (cont'd)

1. (Continued) 3) IMPLEMENT Engineering recommendations to address specific RCP seal performance conditions.

OR COMPLETE normal plant shutdown within 8 hours USING appropriate plant procedure.

4) WHEN reactor is shutdown or tripped, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required. [C.1]

2. MONITOR RCP lower bearing and IF any of the following conditions met:

seal water temperatures less than 225°F.

RCP lower bearing temperature or seal water temperature greater than 225°F OR
seal leakoff flow greater than 6 gpm AND lower bearing and seal temp NOT available for affected RCP THEN GO TO Section 2.1, RCP Tripped or Shutdown Required. [C.1]

                                                         ----~

Page 9 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.2 RCP #1 Seal Leakoff High Flow (cont'd)

3. MONITOR RCP #1 seal ilP GO TO Section 2.1, RCP Tripped or greater than 220 psid: Shutdown Required. [C.1]

PDI-62-8A

_ _ _:e---

PDI-62-21A
PDI-62-34A
PDI-62-47A

4. ENSURE RCP seal water supply flow IF seal water supply flow is less than 6 gpm 6-10 gpm per pump: AND CANNOT be restored,

FI-62-1A THEN ENSURE CCS supply to thermal barriers is
FI-62-14A less than 105°F:
FI-62-27A
TR-70-161
FI-62-40A [CCS HX1A1(2A1)/1A2(2A2)

Outlet Temp]

5. CONTACT Engineering for recommendations WHILE continuing with this procedure.

6. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.

Page 10 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.2 RCP #1 Seal Leakoff High Flow (cont'd)

7. EVALUATE the following Tech Specs for applicability:

3.2.5, DNB Parameters
3.4.1.1, Reactor Coolant Loops and Coolant Circulation - Startup and Power Operation
3.4.1.2, Reactor Coolant System -

Hot Standby

3.4.1.3, Reactor Coolant System -

Shutdown

3.4.6.2, RCS Operational Leakage CAUTION: Slow and uniform temperature adjustments (approx. 50°F in one hour) will prevent thermal shock to the seals.

8. CHECK VCT outlet temperature ADJUST HIC-62-78A to reduce VCT less than 130°F [TI-62-131]. temperature to less than 130°F.

9. ENSURE VCT pressure between 17 psig and 45 psig [PI-62-122].

Page 11 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.2 RCP #1 Seal Leakoff High Flow (cont'd)

10. CHECK RCP lower bearing and IF any of the following conditions met:

seal water temperature less than 180°F:

affected RCP lower bearing or seal water temperature greater than 180°F OR
lower bearing and seal water temp indication NOT available for affected RCP, THEN GO TO Step 1.

_ _ _;11-. 11. GO TO appropriate plant procedure. END OF SECTION Page 12 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.3 RCP #1 Seal Leakoff Low Flow

1. CHECK #1 seal leakoff flow GO TO Step 4.

greater than 0.8 gpm per pump:

FR-62-23 [RCP 1 & 2]
FR-62-49 [RCP 3 & 4]

2. CHECK #1 seal leakoff flow GO TO Step 4.

greater than 0.9 gpm per pump and NOT decreasing:

FR-62-23 [RCP 1 & 2]
FR-62-49 [RCP 3 & 4]

3. GO TO appropriate plant procedure.

4. ENSURE RCP seal water supply flow IF seal water supply flow is less than 6 gpm between 6 gpm and 10 gpm per pump: AND CANNOT be restored, THEN

FI-62-1A ENSURE CCS supply to thermal barriers is
FI-62-14A less than 105°F:
FI-62-27A
TR-70-161

[CCS HX 1A1(2A1)/1A2(2A2)

FI-62-40A Outlet Temp]

Page 13 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.3 RCP #1 Seal Leakoff Low Flow (cont'd)

5. CONTACT Engineering for recommendations WHILE continuing with this procedure.

6. ENSURE VCT pressure between 17 psig and 45 psig [PI-62-122].

7. CHECK RCP standpipe level alarms MONITOR the following:

DARK [M-5B, A-2, B-2, C-2, 0-2].

a. RCOT parameters (O-L-2 AB, el. 669)

Level, LI-77-1
Pressure, PI-77-2
Temperature, TI-77-21

b. Cntmt FI. & Eq. Sump Level rate of rise (ICS pt. U0969)

Page 14 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.3 RCP #1 Seal Leakoff Low Flow (cont'd)

8. VERIFY RCP #2 seal leakoff less than GO TO Section 2.4, RCP #2 Seal or equal to 0.5 gpm USING Appendix A, Leakoff High Flow.

RCDT Level Rate-of-Change.

9. MONITOR RCP lower bearing IF any of the following conditions met:

temperature and seal water temperature

affected RCP lower bearing temp are stable and within limits or seal water temp rising uncontrolled (less than 225°F).

OR

affected RCP lower bearing temp or seal water temp greater than 225°F OR
affected RCP lower bearing temp and seal temp indication NOT available THEN GO TO Section 2.1, RCP Tripped or Shutdown Required. [C.1]

                                                     ----~

Page 15 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.3 RCP #1 Seal Leakoff Low Flow (cont'd) CAUTION: If low seal leakoff compensatory actions are NOT successful, seal failure may result as indicated by a sudden increase in seal leakoff flow (greater than 8 gpm). NOTE: Plant shutdown may be terminated if Seal Leakoff flow stabilizes at greater than 0.8 gpm with pump Lower Bearing temperature and Seal Water Temperature remaining stable (no indications of seal failure).

10. MONITOR RCP #1 sealleakoff flow INITIATE normal plant shutdown greater than 0.8 gpm: USING appropriate plant procedures AND

FR-62-23 [RCP 1 & 2] STOP affected RCP within 8 hours.
FR-62-49 [RCP 3 & 4]

IF RCP #1 seal leakoff flow reverts to high leakage (greater than 8.0 gpm):

FR-62-24 [RCP 1 & 2]
FR-62-50 [RCP 3 & 4]

THEN GO TO Section 2.1 , RCP Tripped or Shutdown Required.

                                                         ---~             ..

11. CHECK #1 seal leakoff flow GO TO Step 1.

greater than 0.9 gpm per pump and NOT decreasing:

FR-62-23 [RCP 1 & 2]

                                                         ---~

FR-62-49 [RCP 3 & 4]

Page 16 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.3 Rep #1 Seal Leakoff Low Flow (cont'd)

12. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.

13. EVALUATE the following Tech Specs for applicability:

3.2.5, DNB Parameters
3.4.1.1, Reactor Coolant Loops and Coolant Circulation - Startup and Power Operation
3.4.1.2, Reactor Coolant System -

Hot Standby

3.4.1.3, Reactor Coolant System -

Shutdown

3.4.6.2, RCS Operational Leakage 14.

___111._--- GO TO appropriate plant procedure. END OF SECTION Page 17 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.4 RCP #2 Seal Leakoff High Flow NOTE: A leakoff of greater than 0.5 gpm indicates that a seal problem exists.

1. NOTIFY Engineering to consult with Westinghouse for continued RCP operation as necessary.

2. CHECK RCP standpipe level alarm(s) GO TO Step 3.

LIT [M-5B, A-2, B-2, C-2, D-2].

a. MONITOR RCOT parameters at Radwaste Panel [Aux Bldg, 669' elev.]:

Level, LI-77-1
Pressure, PI-77-2
Temperature, TI-77-21

b. FILL affected RCP standpipe USING AR-M-5B, Annunciator Response.

RCP 1 [A-2]
RCP 2 [B-2]
RCP 3 [C-2]
RCP 4 [0-2]

c. IF RCP standpipe level alarm clears, THEN GO TO Section 2.5, RCP #3 Seal Leakoff High Flow.

Page 18 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.4 RCP #2 Seal Leakoff High Flow (cont'd)

3. MONITOR RCP #2 seal INTACT: PERFORM the following within 8 hours:

VERIFY RCP #2 seal leakoff a. PERFORM normal plant shutdown less than or equal to 0.5 gpm USING appropriate plant procedure.

USING Appendix A, RCOT Level Rate-of-Change.

VERIFY RCP vibration is within limits b. WHEN reactor is shutdown or tripped, of annunciator response 1-AR-M5-A THEN (window 0-,3) VIBRATION & LOOSE STOP and LOCK OUT affected RCP.

PARTS MONITORING ALM.

CONTACT Engineering for c. PULL TO DEFEAT affected loop ~T recommendations. and T-avg:
XS-68-20 (~T)
XS-68-2M (T-avg)

Page 19 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.4 RCP #2 Seal Leakoff High Flow (cont'd)

4. CHECK RCPs 1 and 2 RUNNING. CLOSE affected loop's pressurizer spray valve.

5. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.

6. EVALUATE the following Tech Specs for applicability:

3.2.5, DNB Parameters
3.4.1.1, Reactor Coolant Loops and Coolant Circulation - Startup and Power Operation
3.4.1.2, Reactor Coolant System -

Hot Standby

3.4.1.3, Reactor Coolant System -

Shutdown

3.4.6.2, RCS Operational Leakage 7.

       --_l1li."'--

GO TO appropriate plant procedure. END OF SECTION Page 20 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.5 RCP #3 Seal Leakoff High Flow

1. CHECK RCP standpipe level alarms PERFORM the following:

DARK [M-5B, A-2, B-2, C-2, 0-2].

a. MONITOR Cntmt FI. & Eq. Sump Level rise rate (ICS pt. U0969)

b. FILL affected RCP standpipe USING AR-M-5B, Annunciator

Response

RCP 1 [A-2]
RCP 2 [B-2]
RCP 3 [C-2]
RCP 4 [0-2]

c. IF RCP bearing temperature rising, THEN GO TO Section 2.4, RCP #2 Seal Leakoff High Flow, Step 1.

                                                       ---~-

Page 21 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.5 RCP #3 Seal Leakoff High Flow (cont'd) NOTE: A leakoff rate of greater than 500 cc/hr indicates that a seal problem exists. The frequency and length of time filling the RCP standpipe may indicate the severity of the leak.

2. MONITOR RCP #3 seal intact: PERFORM the following within 8 hours:

VERIFY RCP vibration is within limits a. PERFORM non:nal plant shutdown of annunciator response 1-AR-M5-A USING appropriate plant procedure.

(window D-3) VIBRATION & LOOSE PARTS MONITORING ALM.

CONTACT Engineering for b. WHEN reactor is shutdown or tripped, assistance in determining acceptable THEN leak rate for continued RCP STOP and LOCK OUT affected RCP.

operation.

c. PULL TO DEFEAT affected loop ~ T and T-avg:

XS-68-2D (~T)
XS-68-2M (T-avg)

3. CHECK RCPs 1 and 2 RUNNING. CLOSE affected loop's pressurizer spray valve.

4. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.

Page 22 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.5 Rep #3 Seal Leakoff High Flow (cont'd)

5. EVALUATE the following Tech Specs for applicability:

3.2.5, DNB Parameters
3.4.1.1, Reactor Coolant Loops and Coolant Circulation - Startup and Power Operation
3.4.1.2, Reactor Coolant System -

Hot Standby

3.4.1.3, Reactor Coolant System -

Shutdown

3.4.6.2, RCS Operational Leakage

6. GO TO appropriate plant procedure.

END OF SECTION Page 23 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.6 RCP Motor Stator Temperature High CAUTION: Operating the RCP with excess winding temperature will reduce the expected life of the motor insulation. NOTE: RCP motor winding temperature limits are as follows:

329°F if RCS temperature is less than 540°F.
311°F if RCS temperature is greater than or equal to 540°F.

1. MONITOR RCP Motor Stator temperature a. IF RCP Motor Stator temperature less than applicable limit by monitoring reaches applicable limit the following computer points.: AND indication is verified valid, THEN

Pump 1: T0409A, 411A or 412A PERFORM the following:
Pump 2: T0429A, 431A or 432A

1) IF reactor power greater than 10%,

Pump 3: T0449A, 451A or 452A THEN
Pump 4: T0469A, 471A or 472A INITIATE a plant shutdown at 2% per minute USING AOP-C.03, Emergency Shutdown.

2) WHEN reactor power less than 10%,

THEN GO TO Section 2.1, RCP Tripped or Shutdown Required. [C.1]

                                                                  ---~-

Page 24 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.6 Rep Motor Stator Temperature High (continued)

2. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.

3. EVALUATE the following Tech Specs for applicability:

3.2.5, DNB Parameters
3.4.1.1 , Reactor Coolant Loops and Coolant Circulation - Startup and Power Operation
3.4.1.2, Reactor Coolant System -

Hot Standby

3.4.1.3, Reactor Coolant System -

Shutdown

3.4.6.2, ReS Operational Leakage 4.

GO TO appropriate plant procedure. END OF SECTION Page 25 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS AOP-R.04 Rev. 22 3.0 SYMPTOMS AND ENTRY CONDITIONS 3.1 Symptoms A. Any of the following annunciators may indicate a RCP malfunction: PANEL 0-XA-55-27-B-A, COMPONENT COOLING 0-2 RC PUMP 1 OIL COOLERS OUTLET FLOW LOW 0-3 RC PUMP 2 OIL COOLERS OUTLET FLOW LOW 0-4 RC PUMP 3 OIL COOLERS OUTLET FLOW LOW 0-5 RC PUMP 4 OIL COOLERS OUTLET FLOW LOW PANEL 0-XA-55-27-B-E, COMPONENT COOLING/MiSe 0-2 RC PUMP 1 OIL COOLERS OUTLET FLOW LOW 0-3 RC PUMP 2 OIL COOLERS OUTLET FLOW LOW 0-4 RC PUMP 3 OIL COOLERS OUTLET FLOW LOW 0-5 RC PUMP 4 OIL COOLERS OUTLET FLOW LOW PANEL 1(2)-XA-55-1B, AUXILIARY POWER/STATION SERVICE A-1 6900V UNIT BO 1(2)A TRANSFER A-2 6900V UNIT BO 1(2)B TRANSFER A-3 6900V UNIT BO 1(2)C TRANSFER A-4 6900V UNIT BO 1(2)0 TRANSFER B-1 6900V UNIT BO 1(2)A FAILURE OR UNOERVOLTAGE B-2 6900V UNIT BO 1(2)B FAILURE OR UNOERVOLTAGE B-3 6900V UNIT BO 1(2)C FAILURE OR UNOERVOLTAGE B-4 6900V UNIT BO 1(2)0 FAILURE OR UNOERVOLTAGE E-3 MOTOR TRIPOUT PNL 1(2)-M-1 THRU 1(2)-M-6 Page 26 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 3.1 Symptoms (cont'd) PANEL XA-55-5A, REACTOR COOLANT - STM - FW A-6 TS-68-2M/N REACTOR COOLANT LOOPS T AVG/AUCT T AVG OEVN HIGH - LOW B-5 CNTMT FLOOR & EQUIP DRAIN SUMP HI-HI-HI B-6 TS-68-2A1B REACTOR COOLANT LOOPS L1T OEVN HIGH - LOW 0-3 VIBRATION & LOOSE PARTS MONITOR ALARM PANEL XA-55-5B, evcs SEAL WATER AND RCP A-2 LS-62-6A REAC COOL PMP 1 STANDPIPE LVL HIGH-LOW A-3 FS-62-10 REAC COOL PMPS SEAL LEAKOFF LOW FLOW A-4 PdIS-62-96 SEAL WATER INJECTION FILTER HIGH L1P A-5 LS-68-10AlB REAC COOL PMP 1 OIL RESERVOIR LEVEL HI-LOW B-2 LS-62-19A REAC COOL PMP 2 STANDPIPE LVL HIGH-LOW B-3 FS-62-11 REAC COOL PMPS SEAL LEAKOFF HIGH FLOW B-4 PdIS-62-97 SEAL WATER INJECTION FILTER 2 HIGH L1P B-5 LS-68-34A1B REAC COOL PMP 2 OIL RESERVOIR LEVEL HI-LOW C-2 LS-62-32A REAC COOL PMP 3 STANDPIPE LVL HIGH-LOW C-3 FS-62-1 REAC COOL PMPS SEAL WATER FLOW LOW C-5 LS-68-53A1B REAC COOL PMP 3 OIL RESERVOIR LEVEL HI-LOW 0-2 LS-62-45A REAC COOL PMP 4 STANDPIPE LVL HIGH-LOW 0-3 PdS-62-8 REAC COOL PMPS SHAFT SEAL WATER L1P 0-5 LS-68-76A1B REAC COOL PMP 4 OIL RESERVOIR LEVEL HI-LOW E-1 REAC COOL PMPS MOTOR STATOR TEMPERATURE HIGH E-2 TS-62-42 REAC COOL PMPS LOWER BEARING TEMP HIGH E-3 REACTOR COOLANT PUMPS MOTOR THRUST BEARING TEMP HIGH E-4 TS-62-43 REAC COOL PMPS SEAL WATER TEMP HI E-5 FIS-62-12 RCP NO 1 SEAL BYPASS FLOW LOW Page 27 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS AOP-R.04 Rev. 22 3.1 Symptoms (cont'd) PANEL XA-55-6A COMPONENT COOLING A-4 FS-68-6A REACTOR COOLANT LOOP 1 LOW FLOW B-4 FS-68-29A REACTOR COOLANT LOOP 2 LOW FLOW C-4 FS-68-48A REACTOR COOLANT LOOP 3 LOW FLOW 0-4 FS-68-71A REACTOR COOLANT LOOP 4 LOW FLOW E-4 RCP BUS UNDERFREQUENCY I UNDERVOLTAGE B. Deviations or unexpected indication on any of the following may indicate a RCP malfunction:

1. Erratic or abnormal RCP motor current

2. Erratic RCP motor frequency

3. Erratic or low RCS Loop Flow indications

4. Plant Computer RCP temperature alarms

5. Indication of high vibrations on a RCP

6. Low RCP #1 seal LlP

7. High or low RCP #1 Seal leakoff flow

8. High or low RCP #1 Seal supply flow

9. Increasing RCP #1 Seal temperature

10. Increasing RCP lower bearing temperature

11. High VCT temperature

12. High VCT pressure

13. High VCT level

14. Increasing Reactor Coolant Drain Tank level

15. High Containment Floor & Equipment Sump Level rate of rise Page 28 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 3.1 Symptoms (cont'd) C. Any of the following automatic actions may indicate a RCP malfunction:

1. RCP trip from motor faults

2. Reactor Trip

3. Safety Injection 3.2 Entry Conditions None END OF SECTION Page 29 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22

4.0 REFERENCES

4.1 Performance A. EPIP-1, Emergency Plan Initiating Conditions Matrix B. E-O, Reactor Trip or Safety Injection C. AR-M-5B, Annunciator Response 4.2 Technical Specifications A. 3.2.5, DNB Parameters B. 3.4.1.1, Reactor Coolant Loops and Coolant Circulation - Startup and Power Operation C. 3.4.1.2, Reactor Coolant System - Hot Standby D. 3.4.1.3, Reactor Coolant System - Shutdown E. 3.4.6.2, RCS Operational Leakage Page 30 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 4.3 Plant Drawings A. 47W600, Sheets 57,60 B. 47W61 0-68, Sheets 1,2,3,4,6 C. 47W61 0-77-3 D. 47W61 0-62-2 E. 47W61 0-72-1 F. 47W61 0-74-1 G. 47W61 0-63-1 H. 47W61 0-67-1 I. 47W61 0-3-3 J. 47W61 0-70-1 K. 47W61 0-30-2 L. 47W61 0-47-1 M. 47W61 0-82-1 N. 45N765, Sheets 1, 2 O. 45N724, Sheets 1, 2, 3, 4 P. 45N751, Sheets 1, 2, 3,4, 5, 6, 7, 8 Q. 45N732, Sheets 1, 2 4.4 10 CFR A. 10CFR50, Appendix R Page 31 of 34

SQN AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 Page 1 of 1 APPENOIXA RCOT LEVEL RATE OF CHANGE CALCULATE RCDT level rate of change to obtain RCP #2 seal leakoff flowrate. FINAL VOLUME (gal)-INITIAL VOLUME (gal) =LEVEL RATE OF CHANGE gpm L1 TIME (minutes) ---- Figure C.20 Page 1 of 1 REACTOR COOLANT DRAIN TANK LEVEL INDICATION ON LI-77-1 t- 100 Z -/ l-' ~ V ...,~ V 1LI 90 (J .. v / /' 0=: 80 v ~ ... v LU ...,v ~ I.'" l/ 0- V ~ V 70 l/ i""

                                                                                                       ~
                                                                                                         ~

l/

                                                                                            ~v   ~v J'V 60                                                       \                v        ~    ~
    ..J                                                                                 .....

LLI 50 ~ l/ l/ v lIJ V

                                                                     ...... ~ ~~ ~v
                                                                            ~    :;/
    ...I   40                                            v     l,,'
                                                                    ~

v "\

                                                  ..",'"  ~
                                                                ./'7             ~

0 30 ,,- 7 -,,/ N". '" ru "N .T RJ .NI i( LLI /V" ./ V J-- 20

                              ""-JI". . Vv
                                            ....,..v (5                  ~,r  ~
    -Z C

10 0

                   .. ./
                      ~   ""
                           ./

oj lso 100 150 200 250 300 350 10 GAL. VOLUME

GALLONS INCREMENTS NOTE: LEVEL TAP NOT AT TANK BOTTOM Page 32 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 APPENDIX B PAGE 1 of 1 RCP TRIP CRITERIA Exceeding the following limitations requires trip of the affected RCP, unless RCP operation is required by FR-C.1, Inadequate Core Cooling or FR-C.2, Degraded Core Cooling [C.1]:

RCP #1 Seal ~P less than 220 psid
RCP #1 Seal Temperature greater than 225°F
RCP Lower Bearing Temperature greater than 225°F
RCP Upper Motor Bearing Temperature greater than 200°F
RCP Lower Motor Bearing Temperature greater than 200°F
RCP Motor Voltage less than 5940V or greater than 7260V
RCP Motor Amps greater than 608 amps
RCP Vibration greater than 20 mils on any axis (x and/or y) [C.3]

Page 33 of 34

AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 22 COMMITMENT LIST

SUMMARY

OF COMMITMENT COMMITMENT ID COMMITMENT CORRESPONDENCE C.1 Provide clear instructions to the NER 82-005 operators should any seal temperature, pressure, or leakage INPO SOER 81-007 alarms annunciate. Include conditions for continued operation or immediate INPO SOER 82-005 shutdown. C.2 Update procedural guidance to NER 930512001 conform to most recent Westinghouse recommendations on RCP shutdown Westinghouse Tech Bulletin with No. 1 seal leakage outside the NSD-TB-93-01-R1 operating limits. C.3 Update procedural guidance to include NER 970134001 RCP vibration as a limitation. TROIINPO SER 97-002 Page 34 of 34

JPM B.1.c Page 1 of 11 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c JPM WITHDRAW SHUTDOWN BANKS PREPAREDI REVISED BY: Datel VALIDATED BY:

Datel APPROVED BY: Datel (Operations Training Manager)

CONCURRED: ** Datel (Operations Representative)

Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.

             ** Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM B.1.c Page 2 of 11 Rev. 0 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/ NUMBER REVISION AFFECTED REVISED BY: 0 Modified JPM Y All v - Specify if the JPM change will require another validation (Y or N). See cover sheet for criteria.

JPM B.1.c Page 3 of 11 Rev. 0 SEQUOYAH NUCLEAR PLANT ROISRO JOB PERFORMANCE MEASURE Task: Withdraw Shutdown Banks JAITA task:

       # 0010180101 (RO) Withdraw shutdown Banks KIA Ratings:

001 Control Rod Drive System A3 Ability to monitor automatic operation of the CRDS, including: (CFR: 41.7/45.13) A3.05 Individual vs. group rod position 3.5/3.5 Task Standard:

1) Initiation of withdrawal of shutdown banks is initiated starting with Shutdown Bank A.

2) Following failure of the group step counters, the reactor trip breakers are opened in accordance with Technical Requirement 3.1.3.3.

Evaluation Method: Simulator - - x -- In-Plant _

=======================================================================

Performer: NAME Start Time _ Performance Rating: SAT UNSAT Performance Time Finish Time _ Evaluator: -------- ~/ __- SIGNATURE DATE

=======================================================================

COMMENTS

JPM B.1.c Page 4 of 11 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Sequenced steps identified by an "s"

2. Any UNSAT requires comments

3. Place MODE 3 sign on the simulator.

4. This task is to be performed using the simulator in IC 183. If not available then raise boron to 1800ppm and withdraw rods to D @ 216; Trip reactor; Close Reactor trip breakers; Reset FWI and one MFPT, Stop TD AFW pump, and Reset M/D LCVs and stabilize SG levels.

Place Rod Control Mode Selector Switch to the Manual position and rest startup switch.

5. When the candidate withdraws Shutdown bank A approximately 100 steps, insert I/O Override / RD control rod drive system / Logical Output ZROSCSBAG1 (RESET) to ON to fail the Shutdown Bank A step counters to '0'

6. Ensure operator performs the following required actions for SELF-CHECKING;

a. Identifies the correct unit, train, component, etc.

b. Reviews the intended action and expected response.

c. Compares the actual response to the expected response.

Validation Time: CR. 16 min Local - - - - - Tools/Equipment/Procedures Needed: 0-GO-2 0-GO-85-1 TR 3.1.3.3 AOP-C.01 TI-28

References:

Reference Title Rev No,

1. 0-GO-2 Unit startup From Hot Standby to Reactor Critical 28

2. 0-SO-85-1 Control Rod Drive System 33

3. TR 3.1.3.3 Reactivity Control Systems, Position Indicating 13 System - Shutdown

4. AOP-C.01 Rod Control System Malfunctions 17

5. T1-28 Curve Book 215

=================================================================

READ TO OPERATOR Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. Unit startup in progress following a trip from 100 % power due to a generator electrical relay malfunction.

2. Per TI-28, the shutdown banks fully withdrawn positon is 228 steps INITIATING CUES:

1. You are to withdraw the shutdown banks in accordance with 0-GO-2, Unit Startup From Hot Standby to Reactor Critical, Section 5.1, Step [26.2]

2. Notify the SRO when the shutdown banks are fully withdrawn.

JPM B.1.c Page 5 of 11 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 1.: Obtain the appropriate procedure. SAT UNSAT STANDARD: Operator identifies 0-SO-85-1 and goes to Section 6.3 "Manual Operation of Rod Control System Below 15 Percent Power". Start Time__ STEP 2.: [1] ENSURE Section 5.2, Reset/Close Reactor Trip Breakers has SAT been completed. _UNSAT STANDARD: Candidate determines by looking at procedure that section 5.2 is complete. COMMENTS: STEP 3.: [2] IF the shutdown and control rods were withdrawn 5 steps to SAT prevent thermal lockup during an RCS cooldown, THEN _UNSAT ENSURE rods are fully inserted prior to withdrawal. Cue: If asked "Rods were not withdrawn 5 steps" STANDARD: Candidate N/As the step. COMMENTS: STEP 4.: [3] MOMENTARILY PLACE [SUS], Rod Control Startup Step Counter SAT Reset to the STARTUP position to reset Control Rod Drive UNSAT System. STANDARD: Candidate places Rod control Startup Step Counter Reset, 1-SUS, to startup and then releases switch. COMMENTS:

JPM B.1.c Page 6 of 11 Rev. a Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 5.: [4] ENSURE all Full Length Rod step counters reset to zero. - SAT

                                                                                     -   UNSAT STANDARD:      Candidate verifies all 14 step counters are reading '000' COMMENTS:

STEP 6.: [5] VERIFY rod control IN-OUT direction lights are NOT LIT. - SAT

                                                                                     -   UNSAT STANDARD:      Candidate verifies that both the RODS IN and the RODS OUT lights are not lit on 1-M-4.

COMMENTS: STEP 7.: [6] DEPRESS [RCAS], Rod Urgent Failure Alarm Reset. - SAT

                                                                                     -    UNSAT STANDARD:      Candidate pushes Rod Urgent Failure Alarm Reset, 1-RCAS COMMENTS:

STEP 8.: [7] RESET Window 6 (A-6), ROD CONTROL SYSTEM URGENT - SAT FAILURE alarm on panel [XA-55-4B] using [XS-55-4A], UNSAT Annunciator RESET/ACKITEST Switch. - STANDARD: Candidate resets the ROD CONTROL SYSTEM URGENT FAILURE alarm using 1-XS-55-4A if lit. COMMENTS:

JPM 8.1.c Page 7 of 11 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 9.: [8] VERIFY the following rod control system alarms on panel SAT [XA-55-4B] are NOT LIT:

WfNOOW UNSAT NOT LIT NitlMBER ~:~)

STANDARD: Candidate verifies listed windows on 1-M-4 overhead annunciatot 1-XA-55-48 are not lit COMMENTS: STEP 10.: [9] ENSURE Plant computer points for rod bank position are ZERO SAT using the following computer points: UNSAT o o o o o o o o Cue: After candidate demonstrates ability to access computer points 'All listed points have been verified to be '0'. STANDARD: Candidate verifies listed computer points are reading '0' on ICS. There are several methods/screens to access the points COMMENTS:

JPM B.1.c Page 8 of 11 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 11.: [10] MONITOR Control Rod position USING Rod Position Indicators - SAT ICS screen 30 minute trend during SO & Control Banks withdrawal to aid in detecting rod misalignment. - UNSAT STANDARD: Candidate locates the Rod Position Indicator RPI TREND screen on the ICS. (when on RPI screen, the RPI TREND screen can be accessed via clicking on TREND.) COMMENTS: STEP 12.: [11] IF Individual Rod Position Indication does not indicate proper rod - SAT position during withdrawal of SO Banks, THEN

                                                                                     -   UNSAT

[a] STOP rod withdrawal. [b] ENSURE subcriticality. [c] CONTACT MIG AND INITIATE troubleshooting. [d] IF troubleshooting does not resolve the problem, OR subcriticality can NOT be verified, THEN INITIATE Reactor TRIP. STANDARD: Candidate acknowledges the requirement of the IF/THEN step for individual RPls. No action required. STEP 13.: [12] IF Individual Rod Position Indication does not indicate proper rod - SAT position during withdrawal of Control Banks, THEN

                                                                                      -   UNSAT GO TO AOP-C.01 section 2.6 Rod Position Indicator (RPI)

Malfunction - Modes 1 or 2. STANDARD: Candidate acknowledges the step, realizes it refers to control banks, and No action is required for this task of withdrawing shutdown banks COMMENTS:

JPM B.1.c Page 9 of 11 Rev. 0 Job Performance Checklist STEP/STAN DARD SAT/UNSAT STEP 14.: [13] PLACE [HS-85-5110], Rod Control Mode Selector to the SBA - SAT position.

                                                                                    -   UNSAT STANDARD:     Candidate rotates Mode Control Mode Selector, 1-HS-85-511 0, counterclockwise to the SBA position                                   Critical Step COMMENTS:

STEP 15.: [14] VERIFY Rod Speed Indicator [51-412], indicates - SAT 64 Steps/minute.

                                                                                    -   UNSAT STANDARD:     Candidate determines SI-412, Rod Speed, on 1-M-4 vertical panel is reading 64 steps/min COMMENTS:

STEP 16.: [15] ENSURE Shutdown Bank A demand position counters - SAT operational by performing the following: [C.2] UNSAT [a] BUMP [HS-85-5111], Rod Control Switch to withdraw - Shutdown Bank A one-half step at a time, for one full step. [b] CHECK group demand position counters advance properly. [c] BUMP [HS-85-5111] to withdraw Shutdown Bank A one-half step at a time, for the second full step. [d] VERIFY group demand position counters advance properly. [e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. B. INITIATE WO to have counter repaired. C. WHEN counter is repaired, THEN

1. ENSURE Shutdown Bank A fully INSERTED.

2. RETURN to beginning of this step.

STANDARD: Candidate uses Rod Control, 1-HS-85-5111, IN-OUT switch to withdraw SBA rods 2 steps in 12 step increments while checking the group step counters are operating properly. COMMENTS:

JPM B.1.c Page 10 of 11 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT Note to evaluator: The shutdown bank full out position is stated in the initial conditions, if candidate refers to TI-28 provide a cue that the full out position is 228 steps. STEP 17.: [16] WITHDRAW Shutdown Bank A to the FULLY WITHDRAWN SAT position using [HS-8S-S111]. UNSAT Cue: If candidate initiates use of TI-28 to determine full out position, state "The full out position is 228 steps. " Critical Step STANDARD: Candidate uses Rod Control, 1-HS-85-5111, IN-OUT switch on 1-M-4 to withdraw SBA COMMENTS: Note to evaluator: Malfunction to fail step counters is to be inserted when the rods reach approximately 100 steps. Candidate may refer to TR-3.1.3.3. If so the required action is to open the Reactor Trip breakers. STEP 18.: Open the Reactor Trip Breakers SAT UNSAT Cue: After the reactor trip breakers have been opened state' We will stop here" STANDARD: Candidate determines the Group 1 step counter is not capable of Critical determining the demand position for each of the Shutdown bank a rods Step within ~ 2 steps and opens the reactor trip breakers. Stop Time__ COMMENTS:

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. Unit startup in progress following a trip from 1000/0 power due to a generator electrical relay malfunction.

2. Per TI-28, the shutdown banks fully withdrawn positon is 228 steps INITIATING CUES:

1. You are to withdraw the shutdown banks in accordance with 0-GO-2, Unit Startup From Hot Standby to Reactor Critical, Section 5.1, Step [26.2]

2. Notify the SRO when the shutdown banks are fully withdrawn.

Sequoyah Nuclear Plant Unit 0 General Operating Instructions O-GO-2 UNIT STARTUP FROM HOT STANDBY TO REACTOR CRITICAL Revision 0028 Quality Related Level of Use: Conti"nuous Use Effective Date: 10-31-2007 Responsible Organization: OPS, Operations Prepared By: D. A. Porter Approved By: W. T. Leary Current Revision Description Revised Section 5.1 steps [28] and [29] to clarify applicability of Sect. 5.2 and 5.3. Added Sect. 5.2 step [67]. Modified title of Sect. 5.2 and 5.3. Added limitation associated with minimum temp for criticality. Provided more specific guidance on S/G level control in Sect. 4.0 Step [7]. THIS PROCEDURE IMPACTS REACTIVITY

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 2 of 85 Table of Contents 1.0 FI*RST SECT.ION 3 1.*1 Purpose : 3 1.2 Scope 3

2.0 REFERENCES

3 2.1 Performance References 3 2.2 Developmental References 5 3.0 PRECAUTIONS AND LIMITATIONS ...........................................*............................... 6 3.1 PRECAUTIONS 6 3.2 LIMITATIONS 8 4.0 PREREQUiSiTES ......................*.......................... ~ 9 5.0 INSTRUCTIONS 12 5.1 Actions to be performed prior to a reactor startup 12 5.2 Reactor Startup with Low Power Physics Testing 21 5.3 Reactor Startup without Physics Testing 45 6.0 RECORDS 69 A*ppendix A: DELETED ~ 70 Appendix B: MODE 3 TO MODE 2, 1 REVIEW AND APPROVAL 71 Appendix C: DETERMINING SOURCE RANGE COUNT RATE DOUBLING 79 Appendix D: ACTIONS IF REACTOR STARTUP MUST BE ABORTED 80, Appendix E: ACTIONS IF BANK D RODS REACH FULL OUT POSITION PRIOR TO CRITICALITY 81 Source Notes 83 ATTACHMENTS Attachment 1: UNIT STARTUP FROM HOT STANDBY TO REACTOR CRITICAL

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 70f 85 3.1 PRECAUTIONS (continued)

2. During Rod Movement

a. Ensure RO has peer check

b. EnsureRO is following procedure

c. EnsureRO understands criteria for stopping rod motion (based upon number of steps and/or nuclear instrument response)

d. Watch performance* of rod manipulation while listening to audible indication of rod .step

e. Ensure peer checking meets expectations (OPDP-1)

f. Re-verifyitems of initial evaluation (on previous page)

g. Monitor plant for expected response

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 8of8S 3.2 LIMITATIONS A. Simultaneous reactivity addition by rod withdrawal and dilution is NOT allowed while in the source range. B. If at any point during the approach to criticality, ONE of the two source range detectors shows an unexplained increase in count rate equal to or greater than a factor of 5, or if BOTH source range detectors show an unexplained increase in count rate equal to or greater than a factor of 2, the approach to criticality shall be SUSPEN*DED IMMEDIATELY (Le., all rod withdrawals and/or boron dilutions shall be terminated). Further positive reactivity changes shall not be resumed until an evaluation is performed and the Shift Manager authorizes a resumption in the approach to criticality. C. After refueling operations, the NIS indications may be inaccurate until calibration at higher power levels. The NIS calibration procedures will adjust the PRM trip set points to ensure that the excore detectors do not contribute to an overpower condition. Prior to startup, the PRM high range flux trip setpoint will be adjusted from 109 to 60%, with the rod stop (C-2) remaining at 103% . [C.3] D. While in Mode 3, maintain the Reactor Coolant System boron concentration in accordance with 0-SI-NUC-000-038.0, Shutdown Margin requirements. E. The stepping or tripping of the .Control Rod during periods when coolant crud level are high should be kept to a minimum. This will limit the possibility of CRDMmis-stepping due to crud contamination of CRDM latch assemblies. F. The lowest operating loop temperature (T -avg) shall be greater than or equal to 541°F (LCO 3.1.1.4, Minimum Temperature for Criticality).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 9 of 85 STARTUP No. - - - Unit - - - 4.0 PREREQUISITES NOTES

1) Throughout this Instruction where an IFITHEN statement exists, the step should be N/A'd if the condition does not exist.

2) Prerequisites may be completed in any order.

3) Management oversight is required for a Reactor Startup after a non-refueling outage.

A Reactor Startup after a refueling outage is a CIPTE. [1 ] ENSURE Instruction to be used is the latest copy of effective version. tv 1A [2] REVIEW Precautions and Limitations. [3] INDICATE below which instruction this GO is being entered from:

0-GO-1 (cold shutdown to hot standby)
0-GO-6 (30% reactor power to hot standby) o
0-GO-7 (hot standby to cold shutdown) o
0-GO-5 (normal power operation) o

[4] MAINTAIN pressurizer pressure within the normal operating band by use of the pressurizer heaters and spray valves. [5] MAINTAIN pressurizer level greater than or equal to 25%.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 10 of8S STARTUP No. - - - Unit-i-4.0 PREREQUISITES (continued) NOTE Due to instru*ment inaccuracies the steam dump or SG atmospheric relief valve setpoint of 84% or 1005 psig maybe +/- 1% or +/- 12 psig off. [6] MAINTAIN TAVG stable at approximately 547°F with steam dumps in pressure mode or with SG atmospheric relief valves. NOTE Minor S/G level variations which exceed the plus or minus 7% band should not be considered a procedural violation. [7] MAINTAIN steady-state S/G levels at approximately 33% (plus or minus 7%) using Auxiliary Feedwater. [8] ENSURE all reactor coolant pumps are in operation in accordance with 1,2-S0-68-2, Reactor Coolant Pumps. [C.12] [9] IF the reactor vessel head has been removed, THEN ENSURE conditional performance of 0-SI-SXX-085-043.0, Rod Drop Time Measurements, has been performed to comply with SR 4.1.3.4.a. [10] REQUEST Periodic Test Coordinate to confirm that the following checklists have been distributed: . [10.1] Mode 3 to Mode 2, 1, Surveillance Checklist (NA if previously performed for this startup). [10.2] Reactor Trip Breaker Checklist (NA if previously performed for this startup). [11] ENSURE East Valve Vault Room Vent Chute dampers OPEN. (inside door near SPING Room, Ref. PER 03-002446-000).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 11 of 85 STARTUP No. - - - Unit~ Date L!l !>>~"- I 4.0 PREREQUISITES .(continued) [12] NOTIFY MIGto re~scale LR-3-43A and LR-3-98A, Steam Generator Wide Range Level Recorders, to 80 0/0 - 90 0/0. [13] E*NSURE each performer documents their name and initials: Print Name Initials Print Name Initials

    ~1'lSO)"  -r~ Abbot        ~v  fA
    °Jk\L 6   . ANb~(),'I      ~

END OF TEXT

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 12 of 85 STARTUP No. - - - Unit -~- Date~ 5.0 INSTRUCTIONS 5.1 Actions to be performed prior to a reactor startup [1 ] ENSURE Section 4.0, Prerequisites complete. WItt NOTE Steps 5.1 [2] through 5.1[11] may be performed in any order. [2] INTIATE Appendix B, , Mode 3 to Mode 2,1 Review And Approval while continuing with this instruction. .~ [3] OBTAIN assistance from Systems Engineering to complete Appendix B steps associated with Pressurizer Spray line bypass valves. NOTE Steps for MFPT startup maybe performed in parallel with other activities. The MFPT trip busses shall be energized prior to entering Mod'e 2 (LeO 3.3.2.1 or 3.3.2) except as allowed by LCO 3.0.4. [C.1] [4] INITIATE applicable section(s) of 1, 2-S0-2/3-1 to prepare at least one MFP for startup, while continuing with this instruction. (N/Aif no MFPT available) [5] ENSURE TDAFW LCVs are in NORMAL. y/1A 1st

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 13 of 85 STARTUP No. Unit +- Date ~i 5.1 Actions to be performed prior to a reactor startup (continued) CAUTION Rapid changes in pressurizer enclosure temperature may result in pressurizer safety valve simmer. [6] IF lower compartment coolers are not in service, THEN [6.1 ] ALIGN lower compartment coolers to maintain pressurizer enclosure temperature less than 11 oaF in accordance withO-SO-30-5. [6.2] MONITOR Pressurizer enclosure temperature using Plant Computer pt. T1001A. [7] IF control rod drive coolers are not in service, THEN [7.1 ] ALIGN control rod drive coolers to maintain shroud enclosure temperature less than 164°F in accordance with 0-SO-30-6. [7.2] MONITOR Reactor Cavity Air temperature using Plant Computer pt. T1014A. NOTE New analysis is not required for this startup. Routine analysis is sufficient unless there is reason to suspect che.mistry has been changed. [8] NOTIFY Chemistry Supervisor that mode change from 3 to 2 requires sampling in accordance with O-SI-CEM-OOO-050.0, 0-SI-CEM~030-407 .2, and O-SI-CEM-030-415.0 requirements.

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 14 of 85 5.1 STARTUP No. Acti~ns to Unit 4-be performed prior to a reactor startup (continued) Date 0 llx JIo~ I I NOTE To preserve the life of 20 AST and 20* ET, power must be removed from turbine trip bus A and trip bus B if unit startup is extended. [9] ENERGIZE main turbine trip buses by CLOSING the following breakers (NA breakers not applicable): UNIT TRAIN BREAKER 250V DC POSITION INITIALS WIll TRAINA 1-BKRD-47-KA/516 BATT Bd 1 CLOSED 1st 1 wT~ TRAINB 1-BKRD-47-KB/516 BATT Bd 2 CLOSED 1st lJ/l{) TRAIN A 2-BKRD-47-KA/519 BATT Bd 1 CLOSED 1st 2 i,vfIf TRAIN B 2-BKRD-47-KB/519 BATT Bd 2 CLOSED 1st NOTE Step 5.1[10] may be marked N/A if not required. [10] PERFORM 0-PI-OPS-047-723.0, 20IAST, 201ET, 20-110PC, and 20-210PC Operability Verification (N/A if not performed).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 15 of 85 STARTUP No. - - - Unit 1 5.1 Actions to be performed prior to a reactor startup (continued) CAUTION Operation of the EHCpumps without the turbine being reset will result in overheating of the EHC fluid and "pumps. NOTE Startup of EHC and turbine reset "may be postponed until later in startup. (N/Aif postponed) [11 ] ENSURE EHC system in service in accordance with 1,2-80-47-2 (NA if previously performed). [12] IFno MFPT is ready for start up per 1,2-80-2/3-1, THEN GO TO Section 5.1 [18]. [13] ENSURE MFPT designated for startup has been tested and ready for start up per 1, 2-80-2/3-1 PRIOR to proceeding with the next step. U/1{) oj /if-Lui I I Initials Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 16 of 85 STARTUP No. Unit - Date _O...-..~~ 5.1 Actions to be performed prior to a reactor startup (continued) NOTES

1) Steps for MFPT startup may be performed in parallel with other activities. The MFPT trip busses shall be energized prior to entering Mode 2 (LCO 3.3.2.1 or 3.3.2) except as allowed by LeO 3.0.4. [C.1]

2) Power is placed on only ONE MFPT trip bus in Step 5.1 [14] to prevent inadvertent AFWP start.

[14] ENSURE power restored to ONLY ONE of MFPT tri.p busses on the applicable unit: (N/A breakers not applicable.) [C.1] ELECTRICAL BREAKER PUMP BREAKER NO. INITIALS BOARD POSITION 250v DC MFPT 1A 1-BKRD-46-KA/523 Battery Bd I CLOSED 1st CV

250v DC 0'iA-MFPT 18 1-BKRD-46-KA/524 Battery Bd I CLOSED 1st 250v DC MFPT 2A 2-BKRD-46-KB/523 Battery Bd 2 CLOSED 1st CV 250v DC MFPT 28 2-BKRD-46-KB/524 Battery Bd 2 CLOSED 1st CV

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 I TO REACTOR CRITICAL Rev. 0028 Page 17 of 85 STARTUP No. Unit --l- Date ~J 5.1 Actions to be performed prior to a reactor startup (continued) CAUTION Failure to reset a MFPT prior to energizing the remai"ning MFPT trip buss will initiate an ESF actuation. NOTE If 81 signal or Hi/Hi steam generator level has occurred, Reactor Trip Breakers will have to be cycled. [15] RESET MFPT energized in step 5.1 [14] above. vV1A 1st o&4f Time tJ '1!~!o3 ate 0041 6\/j{/oJ Time Date NOTE IF the remaining NON-running MFPT is not available, THENN/A step 5.1 [16] and 5.1 [17] [16] RESTORE power to remaining MFPT Trip Bus on applicable unit. (N/A breakers not applicable) ELECTRICAL BREAKER PUMP BREAKER NO. INITIALS BOARD POSITI"ON 250v DC Battery MFPT 1A 1-BKRD-"46-KA/523 Bd I CLOSED 18t CV 250v "DC Battery MFPT 1B 1-BKRD-46-KA/524 Bdl CLOSED 1st CV 250v DC Battery MFPT 2A 2-BKRD-46-KB/523 Bd 2 CLOSED 1st CV 250v DC Battery MFPT 28 2-BKRD-46-KB/524 Bd 2 CLOSED 1st CV

SQN UNIT STARTUP FROM .HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 18 of 85 STARTUP No. Unit~ 5.1 Actions to be performed prior to a reactor startup (continued) [17] RESET MFPT energized in step 5.1 [16] above. 1st Time Date CV Time Date [18] SELECT one source range channel and one intermediate range channel with the highest readings to record on NR 45. ~ [19] ENSURE audio count rate channel isin operation and selected for source range channel with highest reading. [C.11] [20] ENSURE all reactor first out alarms reset. NOTE Refer to 1-PI-OPS-000-021.1 (Unit 1) or 2-PI-OPS-000-023.1 (Unit 2) for updating the Plant Computer. [21] IF ICS is available, THEN ENSURE Plant Computer is reset and updating (NA if previously performed). [C.S] NOTE Closing of the RTB's for performance of O-SI-OPS-085-011.0 (SR4.1.3.3) is addressed in Licensing and NRC TelephoneNisit Report RIMs # S10 960521 800. [22] IF 0-SI~OPS-08.5-011.0 is out-of-frequency, THEN [22.1] CLOSE RTB's provided Group Demand counters have no known deficiencies. [22.2] PERFORM 0-SI-OPS-085-011.0 (NA if above step cannot be performed).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 19 of 85 STARTUP No. Unit -L Date ~ 5.1 Actions to be performed prior to a reactor startup (continued) [23] IF control rods were withdrawn 5 steps to prevent thermal lockup during ReS heatup, THEN INSERT control rods in accordance with 0-SO-85-1. [24] ENSURE Rod Bank Update completed by performing the following: [24.1] DEPRESS NSSS and BOP button on ICS main screen. if [24.2] DEPRESS- ROD BANK UPDATE Button AND ENSURE all bank positions are zero. GV' [24.3] DEPRESS F3 to save these rod bank positions. UV NOTE TI-28 defines fully withdrawn position. [26] IF shutdown rods are inserted, THEN PERFORM the following: [26.1] VERIFY sufficient shutdown reactivity exists USING 0-SI-NUC-000-038.0, Shutdown Margin. I~I-rf} [26.2] WITHDRAW Shutdown Rods to fully withdrawn position in accordance with 0-SO-85-1. 1st CV

SQN UNIT STARTUP FROM HO'T STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 20 of 85 STARTUP No. Unit Date --~- 5.1 Actions to be performed prior to a reactor startup (continued) [27] CONDUCT a pre-evolution briefing, stressing the following points:

Management Expectations
Limitations/Precautions
Avoid activities which distract the operators

[SQ990136PERJ

Appropriate Contingencies
Communications
Chain of Command
Requirements for conservative actions and strict compliance with written procedures when repositioning control rods. [C.11]

SRO [28] IF this start up is after a refueling outage AND Low Power Physics Testing has NOT been performed, THEN [28.1] VERIFY applicable actions in Section 5.1 completed or initiated. [28.2] GO TO Section 5.2. [29] IF this start up is after a non-refueling outage OR Low Power Physics Testing has already been completed, THEN [29.1] VERIFY applicable actions in Section 5.1 completed or initiated. [29.2] GO TO Section 5.3. [30] IF unit is to be shutdown, THEN GO TO 0-GO-7, Unit Shutdown from Hot Standby to Cold shutdown. END OF TEXT

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 21 of 85 STARTUP No. Unit - - - Date - - - 5.2 Reactor Startup with Low Power Physics Testing [1] VERIFY applicable actions in Section 5.1 completed or initiated. NOTE Steps 5.2[2] through 5.2[9] may be performed out of sequence. [2] IF anyMFPT trip buss is NOT energized, THEN [2.1] ENSURE requirements of LCO 3.0.4 are satisfied. [2.2] NOTIFY UnitSRO that LCO 3.3.2.1 (3.3.2) action 20 will apply when Mode 2 is entered. [3] ENSURE Appendix B, Mode 3 to Mode 2, 1 Review and Approval has been completed to ensure all restraints to Mode 2, 1 entry have been resolved and approvals for mode change granted. SM [4] BLOCK the Source Range High Flux At Shutdown alarm: [4.1] PLACE both HI FLUX AT SHUTDOWN switches on panel M-13 to BLOCK position. [4.2] VERIFY annunciator XA-55-4B, window C-1, SOURCE RANGE HIGH SHUTDOWN FLUX ALARM is LIT.[C.2] BLOCK o [5] VERIFY greater than or equal to 0.5 cps on highest reading SR instrument. o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 22 of 85 STARTUP No. Unit Date - - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) NOTE The following count rates may be used as a reference during the approach to criticality. [6] RECORD SR count rates from two of the following: [C.2] (NIA instruments not used) XI-92~5001A (N31) cps XI-92-5002A (N32) cps OR XI-92-5001 B (N31 ) _ _ _cps XI-92-5002B (N32) _ _ _cps Date Time CAUTION After refueling, NIS indications may be inaccurate until calibration at higher power levels. Therefore, NIS calibration procedures will reduce PRM trip setpoints from 109 to 60% to ensure that excore detectors do NOT contribute to an overpower condition. (Rod Stop will remain at 103% ). ReS loop !:lT indicators should" be used for power indication below 30%. [7] ENSURE Power Range high flux trip setpoints reduced to 60% in accordance with following: [C.3]

1,2-SI-ICC-092-N41.1 0
1,2-SI-ICC-092-N42.2 0
1,2-SI-ICC-092-N43.3 0
1,2-SI-ICC-092-N44.4 0 Instrument Maintenance Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 23 of 85 STARTUP No. Unit - - - Date - - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [8] ENSURE PRM calibration values set to startup values. [C.3] Reactor Engineer Time Date NOTE O-RT-NUC-OOO-003.0, Low Power Physics Testing is performed by RxEngineering concurrently with this procedure. [9] RECORD estimated critical position calculated in accordance with 0-RT-NUC-OOO-003.0, Low Power Physics Testing. Estimated critical position: steps on bank Boron concentration: ppm Initials Time Date [10] VERIFY Steps 5.2[1] through 5.2[9] completed. [11] IF actual RCS boron concentration does NOT approximately equal estimated critical boron concentration determined in O-RT-NUC-OOO-003.0, THEN [11.1] DETERMINE the appropriate boration/dilution requirements to achieve estimated boron conc. 0 [11.2] DILUTE/BORATE in accordance withO-SO-62-7 to the estimated critical boron concentration. [C.12] 0 [11.3] OPERATE pressurizer heaters/spray as necessary to equalize boron concentration (within 50 ppm) between reactor coolant loops and the pressurizer. [C.12] 0 [11.4] WHEN sufficient mixing has occurred, THEN OBTAIN a new boron sample. 0 [11.5] ENSURE actual boron concentration is approximately equal to the estimated critical boron concentration.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 24 of 85 STARTUP No. Unit - - - Date - - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [12] RECORD minimum and maximum rod positions corresponding to +/- 1000 pcm ALLOWABLE LIMITS (Tech Spec Limit) determined by 0-SI-NUC-000-001.0, Estimated Critical Conditions. [C.11] Minimum allowable rod position steps on bank Maximum allowable rod position steps on bank Initials Time Date [13] VERIFY all shutdown rods are fully withdrawn in accordance with O-SI-OPS-OOO-004.0, Surveillance Requirements Performed on Increased Frequency with no Specific Frequency, within 15 minutes prior to withdrawing control rods. Time Date NOTE SR 4.1.1.4.a required verifying lowest T-avggreater than or equal to 541°F within 15 minutes prior to achieving criticality. [14] IF 0-SI-SXX-068-127.0 is NOT in progress, THEN INITIATE applicable sections of 0-SI-SXX-068-127.0 to satisfy SR 4.1.1.4.a., Minimum Temperature For Criticality.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 25 of 85 STARTUP No. Unit - - - Date - - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [15] NOTIFY onsite personnel of reactor startup over PIA system. 0 CAUTION Avoid operations that could produce sudden changes of temperature or unplanned boron -concentration changes during approach to criticality or low power. NOTES

1) Nuclear instrumentation shall be monitored very closely for indications of unplanned reactivity rate of change. [C.11]

2) Activities that can distract operators and supervisors involved with reactor startup, such as shift turnover and surveillance testing during approach to criticality, SHALL BE avoided. [C.12]

3) ICS points N0031A, N0032A, N0035A, and N0036A may be used as an aid for monitoring NIS indications.

[16] MONITOR nuclear instruments during approach to criticality: [16.1] MONITOR source range and intermediate range NIS to identify potential reactivity anomalies. [C.11] D [16.2] IF desired to place NR-45 recorder in fast speed, THEN ADJUST chart speed to high.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 26 of 85 STARTUP No. Unit Date - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) CAUTION Do NOT exceed a steady startup rate of +1 DPM. NOTE The unit enters Mode 2 when the control banks are first withdrawn. [17] INITIATE a reactor startup by performing the following: [17.1] RECORD both source range readings for ICRR base counts. N - - . - - . -CPS N - -CPS Initials [17.2] RECORD intermediate range readings. N-35 N-36

                          - - - 0/0                         - - - 0/0 Initials

[17.3] CALCULATE initial source range count doubling value USING Appendix C. MODE 2 [17.4] INITIATE withdrawal of control banks in accordance with 0-80-85-1 to first stop point: CONTROL BANK A 128 STEPS [17.5] ENSURE Mode 2 entry is logged (log entry may be performed out of sequence later). o

SQN *UNIT STARTUP FROM HOT STANDBY O-GO-2 UnitO TO REACTOR CRITICAL Rev. 0028 Page 27 of 85 STARTUP No. Unit - - - Date - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [18] WHEN control bank A is at 128 steps, THEN PERFORM the following: [18.1] STOP rod withdrawal. [18.2] WAIT for approximately two minutes. [18.3] NOTIFYRx Engineering to perform ICRR calculation in accordance with 0~RT-NUC-000-003.0. [C.11] CAUTION Lowest loop T-avg must be verified greater than or equal to 541°F usingO-SI-SXX~068-127.0within 15 minutes prior to achieving criticality. NOTES

1) Approximately five to seven count doublings are expected to result in criticality.

However, criticality should be anticipated at any time.

2) Proper bank overlap must be verified using 0-80-85-1 as each successive rod bank is withdrawn.

[19] WHEN concurrence obtained from Rx Engineering, THEN INITIATE rod withdrawal to first count doubling (determined in App. C) USING 0-80-85-1. o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 28 of 85 STARTUP No. Unit Date 5.2 Reactor Startup with Low Power Physics Testing (continued) NOTE Steps 5.2[20] and 5.2[21] may be repeated as necessary if rod motion is stopped prior to reaching doubling value. [20] WHEN any of the following conditions are met:

Source range count rate is approximately equal to first doubling value determined in Appendix C OR
Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR

Operators orRx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DODD

[21] IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor concurrence is o*btained to resume, THEN RESUME rod withdrawal to first count doubling USING 0-80-85-1. DODD [22] IF source range count rate has reached or exceeded first doubling, THEN PERFORM the following: [22.1] ENSURE rod motion STOPPED. [22.2] WAIT approximately 2-3 *minutes to allow count rate to rise. [22.3] NOTIFY Rx Engineering to perform leRR calculations in accordance with 0-RT-NUC-000-003.0. [C.11] 0 [22.4] DETERMINE new count doubling range USING Appendix C.

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 29 of 85 STARTUP No. Unit Date 5.2 Reactor Startup with Low Power Physics Testing -(continued) [23] IF ICRR plot indicates criticality will fall outside

                 +/- 1000 pcm ECC termination band, THEN

[23.1] NOTIFY SM and OutyPlant Manager. [23~2] EVALUATE if ECC should be recalculated prior to continuing startup. [23.3] IF startup must be aborted, THEN PERFORM Appendix 0, Actions if Reactor Startup Must Be Aborted. D [24] WHEN concurrence obtained from Rx Engineering, THEN INITIATE rod withdrawal to second doubling range (determined in App. C) USING 0-SO-85-1. D NOTE Steps 5.2[25] and -5.2[26] may be repeated as n-ecessary if rod motion is stopped prior to reaching doubling range. [25] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds second doubling range determined -in Appendix C OR
Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR

Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DODD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 30 of 85 STARTUP No. Unit Date - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [26] IF rod motion was stopped prior to reaching doubling ra"nge AND Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal to second doubling range USING 0-SO-85-1. DODD [27] IF source range count rate has reached or exceeded second doubling range, THEN PERFORM the following: [27.1] ENSURE rod motion STOPPED. [27.2] WAIT approximately 2-3 minutes to allow count rate to rise. [27.3] NOTIFY Rx Engineering to perform ICRR calculations in accordance with 0-RT-NUC-000-003.0. [C.11] 0 [27.4] DETERMINE new count doubling range USING Appendix C. [28] IF ICRR plot indicates criticality will fall outside

               +/- 1000 pcm ECC termination band, THEN

[28.1] NOTIFY SM and Duty Plant Manager. [28.2] EVALUATE if EGG should be recalculated prior to continuing startup. [28.3] IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted. D [29] IF leRR plot trend indicates acceptable EGC, THEN INITIATE rod withdrawal to third doubling range (determined in App. G) USING 0-80-85-1. D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 31 of 85 STARTUP No. Unit - - - Date - - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) NOTE Steps 5.2[30] and 5.2[31] may be repeated as necessary if rod motion is stopped prior to reaching doubling range. [30] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds third doubling range determined in Appendix C OR
Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR

Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DODO

[31] IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor concurrence is obtaine*d to resume, THEN RESUME rod withdrawal to third doubling range USINGO-SO-85-1. DODD [32] IF source range count rate has reached or exceeded third doubling range, THEN PERFORM the following: [32.1] ENSURE rod motion STOPPED. [32.2] WA*IT approximately 2-3 minutes to allow count rate to rise. [32.3] NOTIFYRx Engineering to perform leRR calculations in accordance with 0-RT-NUC-000-003.0. [C.11] 0 [32.4] DETERMINE new count doubling range USING Appendix C.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 32 of 85 [33.1] NOTIFY SM and Duty Plant Manager. [33 .2] EVALUATE if EGG should be recalculated prior to continuing startup. [33.3] IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted. 0 [34] IF ICRR plot trend indicates acceptable ECG, THEN INITIATE rod withdrawal USING 0-SO-85-1 to fourth doubling range (App. G) or criticality. D NOTE Steps 5.2[35] through 5.2[37] may be repeated as necessary if rod motion is stop*ped prior to reaching doubling range or criticality. [35] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds fourth doubling range determined in Appendix C OR
Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR

Bank D rods reach fully withdrawn position OR
Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DODD

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 33 of 85 STARTUP No. Unit Date - - - - 5.2 . Reactor Startup with Low Power Physics Testing (continued) [36] IF reactor is critical, THEN GO TO Step 5.2[59] (N/A Steps 5.2[37] through 5.2[58]). [37] IF ALL of the following conditions are met:

rod motion was stopped prior to reaching doubling range or criticality
Bank D rods are below fully withdrawn position
Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal USING 0-SO-85-1 to fourth doubling range or criticality (whichever comes first). DODD

[38] IF source range count rate has reached or exceeded fourth doubling range, THEN PERFORM the following: [38.1] ENSURE rod motion STOPPED. [38.2] WAIT approximately 2-3 minutes to allow count rate to rise. [38.3] NOTIFY Rx Engineering to perform ICRR calculations in accordance with 0-RT-NUC-000-003.0. [C.11] 0 [38.4] DETERMINE new count doubling range US.ING Appendix C. [39] IF reactor is subcritical with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical with Rods Fully Withdrawn. 0

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 34 of 85 STARTUP No. Unit Date - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [40] IF IGRR plot indicates criticality will fall outside

                 +/- 1000 pcm EGG termination band, THEN

[40.1] NOTIFY SM *andDuty Plant Manager. [40.2] EVALUATE if EGG should be recalculated prior to continuing startup. [40.3] IF startup mustbe aborted, THEN PERFORM Appendix 0, Acti*ons if Reactor Startup Must Be Aborted. 0 [41] IF IGRR plot trend indicates acceptable EGG, THEN INITIATE rod withdrawal USING 0-SO-85-1 to fifth doubling range (App. G) or criticality. D NOTE Steps 5.2[42] throu.gh 5.2[44] may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality. [42] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds fifth doubling range determined in Appendix G OR
Bank D rods reach fully withdrawn position OR
Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DDDD

[43] IF reactor is critical, THEN GO TO Step 5.2[59] (N/A Steps 5.2[44] through 5.2[58]).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 35 of 85 STARTUP No. Unit - - - Date - - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [44] IF ALL of the following conditions are met:

rod motion was stopped prior to reaching doubling range or criticality
Bank D rods are below fully withdrawn position
Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal USING 0-SO-85-1 to fifth *doubling range or criticality (whichever comes first). DODO

[45] IF source range* count rate has reached or exceeded fifth doubling range, THEN PERFORM the following: [45.1] ENSURE rod motion STOPPED. [45.2] WAIT approximately 2-3 minutes to allow count rate to rise. [45.3] NOTIFY Rx Engineering to perform ICRR calculations in accordance with O-RT-NUC-000-003.0. [C.11] 0 [45.4] DETERMINE new count doubling range USING Appendix C. [46] IF reactor is subcritical with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical with Rods Fully Withdrawn. o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 36 of 85 STARTUP No. Unit Date --"-' _ 5.2 Reactor Startup with Low Power Physics Testing (continued) [47] IF ICRR plot indicates criticality will fall outside

                 +/- 1000 pcm ECG termination band, THEN

[47.1] NOTIFY SM and Duty Plant Manager. [47.2] EVALUATE if EGC should be recalculated prior to continuing startup. [47.3] IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted. D [48] IF ICRR plot trend indicates acceptable ECC, THEN INITIATE rod withdrawal USING 0-SO-85-1 to sixth doubling range (App. G) or criticality. D NOTE* Steps 5.2[49] through 5.2[51] may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality. [49] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds sixth doubling range determined in Appendix C OR
Bank 0 rods reach fully withdrawn position OR
Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DDDD

[50] IF reactor is critical, THEN GO TO Step 5.2[59] (N/A Steps 5.2[51]through 5.2[58]).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 37 of 85 STARTUP No. Unit - - - Date - - - - 5'.2 Reactor Startup with Low Power Physics Testing (continued) [51] IF ALL of the following conditions are met:

rod motion was stopped prior to reaching doubling range or criticality
Bank D rods are below fully withdrawn position
Unit Supervisor concurrence is obtaine*d to resume, THEN RESUME rod withdrawal USING 0-SO-85-1 to sixth doubling range or criticality (whichever comes first). DODD

[52] IF source range count rate has reached or exceeded sixth doubling range, THEN PERFORM the following: [52.1] ENSURE rod motion STOPPED. [52.2] WAIT approximately 2-3 minutes to allow count rate to rise. [52.3] NOTIFY RxEngineeringto perform ICRR calculations in , accordance with 0-RT-NUC-000-003.0. [C.11] D [52.4] DETERMINE new count doubling range USING Appendix C. [53] IF reactor is subcritical with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical with Rods Fully Withdrawn. D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 38 of 85 STARTUP No. Unit - - - Date ------ 5.2 Reactor Startup with Low Power Physics Testing (continued) [54] IF IGRRplot indicates criticality will fall outside

                  +/- 1000 pcm EGG termination band, THEN

[54.1] NOTIFY SM and Duty Plant Manager. [54.2] EVALUATE if ECG should be recalculated prior to continuing startup. [54.3] IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted. 0 [55] IF IGRR plottrend indicates acceptable EGG, THEN INITIATE rod withdrawal USINGO~SO-85-1 to seventh doubling range (App. G) or criticality. o NOTE Steps 5.2[56] through 5.2[58] may be repeated as*necessary if rod motion is stopped prior to reaching doubling range or criticality. [56] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds seventh doubling range determined in Appendix G OR
Bank D rods reach fully withdrawn position OR
Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DODD

[57] IF reactor is critical, THEN GO TO Step 5.2[59] (N/A Step 5.2[58]).

SQN UNIT STARTUp* FROM HOT STANDBY O-GO-2 UnitO TO REACTOR CRITICAL Rev. 0028 Page 39 of 85 STARTUP No. Unit - - - Date - - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [58] IF ALL of the following conditions are met:

rod motion was stopped prior to reaching doubling range or criticality
Bank 0 "rods are below fully withdrawn position
Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal USING 0-SO-85-1 to seventh doubling range or criticality (whichever comes first). 0 0 0 0

[59] IF any of the following conditions exist:

critical conditions cannot be achieved within the +/-1 OOOpcm allowable limits OR
critical conditions cannot be achieved above rod insertion limit OR
reactor startup must be aborted for other reasons, THEN PERFORM the following to abort rea.ctof startup: [C.11]

[59.1] STOP rod withdrawal. [59.2] INITIATE insertion of control banks. [59.3.] PERFORM Appendix 0, Actions if Reactor Startup Must Be Aborted. o [59.4] DO NOT CONTINUE this section.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028

                                                              *Page 40 of 85 STARTUP No.                               Unit                          Date - - -

5.2 Reactor Startup with Low Power Physics Testing (continued) [60] IF reactor is subcritical with Bank D rods at fully withdrawn position, THEN PERFORM Ap.pendix E, Actions if Reactor is Subcritical with Rods Fully Withdrawn. D [61] IF reactor is critical with SUR less than 0.3 DPM AND intermediate range NIS is less than P-6 (1 X 10-4 %), THEN PERFORM the following: [61.1] IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive SUR of approximately 0.3 DPM. [61.2] IF Bank D rods have reached fully withdrawn position AND Rx Engineering concurs withRCS dilution, THEN PERFORM RCS dilution (as recommended by Rx Eng) to establish positive SUR of approx. 0.3 DPM USING 0-SO-62-7.

SQN UNIT STARTUP FROM HOT STANDBY* 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 41 of 85 STARTUP No. Unit Date 5.2 Reactor Startup with Low Power Physics Testing (continued) IStart of Critical Step(s) NOTES

1) Blocking the SRM reactor trip with [HS-92-5001] and [HS-92-50021 will disable the detector outputs and remove the audio count rate signal.

2) Step 5.2[62] may be performed at time of criticalit¥, if required. Source range reactor trip must be BLOCKED before trip setpoints of 10 cps.

[62] WHEN annunciator XA-55-4A, window D-2 P-6 INTERMEDIATE RANGE is LIT, THEN [C.2] PERMISSIVE [62.1] RECORD both source range readings. N - -CPS N - -CPS Initials [62.2] RECORD both intermediate range readings. N - -%RTP N - -%RTP Initials [62.3] VERIFY a minimum of one IRM channel greater than or equal to 1 X 10 -4 % RTP. D [62.4] BL*OCK source range reactor trip by momentarily placing [HS-92-5001] and [HS-9.2-5002] SRM TRIP RESET-BLOCK P-6 handswitches to BLOCK. Initials Date Time

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 42 of 85 STARTUP No. Unit Date - - - - 5.2 Reactor Startup with Low Power Physics Tes~ing (continued) [62.5] VERIFY annunciator XA-55-4A, window C-1 SOURCE RANGE TRAINS A .& B TRIP BLOCK is LIT. D IEnd of Critical Step(s) [62.6] SELECT NR 45 to record one intermediate range channel and one power range channel. [62.7] ADJ'UST NR 45 chart speed as desired. (N/A is no change needed.) D [63] ENSUR*EPA announcement made to notify plant personnel when the reactor is critical. D NOTE When T-avg is less than 551°F and Tavg - Tref deviation alarm is lit, SR 4.1.1.4.b requires verifying lowest T-avg greater than or equal to 541°F at least once per 30 minutes. [64] IF Tavg - Tref deviation alarm [M-5A window C-6] is LIT AND T-avg is less than 551°F, THEN PERFORM 0-SI-SXX-068-127.0 to satisfy SR 4.1.1.4.b, Minimum Temperature For Criticality.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 43 of 85 STARTUP No. Unit Date - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [65] RAISE reactor power to approximately 1 X 10-3% : [65.1] IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive S*UR of approximately 0.5 DPM(not to exceed 1 DPM). [65.2] IF Bank D rods have reached fully withdrawn position AND Rx Engineering concurs with RCS dilution, THEN PERFORM RCS dilution (as recommended by Rx Eng) to establish positive SUR ofapprox. 0.5 DPM USING 0-SO-62-7. [65.3] WHEN intermediate rangeNls indicate approximately 1 X 10-3% , THEN PERFORM the following: [65.3.1] STABILIZE reactor power using control rods. [65.3.2] RECORD critical data indicated below. Power Level: N -%RTP N-36_ _0/0 RTP Rod Position: RCS Boron concentration Bank Step ppm Loop TAVG: 1 2 3 4 Initials Date Time [66] MAINTAIN reactor power stable with control banks above *Iow insertion limit USING rod movement or boration/dilution to compensate for Xenon. o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 44 of 85 STARTUP No. Unit Date - - - 5.2 Reactor Startup with Low Power Physics Testing (continued) [67] COORD.INATE with Reactor Engineering to perform Physics Testing USING O-RT-NUC-OOO-003.0. 0 NOTE If MSIVs are CLOSED, the reactor should be shut down to allow warming steam lines. [68] IF startup is to be discontinued OR reactor startup was perf'ormed with MSIVs closed, THEN GO TO 0-GO-6, Power Reduction From 30% Reactor Power to Hot Standby. [69] IF start up is to continue with one or both MFPTs available, THEN [69.1] ENSURE Steps 5.1 [13] through 5.1 [15] have been completed for applicable pump(s). [69.2] VERIFY other applicable actions Section 5.2 completed or initiated. [69.3] GO TO 0-GO-3, Power Ascension From Reactor Critical to Less Than 5% Reactor Power. [70] IF start up is to continue with NO MFPT available, THEN [70.1] MARK Steps 5.1[13] through 5.1[17] as "N/A". END OF TEXT

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 45 of 85 STARTUP No. Unit - - - Date - - - 5.3 Reactor Startup without Physics Testing [1] VERIFY applicable actions in Section 5.1 completed or initiated. NOTE Steps 5.3[3] through 5.3[8] may be performed out ofsequence. [2] IF any MFPT trip buss is NOT energized, TH*EN [2.1] ENSURE requirements of LCO 3.0.4 are satisfied. [2.2] NOTIFY Unit 8RO that LCO 3.3.2.1 (3.3.2) action 20 will apply when Mode 2 is entered. [3] ENSURE Appendix* B, Mode 3 to Mode 2, 1 Review and Approval has been completed to ensure all restraints to Mode 2, 1 entry have been resolved and approvals for mode change granted. 8M [4] BLOCK Source Range High Flux At Shutdown alarm: [4.1] PLACE BOTH HI FLUX AT SHUTDOWN switches on M-13 to the BLOCK position. [4.2] VERIFY annunciator XA-55-4B window C-1 , SOURCE RANGE HIGH SHUTDOWN FLUX ALARM is LIT.[C.2]. CLOCK o [5] VERIFY greater than or equal to 0.5 cps on the highest reading SR instrument. o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 46 of 85 STARTUP No. Unit _ Date - - - 5.3 Reactor Startup without Physics Testing (continued) NOTE The following count rates may be used as a reference during the approach to criticality. [6] RECORD SR count rates from two of the following: [C.2] (N/A instruments not used) XI-92-5001A (N31) cps XI-92-5002A (N32) cps OR XI-92-5001 B (N31 ) _ _ _cps XI-92-5002B (N32) _______cps Time Date [7] IF conditions exist which could cause Power RangeNIS indications to be non-conservative, THEN ENSURE Power Range high flux trip setpoints reduced to 60% in accordance with the following: [C.3]

1,2-SI-ICC-092-N41.1 0
1,2-SI-ICC-092-N42.2 0
1,2-SI-ICC-092-N43.3 0
1,2-SI-ICC-092-N44.4 0 Instrument Maintenance Date Time

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 47 of 85 . STARTUP No. Unit - - - Date - - - - 5.3 Reactor Startup without Physics Testing (continued) [8] VERIFY the estimated critical position calculated in accordance with O-SI-NUC-000-001.0, Estimated Critical Conditions. Estimated critical position: steps on bank Assumed boron concentration: ppm Initials Time Date STA Time Date [9] VERIFY* Steps 5.3[1] through 5.3[8] completed. [10] IF estimated critical boron concentration does NOT approximately equal actual boron concentration, THEN [10.1 ] DETERMINE the appropriate boration/dilution requirements to achieve criticality within acceptable limits. D [10.2] DILUTE/BORATE in accordance with 0-80-62-7 to the estimated critical boron concentration. [C.12] 0 [10.3] OPERATE pressurizer heaters/spray as necessary to equalize boron concentration (within 50 ppm) between reactor coolant loops and the pressurizer. [C.12] D [to.4] WHEN sufficient mixing has occurred, THEN OBTAIN a new boron sample. D [10.5] ENSURE actual boron concentration is approximately equal to the estimated critical boron concentration.

SQN UN*IT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 48 of 85 STARTUP No. - - - - Unit - - - Date - - - - 5.3 Reactor Startup without Physics Testing (continued) NOTE Termination limits are associated with +/- 750 pcm tolerance band. These values are within minimum and maximum rod positions corresponding to Tech Spec limit of +/- 1000 pcm (Minimum and Maximum Allowable Limits). Termination limits shall be used by Reactor Engineering and Operations to determine whether approach to criticality should be terminated and a new ECC calculated. ECC must be terminated if Minimum or Maximum Allowable Limits (corresponding to Tech Spec limit of +/- 1000 pcm) are approached. [11] RECORD upper and lower rod position limits corresponding to

               +/- 750 pcm Termination Band as determined by 0-SI-NUC-000-001..0, Estimated Critical Conditions.

Upper termination rod position steps on bank Lower termination rod position steps on bank Initials Time Date [12] RECORD minimum and maximum rod positions corresponding to +/- 1000 pcm ALLOWABLE LIMITS (Tech Spec Limit) determined by 0-SI-NUC-000-001.0, Estimated Critical Conditions. [C.11] Minimum allowable rod position steps on* bank Maximum allowable rod position steps on bank Initials Time Date [13] VERIFY all shutdown rods are fully withdrawn in accordance with 0-SI-OPS-000-004.0, Surveillance Requirements Performed on In'creased Frequency with no Specific Frequency, within 15 minutes prior to withdrawing control rods. Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 UnitO TO REACTOR CRITICAL Rev. 0028 Page 49 of 85 STARTUP No. Unit - - - Date - - - - 5.3 Reactor Startup without Physics Testing (continued) NOTE SR 4.1.1.4.a requires verifying lowest T-avggreater than _or equal to 541°F within 15 minutes prior to achieving criticality. [14] IF O-SI-SXX-068-127.0 is NOT in progress, THEN INITIATE applicable sections of O-SI-SXX-068-127.0 to satisfy SR 4.1.1.4.a., Minimum Temperature For Criticality. [15] NOTIFY onsite personnel of reactor startup over PIA system. D CAUTION Avoid operations that-could produce sudden changes of temperature or unplanned boron concentration changes during approach to criticality or low power. NOTES

1) Nuclear instrumentation shall be monitored very closely for indications of unplanned reactivity rate of change. [C.11]

2) Activities that can distract operators and supervisors involved with reactor startup, such as shift turnover and surveillance testing during approach to criticality, SHALL BE avoided. [C.12]

3) ICS points N0031A, N0032A, N0035A, and N0036A may be used as an aid for monitoring NIS indications.

[16] MONITOR nuclear instruments during approach to criticality: [16.1] MONITOR source rang-e and intermediate range NIS to identify potential reactivity anomalies. [C.11] D [16.2] IF desired to placeNR-45 recorder in fast speed, THEN ADJUST chart speed to high.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 50 of 85 STARTUP No. Unit - - - Date - - - 5.3 Reactor Startup without Physics Testing (continued) CAUTION Do NOT exceed a steady startup rate of +1 DPM. NOTE The unit enters Mode 2 when the control banks are first withdrawn. [17] INITIATE a reactor startup by performing the following: [17.1] RECORD* both source range readings for ICRR base counts. N - -CPS N - -CPS Initials [17.2] RECORD intermediate range readings. N-35 N-36

                          - - - 0/0                          - - - 0/0 Initials

[17.3] CALCULATE initial source range count doubling value USING Appendix C. MODE 2 [17.4] INITIATE withdrawal of control banks in accordance with 0-SO-85-1 to first stop point: CONTROL BANK A 128 STEPS [17.5] ENSURE Mode 2 entry'is logged (log entry may be performed out of sequence later). o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 51 of 85 STARTUP No. Unit - - - Date - - - 5.3 Reactor Startup without Physics Testing (continued) [18] WHEN control bank A is at128 steps, THEN PERFORM the following: [18.1] STOP rod withdrawal. [18.2] WAIT for approximately two minutes. [18.3] N'OTIFY Rx Engineering to perform ICRR calculation in accordance with 0-81-NUC-OOO-001.0. [C.11] CAUTION Lowest loop T-avg must be verified greater than or equal to 541°F using 0-SI-SXX-068-127.0within 15 minutes prior to achieving criticality. NOTES

1) Approximately five to seven count doublings are expected to result in criticality.

However, criticality should be anticipated at .a*ny time.

2) Proper bank overlap must be verified using 0-80-85-1 as each successive rod bank is withdrawn.

[19] WHEN concurrence obtained from Rx Engineering, THEN INITIATE rod withdrawal to first count doubling (determined in App. C) USING 0-80-85-1. D

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 52 of 85 STARTUP No. Unit - - - Date - - - 5.3 Reactor Startup without Physics Testing (continued) NOTE Steps 5.3[20] and 5.3[21] may be repeated as necessary if rod motion is stopped prior to reaching doubling value. [20] WHEN any of the following conditions are met:

Source range count rate is approximately equal to first-doubling value determined in Appendix C OR
Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-80-85-1)

OR

Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DODD

[21] IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal to first count doubling USING 0-SO-85~1. DODD [22] IF source range count rate has reached or exceeded first doubling, THEN PERFORM the following: [22.1] ENSURE rod motion STOPPED. [22.2] WAIT approximately 2-3 minutes to allow count rate to rise. [22.3] NOTI*FYRx Engineering to perform ICRR calculations in accordance with O-SI-NUC-000-001.0. [C.11] D [22.4] DETERMINE new count doubling range USING Appendix C.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 53 of 85 STARTUP No. Unit - - - Date - - - - 5.3 Reactor Startup without Physics Testing (continu.ed) [23] IF ICRR plot indicates criticality will fall outside

                  +/- 750 pcm ECC termination band, THEN

[23.1] NOTIFY SM and Duty Plant Manager. [23.2] EVALUATE if ECC should be recalculated prior to continuing startup. [23.3] IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted. D [24] WHEN concurrence obtained from Rx Engineering, THEN INITIATE rod withdrawal to second doubling range (determined in App. C) USING 0-80-85-1. o NOTE Steps 5.3[25] and 5.3[26] may be repeated as necessary if rod motion is stopped prior to reaching doubling range. [25] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds second doubling range determined in Appendix C OR
C'ontrol bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR

Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DODD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 54 of 85 STARTUP No. Unit - - - Date - - - 5.3 Reactor Startup without Physics Testing (continued) [26] IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal to second doubling range USING 0-SO-85-1. 0000 [27] IF source range count rate has reached or exceeded second doubling range, THE*N PERFORM the following: [27.1] ENSURE rod motion STOPPED. [27.2] WAIT approximately 2-3 mi'nutes to allow count rate to rise. [27.3] NOTIFY Rx Engineering to perform ICRR calculations in accordance with 0-SI-NUC-000-001.0. [C.11] 0 [27.4] DETERMINE new count doubling range USING Appendix C. [28] IF ICRR plot indicates criticality will fall outside

               +/- 750 pcm ECC termination band, THEN

[28.1] NOTIFYSM and Duty Plant Manager. [28.2] EVALUATE if ECC should be recalculated prior to continuing startup. [28.3] IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted. 0 [29] IF ICRR plot trend indicates acceptable ECC, THEN IN'ITIATE rod withdrawal to third doubling range (determined in App. C) USINGO-SO-85-1. o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 55 of 85 STARTUP No. Unit - - - Date - - - - 5.3 Reactor Startup without Physics Testing (continued) NOTE Steps 5.3[30] and 5.3[31 ] may be repeated as necessary if rod motion is stopped prior to reaching doubling range. [30] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds third doubling range determined in Appendix C OR
Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR

Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DODD

[31] IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal to third doubling range USING 0-SO-85-1. DODD [32] IF source range count rate has reached or exceeded third doubling range, THEN PERFORM the following: [32.1] ENSURE rod motion STOPPED. [32.2] WAIT approximately 2-3 minutes to allow count rate to rise. [32.3] NOTIFY Rx Engineering to perform leRR calculations in accordance with 0-SI-NUC-000~001.0. [C.11] 0 [32.4] DETERMINE new count doubling range USING Appendix C.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 56 of 85 STARTUP No. Unit Date - - - 5.3 Reactor Startup without Physics Testing (continued) [33] IF ICRR plot indicates criticality will fall outside

                  +/- 750 pcm ECC termination band, THEN

[33~1] NOTIFY SM and Duty Plant Manager. [33.2] EVALUATE if ECC should be recalculated prior to continuing startup. [33.3] IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted. 0 [34] IF ICRRplot trend indicates acceptable ECC, THEN INITIATE rod withdrawal-USING 0-80-85-1 to fourth doubling range (App. C) or criticality. o NOTE Steps 5.3[35] through 5.3[37] may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality. [35] WHEN any of the foHowing conditions are met:

Source range count rate reaches or exceeds fourth doubling range determined in Appendix C OR
Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-80-85-1)

OR

Bank D rods reach fully withdrawn position OR
Operators or Rx Engineer determine that rod motion shoul-d be stopped THEN STOP outward rod motion. DOOD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 57 of 85 STARTUP No. Unit - - - Date - - - - 5.3 Reactor Startup without Physics Testing (continued) [36] IF reactor is critical, THEN GO TO Step 5.3[59] (N/A Steps 5.3[37] through 5.3[58]). [37] I*F ALL of the following conditions are met:

rod motion was stopped prior to reaching doubling range or criticality
Bank D rods are below fully withdrawn position
Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal USING 0-SO-85-1 to fourth doubling range or criticality (whichever comes first). DODD

[38] IF source range count rate has reached or exceeded fourth doubling range, THEN PERFORM the following: [38.1] ENSURE rod motion STOPPED. [38.2]. WAIT approximately 2-3 minutes to allow count rate to rise.* [38.3] NOTIFY Rx Engineering to perform leRR calculations in accordance with O-SI-NUC-OOO-001.0. [C.11] D [38.4] DETERMINE new count doubling range USING Appendix C. [39] IF reactor is subcritical with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical with Rods Fully Withdrawn. D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 58 of 85 STARTUP No. Unit - - - Date - - - 5.3 Reactor Startup without Physics Testing (continued) [40] IF ICRR plot indicates criticality will fall outside

                  +/- 750 pcm ECC terminati*on band, THEN

[40.1] NOTIFY SMand Duty Plant Manager. [40.2] EVALUATE ifECC should be recalculated prior to continuing startup. [40.3] IF startup must be aborted, THEN PERFO*RM Appendix 0, Actions if Reactor Startup Must Be Aborted . D [41] IF ICRR plot trend indicates acceptable ECC, THEN INITIATE rod withdrawal U5INGO-SO-85-1 to fifth doubling range (App. C) or criticality. D NOTE Steps 5.3[42] through 5.3[44] may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality. [42] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds fifth doubling range determined in Appendix C OR
Bank D rods reach fully withdrawn position OR
Operators orRx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DDDD

[43] IF reactor is critical, THEN GO TO Step 5.3[59] (N/A Steps 5.3[44] through 5.3[58]).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 59 of 85 STARTUP No. Unit Date - - - 5.3 Reactor Startup without Physics Testing (continued) [44] IF ALL of the following conditions are met:

rod motion was stopped 'prior to reaching doubling range or criticality
Bank.D rods are below fully withdrawn position
Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal USING 0-SO-85-1 to fifth doubling range or criticality (whichever comes first). DOOO

[45] IF source range count rate has reached or exceeded fifth doubling range, THEN PERFORM the following: [45.1] ENSURE rod motion STOPPED. [45.2] WAIT approximately 2-3 minutes to allow count rate to rise. [45.3] NOTIFY Rx Engineering to perform ICRR calculations in accordance with O-SI-NUC-OOO-001.0. [C.11] D [45.4] DETERMINE new Gount doubling range USING Appendix C. [46] IF reactor is subcritical with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical with Rods Fully Withdra*wn. 0

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 60 of 85 STARTUP No. Unit Date - - - 5.3 Reactor Startup without Physics Testing (continued) [47] IF IGRR plot indicates criticality will fall outside

                  +/- 750 pcm EGG termination band, THEN

[47.1] NOTIFY SM and Duty Plant Manager. [47.2] EVALUATE if EGO should be recalculated prior to continuing startup. [47.3] IF startup must be aborted, THEN PERFORM Appendix 0, Actions if Reactor Startup Must Be Aborted. 0 [48] IF IGRR plot trend indicates acceptable EGG, THEN INITIATE rod withdrawal USING 0-SO-85-1 to sixth doubling range (App. G) or criticality. o NOTE Steps 5.3[49] through 5.3[51] may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality. [49] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds sixth doubling range determined in Appendix C OR
Bank 0 rods reach fully withdrawn position OR
Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion. DODD

[50] IF reactor is critical, THEN GO TO Step 5.3[59] (N/A Steps 5.3[51] through 5.3[58]).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 61 of 85 STARTUP No. Unit - - - Date - - - - 5.3 Reactor Startup without Physics Testing (continued) [51] IF ALL of the following conditions are met:

rod motion was stopped prior to reaching doubling range or criticality
Bank D rods are below fully withdrawn position
Unit Supervisor concurrence is obtained to resume, THEN RESUME rod withdrawal USING 0-80-85-1 to sixth doubling range or criticality (whichever comes first). DDDD

[52] IF source ran'ge count rate has reached or exceeded sixth doubling range, THEN PERFORM the following: [52.1] ENSURE rod motion STOPPED. [52.2] WAIT approximately 2-3 minutes to allow count rate to rise. [52.3] NOTIFY Rx Engineering to perform ICRR calculations in accordance with 0-SI-NUC-000-001.0. [C.11] 0 [52.4] DETERMINE new count doubling range USING Appendix C. [53] IF reactor is subcriUcal with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if "Reactor is Subcritical with Rods Fully Withdrawn. D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 62 of 85 STARTUP No. Unit -~- Date - - - 5.3 Reactor Startup without Physics Testing (continued) [54] IF ICRR plot indicates criticality will fall outside

                  +/- 750 pcm ECC termination band, THEN

[54.1] NOTIFY SM and Duty Plant Manager. [54.2] EVALUATE if ECC should be recalculated prior to continuing startup. [54.3] IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted. O' [55] IF ICRR plot trend *indicates acceptable ECC, THEN INITIATE rod withdrawal USINGO-SO-85-1 to seventh doubling range (App. C) or criticality. D NOTE Steps 5.3[56] through 5.3[58] may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality. [56] WHEN any of the following conditions are met:

Source range count rate reaches or exceeds seventh doubling range determined in Appendix C OR
Bank D rods reach fully withdrawn position OR
Operators or RxEng.ineer determine that rod motion should be stopped THEN STOP outward rod motion. DODD

[57] IF reactor is critical, THEN GO TO Step 5.3[59] (N/A Step 5.3[58]).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR 'CRITICAL Rev. 0028 Page 63 of 85 STARTUP No. Unit - - - Date 5.3 Reactor Startup without Physics Testing (continued) [58] IF ALL of the following conditions are met:

rod motion was stopped prior to reaching doubling range or criticality
Bank D rods are below fully withdrawn position
Unit Supervisor concurrence is obtained to resume, THEN RES*UME rod withdrawal USING 0-SO-85-1 to seventh doubling range or criticality (whichever comes first). 0 0 0 0

[59] IF any of the following conditions exist:

critical co.nditions cannot be achieved within the +/-750 pcm termination band OR
critical conditions cannot be achieved within the +/-1 000 pcm allowable limits OR
critical conditions cannot be achieved above rod insertion limit OR
reactor startup must be aborted for other reasons, THEN PERFORM the following to abort reactor startup: [C.11]

[59.1] STOP rod withdrawal. [59.2] INITIATE insertion of control banks. [59.3] PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted. o [59.4] DO NOT CONTINUE this section.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 64 of 85 STARTUP No. ~---,-- Unit - - - Date - - - 5.3 Reactor Startup without Physics Testing (continued) [60] IF reactor is subcritical with BankO rods at fully withdrawnposition~ THEN PERFORM Appendix E, Actions if Reactor is Subcritical with Rods Fully Withdrawn. 0 [61] IF reactor is critical with SUR less than 0.3 DPM AND intermediate range NIS is less than P~6 (1 X 10-4 %), THEN PERFORM the following: [61.1] IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive SUR of approximately 0.3 DPM. [61.2] IF Bank D rods have reached fully withdrawn position AND Rx Engineering concurs with RCSdilution, THEN PERFORM RCS dilution (as recommended by Rx Eng) to establish positive SUR of approx. 0.3 OPM USING 0-80-62-7.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 65 of 85 STARTUP No. Unit - - - Date - - - 5.3 Reactor*Startup without Physics Testing (continued) IStart ofCritical Step(s) NOTES

3) Blocking the SRM reactor trip with [HS-92-50011 and [HS-92-50021 will disable the detector outputs and remove the audio count rate signal.

4) Step 5.3[62] may be performed at time of criticality, if required. Source range reactor trip must be BLOCKED before trip setpoint of 105 cps.

[62] WHEN annunciator XA-55-4A, window 0-2 P-6 INTERMEDIATE RANGE PERMISSIVE is LIT, THEN [C.2] [62.1] RECORD both source range readings. N - -CPS N - -CPS Initials [62.2] RECORD both intermediate range readings. N-35 %RTP N-36 %RTP Initials [62.3] VERIFY a minimum of one IRMchannel greater than or equal to 1 X 10-4 % RTP. 0 [62.4] BLOCK source range reactor trip by momentarily placing [HS-92-50011 and [HS-92*~50021 SRM TRIP RESE*T-BLOCK P-6 handswitches to BLOCK. Initials Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO -REACTOR CRITICAL Rev. 0028 Page 66 of 85 Date - - - 5.3 SOURCE RANGE TRAINS A& B TRIP BLOCK is LIT. o IEnd of Critical Step(s) [62.6] SELECT NR 45 to record one intermediate range channel and one power ran-ge channel. D [62.7] ADJUST NR45 chart speed as desired. (N/A if no change needed). D [63] ENSURE PA announcement made to notify plant personnel when the reactor is critical. o NOTE When T-avg is less than 551°F and Tavg - Tref deviation alarm is lit, SR 4.1.1.4.b requires verifying lowest T-avg greater than or equal to 541°F at least once per 30 minutes. [64] IF Tavg - Tref deviation alarm [M-5A window C-6] is LIT AND T-avg is less than 551°F, THEN PERFORM O-SI-SXX-068-127.0 to satisfy SR 4.1.1.4.b, Minimum Temperature For Criticality.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 67 of 85 STARTUP No. Unit - - - Date - - - - 5.3 Reactor Startup without Physics Testing (continued)

    ,[65]    RAISE reactor power to approximately 1X 10-3 %:

[65.1] IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive SUR of approximately 0.5 DPM (not to exceed 1 DPM). [65.2] IF Bank D rods have reached fully withdrawn position AND Rx Engineering concurs with RCS dilution, THEN PERFORM RCS dilution (as recommended by Rx Eng) to establish positive SUR of approx. 0.5 DPM USING 0-SO-62-7. [65.3] WHEN intermediate range NIS indicate approximately 1 X 10-3 %, THEN PERFORM the following: [65.3.1] STABILIZE reactor power using control rods. [65.3.2] RECORD critical data indicated below. Power Level: N - -%RTP N - -%RTP Rod Position: RCS Boron concentration Bank Step ppm Loop TAVG: 1 2 3 4 Initials Time Date [66] VERIFY control rods above rod ins*ertion limit USING 1,2-SI-OPS-OOO-002.0, Shift Log. o [67] MAINTAIN reactor power stable with control banks above low insertion limit USING rod movement or boration/dilution to compensate for Xenon. o

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 68 of 85 STARTUP No. Unit - - - Date - - - 5.3 Reactor Startup without Physics Testing (continued) NOTE If MSIVs are CLOSED, the reactor should be shut down to allow warming steam lines. [68] IF startup is to be discontinued OR reactor startup was performed with MSIVs closed, THEN GO TO 0-GO-6, Power Reduction From 30% Reactor Power to Hot Standby. [69] IF start up is to continue with one or bothMFPTs available, THEN [69.1] ENSURE Steps 5.1[13] through 5.1[15] have been completed for applicable pump(s). [69.2] VERIFY other applicable actions in Section 5.3 completed or initiated. [69.3] GO TO 0-GO-3, Power Ascension From Reactor Critical to Less Than 5% Reactor Power. [70] IF start up is to continue with NO MFPT available, THEN [70.1] MARK Steps 5.1[13] through 5.1[17] as "N/A". [70.2] VERIFY other applicable actions in Section 5.3 completed or initiated. [70.3] GO TO 0-GO-3, Power Ascension From Reactor Critical to Less Than 5% Reactor Power. END OF TEXT

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 69 of 85 6.0 RECORDS Completed copies shall be transmitted to the Operations Superintendent's Secretary.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 UnitO TO REACTOR CRITICAL Rev. 0028 Page 70 of8S Appendix A (Page 1 of 1) DELETED 1.0 DELETED

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 71 of 85 Appendix B (Page 1 of 8) MODE 3 TO MODE 2,1 REVIEW AND APPROVAL STARTUP No. Unit ------'-- Date~j 1.0 MODE 3 TO 2,1 REVIEW AND APPROVAL NOTE Steps in this Appendix may be performed out of sequence, except for those steps that pertain to the Operations Superintendent Hold Point. [1] PRIOR to entering Mode 2, 1, an SRO shall review the following: NOTE Mode 3 to Mode 2, 1 Checklist and Reactor Trip Breaker Checklist are to be attached to this instruction. A. Mode 3 to Mode 2,1 Checklists from the responsible sections and DETERMINE thatthe required surveillance testing for Mode 2 entry has been co pleted tJ{;Vo Time

                                                                                   ~0~ox Da e B. Reactor Trip Breaker Closure C' ecklists from the responsible sections and DETE*RMINE that required surveillance testing for mode change has been completed.                           l 00YO    Of &J,1o~

Time ~

c. Active clearances for mode ch nge restraints. .jO].

I 1 C2?'1 0 Time D. TACF Books for outstanding alternations on systems prior to declaring a T.S. system or comp: ent 0 e ble. [C.10]

                                                          !                01 ~u   at /yy~~

Time ~

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 72 of 85 Appendix B (Page 2 of 8) STARTUP No. Unit ----1('---- J Date~'I 1.0 MODE 3 TO 2,1 REVIEW AND APPROVAL (continued) E. O-TI-EXX-OOO-001.0, Electrical Jumper Control Log to determine if any potential T. S. restriction exists which would prevent a mode chang

f1jJ i2ill tJ/ Iv j, .;

1/ Time ~ F. Active Procedures Book to determine equipment status that may be abnormal. nr ~. iGU

G. OPDP-4, Annunciator Disablement Log for alarms affecting operability of equipment required for mode change. nql() OJ

                                                                             ~~
                                                                                  ~ .. ~'J Time H. O-PI-OPS-301-001.0Plant Computer Point Disablement Log for alarms affecting operability of equipment required for mode change.

61 /v;<,. / uf

                                                                             ~v I. Board walkdown is completed to verify proper equipment alignment.

(Refer to appropriate CRO and GATC Pis for guidance) [C.10] (j1VJ * ( //ylJ Time ~

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 73 of 85 Appendix B (Page 3 of 8) 1.0 STARTUP No. Unit + MODE 3 TO 2,1 REVIEW AND APPROVAL (continued) Date~ NOTE Tech Spec and TRM LCO 3.0.4 govern entering Mode 2 if,any LCO requirement applicable in Mode* 2is not met. Therefore, mode change is not allowed while in a Tech Spec or TRMaction UNLESS the exceptions and/or allowances stated in LCO 3.0.4 can be applied. J. RE*VIEW all Tech Spec and TRM Actions which have been entered on the affected unit and common equipment to verify that mode change is acceptable. SRO Time Date SRO Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 74 of 85 Appen.dix B (Page 4 of 8) STARTUP No. Unit ~ 2.0 DEPARTMENT MANAGERS REVIEW 2.1 Periodic Test Coordinator: . [1 ] ENSURE that all surveillance requirements for m de 2 entry are updated and included Withiit e ~ode c!han checklist. . i 7t i dic Te

                                                      .       /

oordinator

                                                                     &/0 Time
                                                                                °tXr/o ate f

[2] ENSURE that all surveilianceV:eqUirements for Reactor Trip Breaker Closure Checklist are updated and included within the checklist. [e.9] OZIO PiOdlC Test Coordinator Time 2.2 Instrument Maintenance: [1] ENSURE Wide Range SG Level Recorders [LR-3-43A] and [LR-3-98A] are OPERABLE and SET to a range requested by the operator. (Recommended range between 80 and 90% of scale). [C.6] o<;~~ Time 4JfIOJ

                                                                                  ' at 2.3    Fire Ops Section:

[1 ] Oil % Time

                                                                                ~'f~i Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 75 of 85 Appendix B (Page 5 of 8) STARTUP No. ____ I Unit - - - - ' - - 2.4 Systems Engineering Section: [1] REVIEW of mode change checklist is complete and all surveillance requirements have met their acceptance criteria for Mode 2 entry. Shift Manager Time Date [2] REVIEW of Reactor Trip Breaker Closure Checklist is complete, all surveillance requirements have met their acceptance criteria, and all open items that affect mode change have been closed. Shift Manager Time Date NOTE The evaluation made by the Systems Engineer in the next step will prevent thermal shock to the PZR spray nozzle. [3] ENSURE PZR spray line bypass valves are throttled to maintain acceptable spray line temperature* in accordance with 0-SO-68-3. :f£JYWL&1f;t; O~5' orfr;fal System En'gineering Time ate [4] IF startup is following a refueling outage, THEN ENSURE Present Cycle Core Operating Limit Report are inserted in the unit's Technical specU/oon ~,er. C.7] r If! OGO( O~'fX 10) f ' f f f...ilsing or designee Time ate

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 76 of 85 Appendix B (Page 6of8) STARTUP No. - - - - Unit-l- Date fJ tjV;;/Ol 2.5 Maintenance Section: [1] REVIEW of mode change checklist is complete and all surveillance requirements have met their acceptance criteria for Mode 2 entry. Shift Manager Time Date [2] REVIEW of Reactor Trip Breaker Closure Checklist is complete, aH surveillance requirements have met their acceptance criteria, and all open items that affect mod"e change have been closed. Shift Manager Time Date 2.6 Chemistry Section: NOTE The following step does not require a new analysis to be performed for this startup. Routine analysis is sufficient unless there is reason to suspect chemistry has been changed. [1] ENSURE reactor coolant chemistry within limits of Technical Requirements Manual 3.4.7 as determined by the Chemical Shift Supervisor. 4 obJO* ~.J. J'nx'f;~oj Time ~v

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 77 of 85 Appendix B (Page 7 of 8) STARTUP No. Unit - - - Date --_~ 3.0 SHIFT MANAGER (SM) HOLD POINT [1] ENSURE Tech Spec and non-Tech Spec work related activities are completed or will not prohibit entry or impact continued operation in Mode 2. 8M Time Date [2] ENSURE no open DCN/ECNsthat would prohibit a mode change. (SM concurrence with the Modifications Manager or designee). SM Time Date [3] REVIEW all open work activities relative to the unit for the purpose of identifying maintenance activities that could affect system operability prior to mode change SM Time Date [4] IF any potential Tech Spec. mode constraint exists, THEN OBTAIN Operations Superintendent resolution prior to proceeding with the mode change SM Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 78 of 85 Appendix B (Page 8 of 8) STARTUP No. Unit - - - Date - - - 3.0 SHIFT MANAGER (8M) HOLD POINT (continued) [5] IF the startup follows a reactor trip or an emergency shutdown, THEN A. ENSURE cause of the trip/shutdown has been determined and will not impact Mode 2 entry. SM Time Date B. ENSURE Reactor trip report is complete. (0-TI-QXX-000-001.0, Event Critique, Post Trip Report, Equipment Root Cause and Outage Milestone PER Evaluation) SM Time Date

c. ENSURE 0-GO-12, Realignment of Secondary Equipment Following Reactor TriplTurbine Trip/Emergency shutdown, is complete.

SM Time Date 4.0 OPERATIONS SUPERINTENDENT HOLD POINT Operations Superintendent or his designee concurs and grants approval to proceed to Mode 2, 1. Operations Superintendent Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 79 of 85 Appendix C (Page 1 of 1) DETERMINING SOURCE RANGE COUNT RATE DOUBLING 1.0 CALCULATING DOUBLING RANGE NOTES

1) Source range reading shal.l be allowed to stabilize for approximately 3 minutes after each reactivity change prior to determining new stable count rate.

2) The highest reading channel should be used when determining stable count rate.

3) Doubling range is used to determine when rod motion should be stopped during approach to criticality. Criticality is expected in about 5 to 7 count rate doublings.

4) This appendix may be performed and IV'd by operators, STA, or Rx Engineers.

STABLE COUNT RATE DOUBLING RANGE INITIALS COUNT RATE (CR) CR X 1.75 = CR X 2.0 = 1st IV (Lower value not used for first doubling) End of Section

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 80 of 85 Appendix D (Page 1 of 1) ACTIONS IF REACTOR STARTUP MUST BE ABORTED STARTUP No. ~-- Unit - - - Date - - - 1.0 OPERATOR ACTIONS CAUTION If reactor trip is required, E-O should be performed instead of this appendix. [1] ENSURE all control bank rods FULLY INSERTED in accordance with 0-SO-85-1. [2] LOG Mode 3 entry in narrative log. [3] VERIFY adequate shutdown margin in accordance with 0-SI-NUC-000-038.0. Initials Time Date [4] DETERMINE and CORRECT cause of the discrepancy. o [5] WHEN reactor startup is to resume, THEN PERFORM the following: [5.1] RECALCULATE -estimated critical conditions in accordance with 0-RT-NUC-000-003.0(Startup after refueling) or 0-SI-NUC-000-001.0 (Startup after non-refueling outage). [5.2] DILUTE/BORATE in accordance withO-SO-62-7 to the estimated critical boron concentration. [C.12] [5.3] EQUALIZE boron concentration (within 50 ppm) between reactor coolant loops and pressurizer by operating pzr heaters and spray. [C.12] [5.4] R-E-INITIATE 0-GO-2. End of Document

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 81 of 85 Appendix E (Page 1 of 2) ACTIONS IF BANK D RODS REACH FULL OUT POSITION PRIOR TO CRITICALITY 1.0 OPERATOR ACTIONS NOTE Allowable upper limit for critical position may be above the fully withdrawn position on Bank D. If Reactor Engineering determines that core response is within acceptable limits, this appendix allows RCS dilution to assist in achieving criticality. [1 ] CONSULT Reactor Engineering to determine if core response is within acceptable limits. D [2] IF projected critical rod position exceeds +1000 pcm limit OR startup will be aborted due to failing to achieve criticality, THEN [2.1 ] PERFORM AppendixD, Actions if Reactor Startup Must Be Aborted. . D [2.2] DO NOT CONTINUE this appendix. D [3] ENSURE control bank D inserted to less than or equal to estimated critical position determined in O-RT-NUC-000-003.0 (Startup after refueling) or O-SI-NUC-000-001.0 (Startup after non-refueling outage). [4] DETERMINE dilution volume to increase core reactivity by 100 pcm OR as recommended by Rx Engineering. Rx Engineer gallons IV

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 UnitO TO REACTOR CRITICAL Rev. 0028 Page 82 of 85 Appendix E (Page 2 of 2) STARTUP No. Unit Date - - - 1.0 OPERATOR ACTIONS (continued) CAUTION NISindications should be carefully monitored during and following dilution. [5] PERFORM specified dHution USING 0-80-62-7. D [6] WHEN at least30 minutes has elapsed for ReS mixing AND RxEngineer concurs with resuming startup, THEN RETURN to appropriate step (based on number of doublings) in Sect. 5.2 (Startup after refueling) or Section 5.3 (Startup after non-refueling outage). D End of Document

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 83 of 85 Source Notes (Page 1 of 3) Implementing Requirements Statement Source Document Statement Verify MFWP trip bus energized before LER 328/88-014 C.1 entry into Mode 2. Revise GOI-2 to require verification of NCO 890118002 C.2 intermediate range (IR) status at LER 328/89006 approximately 20 and 25 percent, S53 890531 844 verify source range (SR) status and JRBto NRC channel check at lower power, monitor core delta Ts at low-power levels and during power escalation and compare with NIS response, and verify that the IR rod stop and trip bistables come in at the appropriate power level during power ascension. Following refueling operations SOER-90-003 C.3 relocation of NIS or modifications NCO 900107009 affecting the NIS response, provide NER 1187001 adequate reductions of trip setpoint LER 327/90011R1 and limitations of reactor power until accuracy of the NIS is verified. Also, provide alternate indications of power independent of calorimetric calculations during power ascensions. Decommitted 3/12/99 C.4 Assurance that TSC computer is reset Verbal commitment to NRC at C.S prior to startup; defines "reset" and SNP Meeting 10/04/90 "updating". (Modified C.5 permitting relaxing requirement.) Provisions to ensure that enhanced NCO 890097004 C.6 steam generator level recorders are L44 890505 805 operable in the main control room prior to entering mode 2.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev. 0028 Page 84 of 85 Source Notes (Page 2 of 3) Implementing Requirements Statement Source Document Statement Based upon the requirements of the PORC Minutes #50880 C.7 May 6, 1991 PORC meeting this 5/06/91T/891-08 verification has been added to implement the referenced Technical Specification change for the Core Operating Limits Report. Consult Reactor Engineerin*g for NER 89 0794 C.8 guidance during evolutions of unusual OER 89 3497 power maneuvers at end of core life. Provide reactor trip breaker closure U1C5 Outage Critique C.g checklists to ensure all surveillance item requirements for reactor trip breaker closure are satisfied. Revise GOI~2 to include a step signoff 118-92-045 C.10 with the TACF review, hold order review etc. section of GOI, for the Duty SOS to ensure a board walkdown to verify proper alignment is performed by a designated *SRO prior to mode change. Op*erations startup procedures should: 80ER 88-02 C.11

1) Stress conservative actions and NER 88047400 compliance with written procedures when repositioning control rods,

2) Guidance on actions whe.n criticality will be achieved outside the ECC tolerance band,

3) Avoid activities which distract the operators,

4) Directions to use pertinent instrumentation to monitor approach to criticality,

5) Periodic pauses during rod withdrawal.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 2 of 77 TABLE OF CONTENTS Page 1 of 2 Section Title Page

1.0 INTRODUCTION

                                 "...................................................................... 4 1.1       Purpose......                                                                                                            4 1.2       Scope................................................................................................................ 4

2.0 REFERENCES

.................................................................................................. 4 2.1 Performance References.................................................................................. 4 2.2 Developmental References............................................................................... 4 3.0 PRECAUTIONS AND LIMITATIONS................................................................ 6 4.0 PREREQUISITE ACTIONS .. 9 5.0 STARTUP/STANDBY READINESS 10 5.1 Placing MG Set(s) in Standby Readiness............................ 10 5.1.1 Placing MG Set A In Service With MG Set B NOT Operating 12 5.1.2 Placing MG Set B In Service With MG Set A NOT Operating 15 5.2 Reset/Close Reactor Trip Breakers.................................................................. 18 6.0 NORMAL OPERATION 21 6.1 Placing MG Set A In Service With MG Set B Operating......... 21 6.2 Placing MG Set B In Service With MG Set A Operating 30 6.3 Manual Operation of Rod Control System Below 15 Percent Power................ 39 6.4 Transferring from Manual to Auto Rod Control................................................. 52 6.5 Transferring from Auto to Manual Rod Control................................................. 53 7.0 SHUTDOWN..................................................................................................... 54 7.1 Removing the MG Set A From Service 54 7.2 Removing the MG Set B From Service 55

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 3 of 77 TABLE OF CONTENTS Page 2 of 2 Section Title Page 8.0 INFREQUENT OPERATION . 56 8.1 Alternate Method of Paralleling MG Set A . 56 8.2 Alternate Method of Paralleling MG Set B . 58 8.3 Resetting Step Counters After Withdrawing Rods Above 231 Steps . 60 8.4 Resetting Step Counters After Inserting Rods Below 0 Steps . 61 8.5 Placing MG Set A In Service for Maintenance . 62 8.6 Placing MG Set B In Service for Maintenance . 69 9.0 RECORDS . 76 SOURCE NOTES 77 ATTACHMENTS ATTACHMENT 1: CONTROL ROD DRIVE SYSTEM POWER CHECKLIST 1-85-1.01 ATTACHMENT 2: CONTROL ROD DRIVE SYSTEM POWER CHECKLIST 2-85-1.01

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 4 of 77

1.0 INTRODUCTION

1.1 Purpose This instruction provides the steps necessary for the operation of the Control Rod Drive System. 1.2 Scope This instruction provides detailed steps for the following operations: Placing Control Rod Drive MG Sets in Service Removing Control Rod Drive MG Sets from Service Parallel Operation of Control Rod Drive MG Sets Manual Operation of the Control Rod Drive System Transferring Rod Control from Manual to Auto Transferring Rod Control from Auto to Manual

2.0 REFERENCES

2.1 Performance References A. Procedures

1. 0-SI-NUC-000-038.0, Shutdown Margin

2. 1,2-PI-IFT-099-0P4.0, Verification of P4 Contacts B. Tech Specs

1. 3.4.1.2 C. Westinghouse Tech. Bulletin NSD-TB-92-05RO 2.2 Developmental References A. Tech Specs

1. 3.1.3.1

2. 3.1.3.2

3. 3.1.3.4

4. 3.1.3.5

5. 3.1.3.6

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 5 of 77

2.0 REFERENCES

(Continued) B. Technical Requirements Manual

1. TR 3.1.3.3 C. F8AR

1. 7.7.1.2.1 D. TVA Drawings

1. 45N699-1

2. 45N777-3

3. 45N703-1, 2, 3,4

4. 45N1646-4

5. 45N2646-4

6. 45N1624-1, 2, 3,4, 5, 8

7. 45N2624-1, 2, 3,4, 5, 8

8. 617F619

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 6 of 77 3.0 PRECAUTIONS AND LIMITATIONS A. Rod thermal lock-up is NOT a concern when the reactor trip breakers are OPEN. If reactor trip breakers are CLOSED and an RCS cooldown of greater than 50°F is planned, the shutdown and control banks should be withdrawn at least 5 steps each. This will limit the possibility of "thermal lock-up" of the rods. This does not apply if performing sections 8.5 or 8.6. B. If both MG sets are to be shutdown, the control rods and shutdown rods shall be inserted in the core and the reactor trip breakers OPEN prior to shutting down the MG sets. C. Reactor Trip Breakers shall NOT be closed while in Mode 3 unless in compliance with LCO 3.4.1.2. D. Failure to perform 1,2-PI-IFT-099-0P4.0, Verification of P4 Contacts could result in the prevention of AUTO SI if required. E. Under normal conditions, the control rod banks must be withdrawn and inserted in the prescribed sequence. For withdrawal the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank D, Control Bank A, Control Bank B, Control Bank C, and Control Bank D. The insertion sequence is the reverse of the withdrawal sequence. F. For manual bank sequencing, the prescribed withdrawal and insertion sequence should be followed. Rod motion of the correct bank should be monitored by observing the group step counters and the rod position indicators. G. During Control Rod withdrawal, the Control Banks should be monitored for bank overlap. H. The control banks must be maintained above their respective insertion limits (Low-Low Alarm to ensure adequate shutdown in the event of a reactor trip, to ensure that maximum possible ejected rod reactivity limits are maintained and to ensure acceptable core power distributions. I. Before withdrawing any rod bank from the fully inserted position, the group step counters and the rod position indicators for that bank must be at zero steps.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 7 of 77 3.0 PRECAUTIONS AND LIMITATIONS (Continued) J. Deleted K. The Control Rods shall NOT be stepped or tripped unless the RCS pressure is at least 100 psig. L. RPls and step counters shall be maintained within limits per TS 3.1.3.1 and 3.1.3.2. M. Continuous rod motion shall comply with these restrictions: CRDM OUTLET ROD MOTION LIMITS TEMPERATURE

                 ~  190°F          10 minutes ON          20 minutes OFF
                 ~  200°F          6 minutes ON           24 minutes OFF Time limitations are due to a lower air flow rate of 48,000 cfm across the shroud combined with a higher temperature (Reference TSIR-97-80P-30-636 and Westinghouse Letters RIM's #838931005806, 838930920800, and 838931005803).

N. The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication:

1) Hand switch failure; 2) relay failure, and 3) failure of both 100v DC power supplies (PS3 and PS6) simultaneously.

O. Defeating or restoring Tavg/Delta T or NIS channel may cause step change in input to rod control. A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 8 of 77 3.0 PRECAUTIONS AND LIMITATIONS (Continued) P. Directional Overcurrent Relay Targets are reset by depressing the Relay Target Reset Pushbutton on the panel to break the target coil seal in circuit and then lifting the mechanical reset at the bottom of the relay cover. Q. US / SRO Oversight for control rod manipulation shall include:

1. Prior to Rod Movement

a. Ensure RPI's within T.S. range (+ or - 12 steps)

b. Ensure delta flux will not be adversely affected

c. Ensure Tavg and Rx Thermal power will not be adversely affected

d. Verify on target with Rx Eng reactivity balance sheet

e. Verify power change will not exceed hourly rate

f. Ensure no simultaneous reactivity manipulations in progress (i.e.: borations, dilutions or turbine load changes)

2. During Rod Movement

a. Ensure RO has peer check

b. Ensure RO is following procedure

c. Ensure RO understands how many steps they are moving rods

d. Ensure RO has checked all the above mentioned items

e. Watch performance of rod manipulation while listening to audible indication of rod step

f. Ensure peer check is doing their job

g. Re-verify steps a - d of initial evaluation

h. Ensure procedure is followed placing rods back to auto (Tavg - Tref mismatch)

i. Monitor plant for expected response

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 9 of 77 Unit J _ Date Q'7Ix;7/98 4.0 PREREQUISITE ACTIONS NOTE Throughout this instruction where an IF/THEN statement occurs, the step may be N/A if the condition does NOT exist. [1] ENSURE the instruction to be used is a copy of the effective version. WtA [2] ENSURE Precautions and Limitations, Section 3.0 has been reviewed. [3] ENSURE each performer documents their name and initials: Print Name Initials W tJSoN '-r: Abbu+ w7A [4] INDICATE below which performance section of this instruction will be used and the reason for this performance: D 5.0 STARTUP/STANDBY READINESS ff. 6.0 NORMAL OPERATION D 7.0 SHUTDOWN D 8.0 INFREQUENT OPERATION Reason: WI'1Hb/t4W ~H\\160WN t3AN( P{LI\l(l To (2t A(:10 r'l s"1A(l:1 Uf

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 10 of 77 Unit Date _ 5.0 STARTUP/STANDBY READINESS 5.1 Placing MG Set(s) in Standby Readiness [1] ENSURE Section 4.0, Prerequisites complete. D [2] ENSURE [HS-85-5110], Rod Control Mode Selector Switch is in the MANUAL position. D [3] IF performance is on Unit 1, THEN ENSURE Power Checklist 1-85-1.01 is complete. D [4] IF performance is on Unit 2, THEN ENSURE Power Checklist 2-85-1.01 is complete. D NOTE Green targets on the breaker handswitches can be obtained by rotating the operating switch to the TRIP position and releasing to the NEUTRAL position. [5] ENSURE the following breakers are in the required position: REQUIRED TARGET BREAKER INITIALS POSITION COLOR CRD MG SetA OPEN GREEN Motor Bkr 52A (480V Unit Bd) CRD MG Set B OPEN GREEN Motor Bkr 52B (480V Unit Bd) MG SetA OPEN GREEN Load (Generator) Bkr 52-1 MG Set B OPEN GREEN Load (Generator) Bkr 52-2 [6] VERIFY [XA-55-4B-A5], ROD CONTROL MG SETS TRIPPED OR GROUNDED, alarm is NOT LIT.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 11 of 77 UNIT Date _ 5.1 Placing MG Set(s) in Standby Readiness (Continued) [7] TURN Generator No. 1 Westinghouse Thyrex Voltage Regulator (Reg) potentiometer to the FULL COUNTER-CLOCKWISE position and RETURN to the 9 O'CLOCK position. [8] TURN Generator No.2 Westinghouse Thyrex Voltage Regulator (WTV Reg) potentiometer to the FULL COUNTER-CLOCKWISE position and RETURN to the 9 O'CLOCK position. [9] ENSURE the following MG Set handswitches are in the required position: REQUIRED SWITCH INITIALS POSITION MG Set A Ammeter Selector Switch A MG Set B Ammeter Selector Switch A MG Set A Voltmeter Selector Switch AB MG Set B Voltmeter Selector Switch AB Generator No.1 Synchronize Sel Sw OFF Generator No.2 Synchronize Sel Sw OFF [10] ENSURE [1 KS], Three Pole Grounding Switch (located inside L-115 cabinet) is in the OPEN position. [11] ENSURE all relays and targets (located on L-115) for the MG Set breakers are RESET. End of Section 5.1

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 12 of 77 Unit Date- - - - 5.1.1 Placing MG Set A In Service With MG Set B Not Operating [1] ENSURE MG Set A is in Standby Readiness. D [2] START CRD MG Set A by placing [HS-85-1A] MOTOR Breaker 52A Circuit Control in the CLOSE position. D NOTE Allow 15 seconds for the MG set to obtain full rated speed. [3] VERIFY generator speed increasing. D [a] WHEN generator has increased to full speed, THEN [b] DEPRESS AND HOLD Gen Field Flash pushbutton. D [c] WHEN voltage is > 250 volts, THEN RELEASE Gen Field Flash pushbutton. D [4] IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with wrv Reg to a nominal 260 volts. D NOTE Voltage may vary slightly between phases. [5] CHECK equal voltage on all phases using voltmeter selector switch. D NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker. [6] ENSURE MG Set A Load (GENERATOR) Breaker 52-1 [BCTF-85-121 is RACKED IN.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 13 of 77 Unit Date _ 5.1.1 Placing MG Set A In Service With MG Set B Not Operating (Continued) [7] ENSURE MG Set B Load (GENERATOR) Breaker 52-2 [BCTF-85-22] is RACKED IN. [8] ENSURE CRDM MG Set A Directional Overcurrent Relay Target Coils are RESET (Panel Pushbutton). (N/A other Unit) Relay INITIALS [1-RLY-085-DE/4D/Al (67A) [1-RLY-085-DE/4D/C] (67C) [2-RLY-085-DG/4D/A] (67A) [2-RLY-085-DG/4D/C] (67C) [9] ENSURE targets for CRDM MG Set A Directional Overcurrent Relays RESET (Mechanical Linkage on relay). (N/A other Unit) Relay INITIALS [1-RLY-085-DE/4D/A] (67A) [1-RLY-085-DE/4D/C] (67C) [2-RLY-085-DG/4D/A] (67A) [2-RLY-085-DG/4D/C] (67C) NOTE: Generator voltage will drop slightly as the electrical load increases. [10] CLOSE MG Set A Load (GENERATOR) Breaker 52-1 USING [HS-85-121. D [11] IF MG Set A Load breaker 52-1 trips due to Directional Overcurrent Relay operation, THEN [a] RESET Directional Overcurrent Relays with Relay Target Reset Button on Relay panel. [b] RESET Directional Overcurrent Relay Targets. [c] RECLOSE MG Set A load Breaker 52-1 USING [HS-85-121. D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 14 of 77 Unit Date _ 5.1.1 Placing MG Set A In Service With MG Set B Not Operating (Continued) [d] IF another trip of breaker 52-1 occurs, REPEAT substeps [a], [b] and [c]. [e] IF breaker 52-1 trips the third time, THEN NOTIFY SM and System Engineering for assistance. D [12] WHEN placing the MG Sets in service initially OR Reactor Trip Breakers are to be reset, THEN GO TO Section 5.2, Resetting Reactor Trip Breakers. D End of Section 5.1.1

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 15 of 77 Unit- - - - - - Date _ 5.1.2 Placing MG Set B In Service With MG Set A Not Operating [1] ENSURE MG Set B is in Standby Readiness. D [2] START CRD MG Set B by placing [HS-85-1 B] MOTOR Breaker 52B Circuit Control in the CLOSE position. D NOTE Allow 15 seconds for the MG set to obtain full rated speed. [3] VERIFY generator speed increasing. D [4] WHEN generator has increased to full speed, THEN [a] DEPRESS AND HOLD Gen Field Flash pushbutton. D [b] WHEN voltage is > 250 volts, THEN RELEASE Gen Field Flash pushbutton. D [5] IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with WTV Reg to a nominal 260 volts. D NOTE Voltage may vary slightly between phases. [6] CHECK equal voltage on all phases using voltmeter selector switch. D NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker. [7] ENSURE MG Set A Load (GENERATOR) Breaker 52-1 is RACKED IN.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 16 of 77 Unit Date _ 5.1.2 Placing MG Set B In Service With MG Set A Not Operating (Continued) [8] ENSURE MG Set B Load (GENERATOR) Breaker 52-2 is RACKED IN. [9] ENSURE CRDM MG Set B Directional Overcurrent Relay Target Coils are RESET (Panel Pushbutton). (N/A other Unit) Relay INITIALS [1-RLY-085-DF/3B/A] (67A) [1-RLY-085-DF/3B/C] (67C) [2-RLY-085-DH/3B/A] (67A) [2-RLY-085-DH/3B/C] (67C) [10] ENSURE targets for CRDM MG Set B Directional Overcurrent Relays are RESET (Mechanical Linkage on relay). (N/A other Unit) Relay INITIALS [1-RLY-085-DF/3B/Al (67A) [1-RLY-085-DF/3B/C] (67C) [2-RLY-085-DH/3B/A] (67A) [2-RLY-085-DH/3B/C] (67C) NOTE Generator voltage will drop slightly as the electrical load increases. [11] CLOSE MG Set B Load (GENERATOR) Breaker 52-2 USING [HS-85-22]. [12] IF MG Set B Load breaker 52-2 trips due to Directional Overcurrent Relay operation, THEN [a] RESET Directional Overcurrent Relays with Relay Target Reset Button on Relay panel. [b] RESET Directional Overcurrent Relay Targets. [c] RECLOSE MG Set B load Breaker 52-2 USING [HS-85-221. D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 17 of 77 Unit Date _ 5.1.2 Placing MG Set B In Service With MG Set A Not Operating (Continued) [d] IF another trip of breaker 52-2 occurs, REPEAT substeps [a], [b] and [c]. [e] IF breaker 52-2 trips the third time, THEN NOTIFY SM and system engineering for assistance. D [13] WHEN placing the MG Sets in service initially OR Reactor Trip Breakers are to be reset, THEN GO TO Section 5.2, Resetting Reactor Trip Breakers. D End of Section 5.1.2

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 18 of 77 unit l _ 5.2 Reset/Close Reactor Trip Breakers [1] ENSURE desired MG Set is In Service. [2] ENSURE [1CB], Auxiliary 150-VAC Supply to Rod Drive System is CLOSED. (located in Panel L-115). [3] ENSURE lift coil disconnect switches, for Control Rods and Shutdown Rods are in the CONNECTED position (located on M-8). WTA [4] ENSURE all Control Rods and Shutdown Rods are inserted: ROD BANK FULLY INSERTED (-V) Shutdown Bank A [3' Shutdown Bank B ~ Shutdown Bank C ~ Shutdown Bank D ~ Control Bank A ~ Control Bank B CH' Control Bank C ~ Control Bank D ~ W-rA CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4) should never be held in STARTUP position for any extended period of time. Holding this switch in STARTUP position may cause damage to the counters. [5] MOMENTARILY PLACE [SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System, AND VERIFY RPls and group step counters are at zero steps. W'tA

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 19 of 77 Unit Date 0#// oS 5.2 Reset/Close Reactor Trip Breakers (Continued) [6] ENSURE Reactor Trip Bypass breakers BYA and BYB are OPEN and RACKED OUT. BYPASS RACKED OUT BREAKER OPEN (~) (~) BYA [}1' ~ BYB cV cY [7] ENSURE Reactor Trip breakers are RACKED IN: TRIP RACKED IN BREAKER (..J) RTA RTB [8] ENSURE control power is ON by GREEN indicating lights on M-4: BREAKER GREEN POSITION INITIALS LIGHT INDICATION RTA ON UJ1tl RTB ON tAJflf [9] ENSURE Rod Control switch [HS-85-51111 is in MID position. [10] IF unit is in Mode 3,THEN ENSURE requirements of Tech Spec 3.4.1.2 are met. W10 [11] DEPRESS and HOLD FW Isol Reset pushbuttons [HS-3-99A] and [HS-3-99B]. [C.1]

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 20 of 77 I Unit- - - - - - Date 0 J/xx,lo3 5.2 Reset/Close Reactor Trip Breakers (Continued) [12] IF resetting Unit 1 Reactor Trip Breakers, THEN CLOSE Rx Trip Breakers by placing [1-RT-1], in CLOSE position. [13] IF resetting Unit 2 Reactor Trip Breakers, THEN CLOSE Rx Trip Breakers by placing [2-HS-99-7], in CLOSE position. [14] VERIFY Reactor Trip Breakers CLOSED by RED indicating lights on M-4: BREAKER POSITION RED LIGHT INITIALS INDICATION RTA ON VV-rtt RTB ON W<1A [15] RELEASE FW Isol Reset push buttons [HS-3-99A] and [HS-3-99B]. [C.1] [16] NOTIFY IMs to perform 1,2-PI-IFT-099-0P4.0, Verification of P4 Contacts. [17] IF Shutdown or Control Rods will be withdrawn, THEN GO TO Section 6.3, Manual Operation of Rod Control System Below 15 Percent Power. End of Section 5.2

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 21 of 77 Unit Date- - - - 6.0 NORMAL OPERATION 6.1 Placing MG Set A In Service With MG Set B Operating [1] ENSURE MG Set B is In Service. [2] ENSURE MG Set A is in Standby Readiness. D [3] ENSURE Reactor Trip Breakers are CLOSED. [4] START CRD MG Set A by placing [HS-85-1Al MOTOR Breaker 52A Circuit Control in the CLOSE position. D [5] VERIFY generator speed increasing. D [6] WHEN generator has increased to full speed, THEN [a] DEPRESS AND HOLD Gen Field Flash pushbutton. D [b] WHEN voltage is > 250 volts, THEN RELEASE Gen Field Flash pushbutton. D NOTE Digital voltmeters are much more accurate than panel meters and are the preferred instrumentation when synchronizing the generators. The panel meters should only be used in the event of an emergency. [7] REQUEST the SM/SRO to determine which of the following types of meters should be used to synchronize and balance the MG Sets: MG Set panel meters. D Digital meters. D US/SRO

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 22 of 77 Unit Date- - - - 6.1 Placing MG Set A In Service With MG Set B Operating (Continued) NOTE The auto synchronizing circuit has a low voltage cutout circuit which will NOT allow the second MG Set to synchronize if voltage on the loaded MG Set is less than 254 volts. Minimum voltage for placing the second generator in parallel is 260 volts. [8] IF using the MG Set panel voltmeters for voltage adjustment, THEN [a] ENSURE MG Set B voltage is ADJUSTED with Westinghouse Thyrex voltage (WTV) regulator potentiometer to 260 volts (within plus or minus 1.0 volts) on panel meter. [b] ENSURE MG Set A voltage is ADJUSTED with WTV regulator potentiometer to match MG Set B voltage. CAUTION Do NOT jar MG set panel doors when they are being opened or closed. There is a potential for inadvertent relay operation. [9] IF using digital meters for voltage adjustment, THEN [a] ENSURE qualified electrical maintenance personnel have OBTAINED 2 Fluke 8840A (or equivalent) digital voltmeters and 2 Keithley 197 (or equivalent) digital voltmeters to be used for synchronization and balancing of the MG Sets. [b] ENSURE Keithley (or equivalent) digital voltmeters (DVM) are CONNECTED to the terminals on the panel voltmeters for both MG Set Band MG Set A. This DVM voltage is proportional to generator voltage. [c] ENSURE Fluke (or equivalent) digital voltmeters (DVM) are CONNECTED to the terminals on the panel ammeters for both MG Set Band MG Set A. This DVM voltage is proportional to generator amps. (Step continued on Next Page)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 23 of 77 Unit Date 6.1 Placing MG Set A In Service With MG Set B Operating (Continued) [9] (Continued) [d] ENSURE MG Set B voltage is ADJUSTED with WTV regulator potentiometer to 108 volts (260 volts on panel meter) as indicated on the digital voltmeter, to be within plus or minus 1.0 volt (digital voltmeter). [e] ENSURE MG Set A voltage is ADJUSTED with WTV regulator potentiometer to match MG Set B voltage, to be within 0.5 volts (digital voltmeter). [10] ENSURE CRDM MG Set A Directional Overcurrent Relay Target Coils RESET (Panel Pushbutton). (N/A other Unit) Relay INITIALS [1-RLY -085-DE/4D/A] (67A) [1-RLY-085-DE/4D/Cl (67C) [2-RLY -085-DG/4DIA] (67A) [2-RLY -085-DG/4D/Cl (67C) [11] ENSURE targets for CRDM MG Set A Directional Overcurrent Relays RESET (Mechanical Linkage on relay). (N/A other Unit) Relay INITIALS [1-RLY-085-DE/4D/Al (67A) [1-RLY -085-DE/4D/C] (67C) [2-RLY-085-DG/4D/A] (67A) [2-RLY-085-DG/4D/C] (67C) NOTE The following step should close the generator load breaker if paralleling is successful. [12] PLACE [HS-85-12Bl Gen NO.1 SYNCHRONIZE Switch in the ON position.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 24 of 77 Unit Date _ 6.1 Placing MG Set A In Service With MG Set B Operating (Continued) NOTE MG Set A should parallel within 17 seconds. [13] IF MG Sets are paralleled, THEN [a] PLACE [HS-85-12B] Gen NO.1 SYNCHRONIZE Switch in the OFF position. [14] IF DVMs are being utilized to balance generator amps (loading), THEN PERFORM the following to balance MG set A & B currents: [a] RECORD "as found" voltage and current readings: NOTE With MG sets paralleled, the voltmeters are reading the same electrical point. Therefore, data is only required from one MG set in sub- steps 1 -6.

1. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "AB".

2. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts

3. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "BC".

4. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts

5. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "CA".

6. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 25 of 77 Unit Date _ 6.1 Placing MG Set A In Service With MG Set B Operating (Continued) [14] (Continued) [a] (Continued) NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical point. Therefore, data is required from 80TH MG sets in sub- steps 7 - 12.

7. ENSURE MG Set A and 8 Ammeter Selector Switches are selected for "A".

8. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - - mV MG Set 8 mV

9. ENSURE MG Set A and 8 Ammeter Selector Switches are selected for "8".

10. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - - mV MG Set 8 mV

11. ENSURE MG Set A and 8 Voltmeter Selector Switches are selected for "C".

12. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - - mV MG Set 8 mV [b] EVALUATE 'as found" data from Step [14][a] and the position of the directional contacts on the Directional Overcurrent Relays (DaR) associated with both MG sets to determine if any adjustment is necessary.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 26 of 77 Unit Date- - - - 6.1 Placing MG Set A In Service With MG Set B Operating (Continued) [14] (Continued) NOTE There are two methods by which balanced MG Set currents can be achieved using the WTV Voltage Potentiometers. The preferred method is to balance the Directional Overcurrent Relays directional contacts to the far right and as steady as achievable while maintaining 108 +/- 1 volts on the Fluke (or equivalent) DVMs connected to the MG Set voltmeters. This method will NOT usually result in currents balanced to within 1 mV (as read on the Keithley (or equivalent)). The secondary method is to balance the Keithley (or equivalent) DVMs connected to the panel ammeters to within 1 mV while maintaining 108 +/- 1 volts as indicated by the Fluke (or equivalent) DVM connected to the generator voltmeter. [c] IF adjustment is determined to be necessary by Cognizant Craft or Engineer, THEN ADJUST WTV voltage regulator potentiometers on MG Sets A & B to balance generator currents. [d] IF an adjustment was made, THEN RECORD "as left" voltage and current readings: NOTE With MG sets paralleled, the voltmeters are reading the same electrical point. Therefore, data is only required from one MG set in sub- steps 1 -6.

1. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "AB".

2. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts

3. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "BC".

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 27 of 77 Unit Date _ 6.1 Placing MG Set A In Service With MG Set B Operating (Continued) [14] (Continued) [d] (Continued)

4. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts

5. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "CA".

6. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical point. Therefore, data is required from BOTH MG sets in sub- steps 7 - 12.

7. ENSURE MG Set A and B Ammeter Selector Switches are selected for "A".

8. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - - mV MG Set B mV

9. ENSURE MG Set A and B Ammeter Selector Switches are selected for "B".

1O. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for: MG SetA - - - - - - mV MG Set B mV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 28 of 77 Unit Date- - - - 6.1 Placing MG Set A In Service With MG Set B Operating (Continued) [14] (Continued) [d] (Continued)

11. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "C".

12. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - mV MG Set B mV [e] IF digital meters were installed in step [9], THEN

1. ENSURE all digital meters are removed. __ I_-

1st CV

2. ENSURE the MG Set panel doors are closed.

1st CV [15] IF MG Set A load breaker 52-1 closes but subsequently trips due to Directional Overcurrent Relay operation, THEN [a] PLACE [HS-85-12Bl Gen NO.1 SYNCHRONIZE Switch in the OFF position. [b] ENSURE CRDM MG Set A Directional Overcurrent Relay Target Coils are RESET (Panel Pushbutton). (N/A other Unit) Relay INITIALS [1-RLY-085-DE/4D/Al (67A) [1-RLY-085-DE/4D/C] (67C) [2-RLY-085-DG/4D/Al (67A) [2-RLY-085-DG/4D/Cl (67C)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 29 of 77 Unit Date 6.1 Placing MG Set A In Service With MG Set B Operating (Continued) [c] ENSURE targets for CRDM MG Set A Directional Overcurrent Relays RESET (Mechanical Linkage on relay). (N/A other Unit) Relay INITIALS [1-RLY -085-DE/4D/A] (67A) [1-RLY -085-DE/4D/Cl (67C) [2-RLY-085-DG/4D/Al (67A) [2-RLY -085-DG/4D/Cl (67C) [d] IF 1st attempt to synchronize, RETURN to step [12]. D [e] IF 2 nd attempt to synchronize was unsuccessful, THEN INITIATE a WO to troubleshoot the problem. D [16] IF MG Set A does NOT parallel within 17 seconds, THEN [a] CHECK MG Set voltages. D [b] IF voltages appear to have drifted apart AND/OR another adjustment is desired, THEN

1. PLACE [HS-85-12Bl Gen No. 1 SYNCHRONIZE Switch in the OFF position. D

2. RETURN to step [7]. D

[17] IF Alternate Method of Paralleling MG Set A is desired, THEN GO TO Section 8.1. [18] ENSURE target for CRD MG Set A Load (GENERATOR) Bkr 52-1 is RED by placing [HS-85-121 GENERATOR breaker circuit control in the CLOSE position. D End of Section 6.1

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 30 of 77 Unit Date- - - - 6.2 Placing MG Set B In Service With MG Set A Operating [1] ENSURE MG Set A is In Service. D [2] ENSURE MG Set B is in Standby Readiness. D [3] ENSURE Reactor Trip Breakers are CLOSED. D [4] START CRD MG Set B by placing fHS-85-1 B] MOTOR Breaker 52B Circuit Control in the CLOSE position. D [5] VERIFY generator speed increasing. D [6] WHEN generator has increased to full speed, THEN [a] DEPRESS AND HOLD Gen Field Flash pushbutton. D [b] WHEN voltage is greater than 250 volts, THEN RELEASE Gen Field Flash pushbutton. D NOTE Digital voltmeters are much more accurate than panel meters and are the preferred instrumentation when synchronizing the generators. The panel meters should only be used in the event of an emergency. [7] REQUEST the SM/SRO to determine which of the following types of meters should be used to synchronize and balance the MG Sets: MG Set panel meters. D Digital meters. D SM/SRO

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 . Rev 32 Page 31 of 77 Unit Date 6.2 Placing MG Set B In Service With MG Set A Operating (Continued) NOTE The auto synchronizing circuit has a low voltage cutout circuit which will NOT allow the second MG Set to synchronize if voltage on the loaded MG Set is less than 254 volts. Minimum voltage for placing the second generator in parallel is 260 volts. [8] IF using the MG Set panel voltmeters for voltage adjustment, THEN [a] ENSURE MG Set A voltage is ADJUSTED with Westinghouse Thyrex voltage (WTV) regulator potentiometer to 260 volts (within plus or minus 1.0 volts) on panel meter. [b] ENSURE MG Set B voltage is ADJUSTED with WTV regulator potentiometer to match MG Set A voltage. CAUTION Do NOT jar MG set panel doors when they are being opened or closed. There is a potential for inadvertent relay operation. [9] IF using digital meters for voltage adjustment, THEN [a] ENSURE qualified electrical maintenance personnel have OBTAINED 2 Fluke 8840A (or equivalent) digital voltmeters and 2 Keithley 197 (or equivalent) digital voltmeters to be used for synchronization and balancing of the MG Sets. [b] ENSURE Keithley (or equivalent) digital voltmeters (DVM) are CONNECTED to the terminals on the panel voltmeters for both MG Set Band MG Set A. This DVM voltage is proportional to generator voltage. [c] ENSURE Fluke (or equivalent) digital voltmeters (DVM) are CONNECTED to the terminals on the panel ammeters for both MG Set Band MG Set A. This DVM voltage is proportional to generator amps. (Step continued on Next Page)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 32 of 77 Unit Date _ 6.2 Placing MG Set B In Service With MG Set A Operating (Continued) [d] ENSURE MG Set A voltage is ADJUSTED with WTV regulator potentiometer to 108 volts (260 volts on panel meter) as indicated on the digital voltmeter, to be within plus or minus 1.0 volt (DVM). [e] ENSURE MG Set B voltage is ADJUSTED with WTV regulator potentiometer to match MG Set A voltage, to be within 0.5 volts (DVM). [10] ENSURE CRDM MG Set B Directional Overcurrent Relay Target Coils are RESET (Panel Pushbutton). (N/A other Unit) Relay INITIALS [1-RLY -085-DF/3B/A] (67A) [1-RLY-085-DF/3B/C] (67C) [2-RLY-085-DH/3B/Al (67A) [2-RLY-085-DH/3B/Cl (67C) [11] ENSURE targets for CRDM MG Set B Directional Overcurrent Relays are RESET (Mechanical Linkage on re Iay ) . (N/A oth er U nl't) Relay INITIALS [1-RLY-085-DF/3B/Al (67A) [1-RLY-085-DF/3B/Cl (67C) [2-RLY-085-DH/3B/Al (67A) [2-RLY-085-DH/3B/Cl (67C) NOTE The following step should close the generator load breaker if paralleling is successful. [12] PLACE [HS-85-22B] Gen NO.2 SYNCHRONIZE Switch in the ON position. NOTE MG Set B should parallel within 17 seconds. [13] IF MG Sets are paralleled, THEN [a] PLACE [HS-85-22B] Gen NO.2 SYNCHRONIZE Switch in the OFF position.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 33 of 77 Unit Date 6.2 Placing MG Set B In Service With MG Set A Operating (Continued) [14] IF DVMs are being utilized to balance generator amps (loading), THEN PERFORM the following to balance MG set A & B currents: [a] RECORD "as found" voltage and current readings: NOTE With MG sets paralleled, the voltmeters are reading the same electrical point. Therefore, data is only required from one MG set in sub- steps 1 -6.

1. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "AB".

2. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts

3. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "BC".

4. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG SetAOR MG Set B volts

5. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "CA".

6. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG SetAOR MG Set B volts NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical point. Therefore, data is required from BOTH MG sets in sub- steps 7 - 12.

7. ENSURE MG Set A and B Ammeter Selector Switches are selected for "A".

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 34 of 77 Unit Date _ 6.2 Placing MG Set B In Service With MG Set A Operating (Continued) [14] (Continued) [a] (Continued)

8. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - - mV MG Set B mV

9. ENSURE MG Set A and B Ammeter Selector Switches are selected for "B".

1O. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for: MG SetA - - - - - - mV MG Set B mV

11. ENSURE MG Set A and B Ammeter Selector Switches are selected for "C".

12. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - - mV MG Set B mV [b] EVALUATE 'as found" data from Step [14] [a] and the position of the directional contacts on the Directional Overcurrent Relays (DOR) associated with both MG sets to determine if any adjustment is necessary.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 35 of 77 Unit Date 6.2 Placing MG Set B In Service With MG Set A Operating (Continued) [14] (Continued) NOTE There are two methods by which balanced MG Set currents can be achieved using the WTV Voltage Potentiometers. The preferred method is to balance the Directional Overcurrent Relays directional contacts to the far right and as steady as achievable while maintaining 108 +/- 2 volts on the Fluke (or equivalent) DVMs connected to the MG Set voltmeters. This method will NOT usually result in currents balanced to within 1 mV (as read on the Keithley (or equivalent)). The secondary method is to balance the Keithley (or equivalent) DVMs connected to the panel ammeters to within 1 mV while maintaining 108 +/- 1 volts as indicated by the Fluke (or equivalent) DVM connected to the generator voltmeter. [c] IF adjustment is determined to be necessary by Cognizant Craft or Engineer, THEN ADJUST WTV voltage regulator potentiometers on MG Sets A & B to balance generator currents. [d] IF an adjustment was made, THEN RECORD "as left" voltage and current readings: NOTE With MG sets paralleled, the voltmeters are reading the same electrical point. Therefore, data is only required from one MG set in sub- steps 1 -6.

1. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "AB".

2. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts

3. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "BC".

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 36 of 77 Unit Date- - - - 6.2 Placing MG Set B In Service With MG Set A Operating (Continued) [14] (Continued) [d] (Continued)

4. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts

5. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "CA".

6. RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent) DVM connected to the panel volt meters for:

MG Set A OR MG Set B volts NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical point. Therefore, data is required from BOTH MG sets in sub- steps 7 - 12.

7. ENSURE MG Set A and B Ammeter Selector Switches are selected for "A".

8. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - - mV MG Set B mV

9. ENSURE MG Set A and B Ammeter Selector Switches are selected for "B".

10. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - - mV MG Set B mV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 37 of 77 Unit Date 6.2 Placing MG Set B In Service With MG Set A Operating (Continued) [14] (Continued) [d] (Continued)

11. ENSURE MG Set A and B Voltmeter Selector Switches are selected for "C".

12. RECORD output current as indicated by the Fluke (or equivalent) DVM connected to the panel amp meters for:

MG SetA - - - - - mV MG Set B mV [e] IF digital meters were installed in step [9], THEN

1. ENSURE all digital meters are removed. __ I_-

1st CV

2. ENSURE the MG Set panel doors are closed.

1st CV [15] IF MG Set B load breaker 52-2 closes but subsequently trips due to Directional Overcurrent Relay operation, THEN [a] PLACE [HS-85-22Bl Gen NO.2 SYNCHRONIZE Switch in the OFF position. [b] ENSURE CRDM MG Set B Directional Overcurrent Relay Target Coils are RESET (Panel Pushbutton). (N/A other Unit) Relay INITIALS [1-RLY-085-DF/3B/Al (67A) [1-RLY-085-DF/3B/C] (67C) [2-RLY-085-DH/3B/Al (67A) [2-RLY-085-DH/3B/C] (67C)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 38 of 77 Unit Date- - - - 6.2 Placing MG Set B In Service With MG Set A Operating (Continued) [c] ENSURE targets for CRDM MG Set B Directional Overcurrent Relays are RESET (Mechanical Linkage on relay). (N/A other Unit) Relay INITIALS [1-RLY-085-DF/3B/Al (67A) [1-RLY-085-DF/3B/Cl (67C) [2-RLY-085-DH/3B/Al (67A) [2-RLY-085-DH/3B/Cl (67C)

             ,[d] IF 1st attempt to synchronize, RETURN to step [12].                 D nd

[e] IF 2 attempt to re-synchronize was unsuccessful, THEN INITIATE a WO to troubleshoot the problem. D [16] IF MG Set B does NOT parallel within 17 seconds, THEN [a] CHECK MG Set voltages. D [b] IF voltages appear to have drifted apart AND/OR another adjustment is desired, THEN

1. PLACE [HS-85-22Bl Gen NO.2 SYNCHRONIZE Switch in the OFF position. D

2. RETURN to step [7]. D

[17] IF Alternate Method of Paralleling MG Set B is desired, THEN GO TO Section 8.2. D [18] ENSURE target for CRD MG Set B Load (GENERATOR) Bkr 52-2 is RED by placing [HS-85-22] GENERATOR breaker circuit control in the CLOSE position. D End of Section 6.2

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 39 of 77 Unit Date- - - - 6.3 Manual Operation of Rod Control System Below 15 Percent Power CAUTION If reactor trip breakers are CLOSED and an RCS cooldown of greater than 50°F is planned, the shutdown and control banks should be withdrawn at least 5 steps each. This will limit the possibility of "thermal lock-up" of the rods. Thermal lock-up is NOT a concern during unit heatup. NOTE Continuous rod motion shall comply with these restrictions: CRDM OUTLET ROD MOTION LIMITS TEMPERATURE s190°F 10 minutes ON 20 minutes OFF s200°F 6 minutes ON 24 minutes OFF [1] ENSURE Section 5.2, ReseUClose Reactor Trip Breakers has been completed. D [2] IF the shutdown and control rods were withdrawn 5 steps to prevent thermal lockup during an RCS cooldown, THEN ENSURE rods are fully inserted prior to withdrawal. 1st CV NOTE ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4) Resets: A. All GROUP STEP COUNTERS on the Control Board. B. The master cycler reversible counter. C. All slave cycler counters. D. The bank overlap counter. E. All internal memory and alarm circuits. F. All pulse-to-analog converters in the Rod Position Indication System. CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4) should never be held in STARTUP position for any extended period of time. Holding this switch in STARTUP position may cause damage to the counters. [3] MOMENTARILY PLACE [SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System. D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 40 of 77 Unit Oate _ 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) CAUTION Before withdrawing any rod from the fully inserted position, all Group Step Counters and all Rod Position indicators must be at zero steps. [4] ENSURE all Full Length Rod step counters reset to zero. [5] VERIFY rod control IN-OUT direction lights are NOT LIT. [6] DEPRESS [RCAS], Rod Urgent Failure Alarm Reset. D [7] RESET Window 6 (A-6) , ROD CONTROL SYSTEM URGENT FAILURE alarm on panel [XA-55-4Bl using [XS-55-4A], Annunciator RESET/ACKITEST Switch. [8] VERIFY the following rod control system alarms on panel [XA-55-4Bl are NOT LIT: WINDOW NOT LIT NUMBER N) 5 (A5) D 6 (A6) D 11 (84) D 12 (85) D 13(86) D 18 (C4) D 19(C5) D 27 (06) D 34 (E6) D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 41 of 77 Unit Date _ 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) [9] ENSURE Plant computer points for rod bank position are ZERO using the following computer points: COMPUTER PT ROD BANK ..J U0049 Control A D U0050 Control B D U0051 Control C D U0052 Control D D U0053 Shutdown A D U0054 Shutdown B D U0055 Shutdown C D U0056 Shutdown D D [10] MONITOR Control Rod position USING Rod Position Indicators ICS screen 30 minute trend during SD & Control Banks withdrawal to aid in detecting rod misalignment. D [11] IF Individual Rod Position Indication does not indicate proper rod position during withdrawal of SD Banks, THEN [a] STOP rod withdrawal. D [b] ENSURE subcriticality. D [c] CONTACT MIG AND INITIATE troubleshooting. D [d] IF troubleshooting does not resolve the problem, OR subcriticality can NOT be verified, THEN INITIATE Reactor TRIP. D [12] IF Individual Rod Position Indication does not indicate proper rod position during withdrawal of Control Banks, THEN GO TO AOP-C.01 section 2.6 Rod Position Indicator (RPI) Malfunction - Modes 1 or 2. D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 42 of 77 Unit Date 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) CAUTION Under normal conditions control rod banks must be withdrawn and inserted in the prescribed sequence. For withdrawal, the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank 0, Control Bank A, Control Bank B, Control Bank C, Control Bank D. The insertion sequence is the reverse of the withdrawal sequence. NOTE 1 Startup rate, Source range, Intermediate range, Nuclear Instrumentation recorders, Group Step Counters and the Rod Position Indicators should be monitored during each bank withdrawal. NOTE 2 The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and

3) simultaneous failure of both 100v DC power supplies (PS3 and PS6)

[13] PLACE [HS-85-511 0], Rod Control Mode Selector to the SBA position. 1st CV [14] VERIFY Rod Speed Indicator [SI-412], indicates 64 Steps/minute. 1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 43 of 77 Unit Date 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) NOTE Monitor Group Step Counters, Rod Position Indicator and the "IN-OUT" status lights to ensure anticipated motion as each bank is being withdrawn. Rod speed indicator should be reading 64 steps per minute. [15] ENSURE Shutdown Bank A demand position counters operational by performing the following: [C.2] [a] BUMP [HS-85-51111, Rod Control Switch to withdraw Shutdown Bank A one-half step at a time, for one full step. 1st CV [b] CHECK group demand position counters advance properly. D [c] BUMP [HS-85-51111 to withdraw Shutdown Bank A one-half step at a time, for the second full step. 1st CV [d] VERIFY group demand position counters advance properly. D [e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. D B. INITIATE WO to have counter repaired. D C. WHEN counter is repaired, THEN

1. ENSURE Shutdown Bank A fully INSERTED. D

2. RETURN to beginning of this step. D NOTE The fully withdrawn position for shutdown and control rods is defined by TI-28, Att. 6.

[16] WITHDRAW Shutdown Bank A to the FULLY WITHDRAWN position using [HS-85-5111]. 1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 44 of 77 Unit Date _ 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) [17] PLACE [HS-85-511 01, Rod Control Mode Selector to the SBB position. 1st CV [18] VERIFY Rod Speed Indicator [SI-412], indicates 64 Steps/minute. __ I_- 1st CV NOTE The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and

3) simultaneous failure of both 100v DC power supplies (PS3 and PS6).

[19] ENSURE Shutdown Bank B demand position counters operational by performing the following: [C.2] [a] BUMP [HS-85-51111, Rod Control Switch to withdraw Shutdown Bank B one-half step at a time, for one full step. 1st cv [b] CHECK group demand position counters advance properly. D [c] BUMP [HS-85-5111] to withdraw Shutdown Bank B one-half step at a time, for the second full step. 1st cv [d] VERIFY group demand position counters advance properly. D [e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. D B. INITIATE WO to have counter repaired. D C. WHEN counter is repaired, THEN

1. ENSURE Shutdown Bank B fully INSERTED and D

2. RETURN to beginning of this step. D

[20] WITHDRAW Shutdown Bank B to the FULLY WITHDRAWN position using [HS-85-5111]. 1st cv

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 45 of 77 Unit Date- - - - 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) [21] PLACE [HS-85-511 0], Rod Control Mode Selector to the SBC position. 1st CV [22] VERIFY Rod Speed Indicator [SI-412], indicates o Steps/minute. __ I_- 1st CV NOTE The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and

3) simultaneous failure of both 100v DC power supplies (PS3 and PS6).

[23] ENSURE Shutdown Bank C demand position counters operational by performing the following: [C.2] [a] BUMP [HS-85-5111], Rod Control Switch to withdraw Shutdown Bank C one full step. 1st CV [b] CHECK group demand position counter advances properly. D [c] BUMP [HS-85-5111] to withdraw Shutdown Bank C a second full step. 1st CV [d] VERIFY group demand position counter advanced properly. D [e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. D B. INITIATE WO to have counter repaired. D C. WHEN counter is repaired, THEN

1. ENSURE Shutdown Bank C fully INSERTED and D

2. RETURN to beginning of this step. D

[24] WITHDRAW Shutdown Bank C to the FULLY WITHDRAWN position using [HS-85-51111. 1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 46 of 77 Unit Date- - - - 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) [25] PLACE [HS-85-511 0], Rod Control Mode Selector to the SBD position. 1st CV [26] VERIFY Rod Speed Indicator [SI-412], indicates o Steps/minute. __ I_- 1st CV NOTE The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and

3) simultaneous failure of both 100v DC power supplies (PS3 and PS6).

[27] ENSURE Shutdown Bank D demand position counters operational by performing the following: [C.2] [a] BUMP [HS-85-51111, Rod Control Switch to withdraw Shutdown Bank D one full step. 1st CV [b] CHECK group demand position counter advances properly. D [c] BUMP [HS-85-51111 to withdraw Shutdown Bank D a second full step. 1st CV [d] VERIFY group demand position counter advanced properly. D [e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. D B. INITIATE WO to have counter repaired. D C. WHEN counter is repaired, THEN

1. ENSURE Shutdown Bank D fully INSERTED and D

2. RETURN to beginning of this step. D

[28] WITHDRAW Shutdown Bank D to the FULLY WITHDRAWN position using [HS-85-5111 1. 1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 47 of 77 Unit Date 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) NOTE Remainder of this section performed in conjunction with 0-GO-2 or 0-RT-NUC-000-003.0. [29] PLACE [HS-85-511 0], Rod Control Mode Selector to the MANUAL position. 1st CV [30] VERIFY Rod Speed Indicator [SI-412], indicates 48 Steps/minute. __ I_- 1st CV NOTE The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and

3) simultaneous failure of both 100v DC power supplies (PS3 and PS6).

[31] ENSURE Control Bank A demand position counters operational by performing the following: [C.2] [a] BUMP [HS-85-5111], Rod Control Switch to withdraw Control Bank A one-half step at a time, for one full step. 1st CV [b] CHECK group demand position counters advance properly. D [c] BUMP [HS-85-5111] to withdraw Control Bank A one-half step at a time, for the second full step. 1st CV [d] VERIFY group demand position counters advance properly. D [e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. D B. INITIATE WO to have counter repaired. D C. WHEN counter is repaired, THEN

1. ENSURE Control Bank A fully INSERTED and D

2. RETURN to beginning of this step. D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 48 of 77 Unit Date- - - - 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) [32] CONTINUE withdrawal of Control Bank A using [HS-85-5111], Rod Control Switch to 128 steps or next doubling. NOTE When Control Bank A is above 20 steps, alarm FULL LENGTH RODS AT BOTTOM light on [XA-55-4B] should clear. When Control Bank A gets above 20 steps and rods are driven back in, the alarm will come back in. When Control Banks B, C, and 0 get above 35 steps, then drop below 20 steps, the alarm will come back in. [33] WHEN Control Bank A is above 20 steps, THEN ENSURE Window 28 (0-7), FULL LENGTH RODS RODS AT BOTTOM alarm on panel [XA-55-4B] CLEARS.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 49 of 77 Unit Date _ 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) CAUTION When Control Bank A is reaches 128 steps, Control Bank B should begin to move. Each successive bank should begin to move when the previous bank reaches 128 steps. [34] WHEN Control Bank A is withdrawn to 128 steps, THEN ENSURE Control Bank B demand position counters operational by performing the following: [C.2] [a] BUMP [HS-85-5111], Rod Control Switch to withdraw Control Bank B one-half step at a time, for one full step. 1st CV [b] CHECK group demand position counters advance properly. D [c] BUMP [HS-85-51111 to withdraw Control Bank B one-half step at a time, for the second full step. 1st CV [d] VERIFY group demand position counters advance properly. D [e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. D B. INITIATE WO to have counter repaired. D C. WHEN counter is repaired, THEN

1. ENSURE Control Bank B fully INSERTED and D

2. RETURN to beginning of this step. D

[35] CONTINUE withdrawal of Control Bank Busing [HS-85-5111l to 128 steps or next doubling.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 50 of 77 Unit Date _ 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) [36] WHEN Control Bank B is withdrawn to 128 steps, THEN ENSURE Control Bank C dema,nd position counters operational by performing the following: [C.2] [a] BUMP [HS-85-51111, Rod Control Switch to withdraw Control Bank C one-half step at a time, for one full step. 1st CV [b] CHECK group demand position counters advance properly. D [c] BUMP [HS-85-51111 to withdraw Control Bank C one-half step at a time, for the second full step. 1st CV [d] VERIFY group demand position counters advance properly. D [e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. D B. INITIATE WO to have counter repaired. D C. WHEN counter is repaired, THEN

1. ENSURE Control Bank C fully INSERTED and D

2. RETURN to beginning of this step. D

[37] CONTINUE withdrawal of Control Bank C using [HS-85-51111 to 128 steps or next doubling. NOTE Three steps are added to the low-low insertion limit (110 steps @ zero power) until LEFM is available. [38] WHEN Control Bank C is ~ 113 Steps, THEN ENSURE Window 14 (B-7), ROD CONTROL BANKS LIMIT LOW-LOW alarm on panel [XA-55-4Bl CLEARS.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 51 of 77 Unit Date 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued) NOTE Three steps are added to the low insertion limit (120 steps @ zero power) until LEFM is available. [39] WHEN Control Bank C is ~ 123 steps, THEN ENSURE Window 7 (A-7), ROD CONTROL BANKS LIMIT LOW alarm on panel [XA-55-4Bl CLEARS. [40] WHEN Control Bank C is withdrawn to 128 steps, THEN ENSURE Control Bank 0 demand position counters operational by performing the following: [C.2] [a] BUMP [HS-85-5111], Rod Control Switch to withdraw Control Bank 0 one-half step at a time, for one full step. 1st CV [b] CHECK group demand position counters advance properly. D [c] BUMP [HS-85-51111 to withdraw Control Bank 0 one-half step at a time, for the second full step. 1st CV [d] VERIFY group demand position counters advance properly. D [e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. D B. INITIATE WO to have counter repaired. D C. WHEN counter is repaired, THEN

1. ENSURE Control Bank D fully INSERTED and D

2. RETURN to beginning of this step. D

[41] CONTINUE withdrawal of Control Bank Dusing [HS-85-51111 to next doubling or criticality. End of Section 6.3

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 52 of 77 Unit Date 6.4 Transferring from Manual to Auto Rod Control NOTE 1 A laminated copy of this section can be maintained in the Unit Control Room for repetitive use for routine rod manipulations. NOTE 2 Defeating or restoring Tavg/Delta T or NIS channel may cause step change in input to rod control. A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off. NOTE 3 This Section may be N/A if Rod Control is being returned to AUTO in response to a transient (runback) condition. [1] ENSURE turbine power is greater than 15 percent. [2] ENSURE Window 31 (E-3), LOW TURB IMPULSE PRESS ROD WITHDRAWAL BLOCKED C-5, Permissive light on panel [XA-55-4A] is NOT LIT. [3] ENSURE less than 1 degree Tavg/Tref mismatch. [4] PLACE [HS-85-511 0], Rod Control Mode Selector in the AUTO position. 1st cv [5] VERIFY Rod Speed Indicator [SI-412], indicates 8 Steps/minute. 1st CV End of Section 6.4

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 53 of 77 Unit Date _ 6.5 Transferring from Auto to Manual Rod Control NOTE 1 A laminated copy of this section can be maintained in the Unit Control Room for repetitive use for routine rod manipulations. NOTE 2 Manual rod withdrawal is inhibited by any of the following signals: A. C-1, High Flux Intermediate Range Monitor B. C-2, High Flux Power Range Monitor C. C-3, Overtemperature Delta-T D. C-4, Overpower Delta-T [1] PLACE [HS-85-5110], Rod Control Mode Selector in the MANUAL position. 1st CV [2] VERIFY Rod Speed Indicator [SI-412], indicates 48 Steps/minute. 1st CV [3] IF control rod movement is required, THEN ADJUST position using [HS-85-5111], Rod Control Switch. 1st CV [4] IF it is desired to leave [HS-85-5110], Rod Control Mode Selector in Manual for an extended period of time, THEN PLACE this Section in the Active Procedures Book. [5] WHEN it is desired to place [HS-85-5110], Rod Control Mode Selector to Automatic, THEN GO TO Section 6.4. End of Section 6.5

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 54 of 77 Unit Date - - - - 7.0 SHUTDOWN 7.1 Removing the MG Set A From Service [1] IF MG Set B has been removed from service, THEN [a] ENSURE the control rods and shutdown rods are fully inserted into the core. NOTE: The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional Overcurrent Relay contacts. [b] IF the reactor trip breakers are CLOSED THEN

1. DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons

[HS-3-99A] and [HS-3-99B]

2. OPEN the reactor trip breakers.

3. RELEASE Feedwater Isolation Reset Pushbuttons [HS-3-99Al and [HS-3-99B]

CAUTION Opening GENERATOR or MOTOR breaker of an MG Set that is to remain in service will result in a reactor trip. [2] OPEN MG Set A Load (GENERATOR) Breaker 52-1 USING [HS-85-121. D NOTE Voltage will be maintained for a short time after opening the motor circuit breaker due to an intended time delay. [3] STOP CRD MG Set A by placing MOTOR Breaker 52A Circuit Control in the TRIP position USING [HS-85-1A]. D [4] VERIFY MG Set A speed decreases. End of Section 7.1

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 55 of 77 Unit Date 7.2 Removing the MG Set B From Service [1] IF MG Set A has been removed from service, THEN [a] ENSURE the control rods and shutdown rods are fully inserted into the core. NOTE: The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional Overcurrent Relay contacts. [b] IF the reactor trip breakers are CLOSED THEN

1. DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons [HS-3-99A]

and [HS-3-99Bl

2. OPEN the reactor trip breakers.

3. RELEASE Feedwater Isolation Reset pushbuttons [HS-3-99A] and [HS-3-99Bl.

CAUTION Opening GENERATOR or MOTOR breaker of an MG Set that is to remain in service will result in a reactor trip. [2] OPEN MG Set B Load (GENERATOR) Breaker 52-2 USING [HS-85-221. D NOTE Voltage will be maintained for a short time after opening the motor circuit breaker due to an intended time delay. [3] STOP CRD MG Set B by placing MOTOR Breaker 52B Circuit Control in the TRIP position USING [HS-85-1 B]. D [4] VERIFY MG Set B speed decreases. End of Section 7.2

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 56 of 77 Unit Date 8.0 INFREQUENT OPERATION 8.1 Alternate Method of Paralleling MG Set A CAUTION This method should only be used if one unit is on line and providing for a load that may cause too great a speed difference to synchronize, and parallel operation is deemed necessary. [1] OBTAIN Shift Manager's approval to perform this method of paralleling MG Set A.

                                                                         /         /

SM/SRO Date Time [2] ENSURE Section 6.1 has been completed. D [3] ENSURE CRDM MG Set A Directional Overcurrent Relay Target Coils are RESET (Panel Pushbutton). (N/A other Unit) Relay INITIALS [1-RLY-085-DE/4D/Al (67A) [1-RLY-085-DE/4D/Cl (67C) [2-RLY-085-DG/4D/A] (67A) [2-RLY-085-DG/4D/Cl (67C) [4] ENSURE targets for CRDM MG Set A Directional Overcurrent Relays are RESET (Mechanical Linkage on relay). (N/A other Unit) Relay INITIALS [1-RLY-085-DE/4D/Al (67A) [1-RLY-085-DE/4D/C] (67C) [2-RLY-085-DG/4D/A] (67A) [2-RLY-085-DG/4D/Cl (67C) [5] PLACE CRD MG Set A MOTOR Breaker 52A Circuit Control [HS-85-1Al in the TRIP position. D [6] VERIFY MG Set A speed decreases. D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 57 of 77 Unit Date 8.1 Alternate Method of Paralleling MG Set A (Continued) [7] IF MG Sets are paralleled, THEN [a] PLACE Gen No.1 SYNCHRONIZE Switch [HS-85-12B] in the OFF position. D [b] ENSURE target for CRD MG Set A Mtr Bkr 52A is RED by placing the MOTOR breaker circuit control [HS-85-1Al in the CLOSE position. D [c] IF digital meters were used in Section 6.1, THEN A. ENSURE all digital meters are removed. _ _ / __ 1st CV B. 'ENSURE the MG Set panel doors are closed. 1st CV [d] ENSURE target for CRD MG Set A Load (GENERATOR) Bkr 52-1 is RED by placing the GENERATOR breaker circuit control in the CLOSE position. D [8] IF MG Set A does NOT parallel, THEN REPEAT Section 6.1 as required to synchronize MG Sets. [9] CHECK all Power, Logic, and Hold cabinets for alarm lights. D End of Section 8.1

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 58 of 77 Unit Date _ 8.2 Alternate Method of Paralleling MG Set B CAUTION This method should only be used if one unit is on line and providing for a load that may cause too great a speed difference to synch, and parallel operation is deemed necessary. [1] OBTAIN Shift Manager's approval to perform this method of paralleling MG Set B.

                                                                          /        /

SM/SRO Date Time [2] ENSURE Section 6.2 has been completed. D [3] ENSURE CRDM MG Set B Directional Overcurrent Relay Target Coils are RESET (Panel Push~utton). (N/A other Unit) Relay INITIALS [1-RLY-085-DF/3B/A] (67A) [1-RLY-085-DF/3B/C] (67C) [2-RLY-085-DH/3B/Al (67A) [2-RLY-085-DH/3B/Cl (67C) [4] ENSURE targets for CRDM MG Set B Directional Overcurrent Relays are RESET (Mechanical Linkage on relay). (N/A other Unit) Relay INITIALS [1-RLY-085-DF/3B/Al (67A) [1-RLY-085-DF/3B/C] (67C) [2-RLY-085-DH/3B/Al (67A) [2-RLY-085-DH/3B/Cl (67C) [5] PLACE CRD MG Set B MOTOR Breaker 528 Circuit Control [HS-85-1 B] in the TRIP position. D [6] VERIFY MG Set 8 speed decreases. D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 59 of 77 Unit Date- - - - 8.2 Alternate Method of Paralleling MG Set B (Continued) [7] IF MG Sets are paralleled, THEN [a] PLACE [HS-85-22Bl Gen NO.2 SYNCHRONIZE Switch in the OFF position. D [b] ENSURE target for CRD MG Set B Mtr Bkr 52B is RED by placing the MOTOR breaker circuit control [HS-85-1 B] in the CLOSE position. D [c] IF digital meters were used in section 6.2, THEN

1. ENSURE all digital meters are removed. __ I_-

1st CV

2. ENSURE the MG Set panel doors are closed.

1st CV [d] ENSURE target for CRD MG Set B Load (GENERATOR) Bkr 52-2 is RED by placing the GENERATOR breaker circuit control in the CLOSE position. D [8] IF MG Set B does NOT parallel, THEN REPEAT Section 6.2 as required to synchronize MG Sets. [9] CHECK all Power, Logic, and Hold cabinets for alarm lights. D End of Section 8.2

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 60 of 77 Unit Date _ 8.3 Resetting Step Counters After Withdrawing Rods Above 231 Steps

                                                     ~ Ramp Up Button
                                                     ~ Step Down Button
                                                     ~ Reset to Zero LCD Step Counter

[1] DEPRESS the affected group step counter "Step Down Button" to obtain 231 on display. [2] IF the affected bank is a control bank, THEN NOTIFY IMs to: [a] UPDATE the Pulse-to-Analog converter. D [b] CHECK the bank overlap unit in the logic cabinet. D [c] CHECK Master Cycler and UPDATE as needed. D [3] ENSURE Plant computer points for rod bank position are UPDATED using the following computer points: COMPUTER PT ROD BANK ~ U0049 Control A D U0050 Control B D U0051 Control C D U0052 Control D D U0053 Shutdown A D U0054 Shutdown B D U0055 Shutdown C D UOO56 Shutdown D D End of Section 8.3

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 61 of 77 Unit Date- - - - 8.4 Resetting Step Counters After Inserting Rods Below 0 Steps

                                             ~   Ramp Up Button
                                             ~ Step Down Button
                                             ~ Reset to Zero LCD Step Counter NOTE           Depressing the "Ramp Up Button" will cause a rapid change in the display.

[1] MOMENTARILY DEPRESS the affected group step counter "Ramp Up Button" to obtain 0 on display. [2] IF the affected bank is a control bank, THEN NOTIFY IMs to: [a] UPDATE the Pulse-to-Analog converter. D [b] CHECK the bank overlap unit in the logic cabinet. D [c] CHECK Master Cycler and UPDATE as needed. D [3] ENSURE Plant computer points for rod bank position are UPDATED using the following computer points: COMPUTER PT ROD BANK ~ UOO49 Control A D U0050 Control B D UOO51 Control C D UOO52 Control D D UOO53 Shutdown A D UOO54 Shutdown B D UOO55 Shutdown C D U0056 Shutdown D D End of Section 8.4

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 62 of 77 Unit Date- - - - 8.5 Placing MG Set A In Service for Maintenance [1] ENSURE clearance in place to isolate power to Rod Control coils on reactor head AND RECORD Hold Order Number. [2] START CRD MG Set A by placing [HS-85-1Al MOTOR Breaker 52A Circuit Control in the CLOSE position. NOTE Allow 15 seconds for the MG set to obtain full rated speed. [3] VERIFY generator speed increasing. [4] WHEN generator has increased to full speed, THEN [a] DEPRESS AND HOLD Gen Field Flash pushbutton. [b] WHEN voltage is > 250 volts, THEN RELEASE Gen Field Flash pushbutton. [5] IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with WTV Reg to a nominal 260 volts. NOTE Voltage may vary slightly between phases. [6] CHECK voltage approximately equal on all phases using voltmeter selector switch.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 63 of 77 Unit Date _ 8.5 Placing MG Set A In Service for Maintenance(Continued) [7] WHEN Maintenance requires MG Set A Load Breaker to be closed, THEN PERFORM the following: NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker. [a] ENSURE MG Set A Load (GENERATOR) Breaker 52-1 [BCTF-85-121 is RACKED IN. [b] ENSURE MG Set B Load (GENERATOR) Breaker 52-2 [BCTF-85-221 is RACKED IN. [c] ENSURE CRDM MG Set A Directional Overcurrent Relay Target Coils are RESET (Panel Pushbutton). (N/A other Unit) Relay INITIALS [1-RLY -085-DE/4D/A] (67A) [1-RLY-085-DE/4D/Cl (67C) [2-RLY -085-DG/4D/Al (67A) [2-RLY -085-DG/4D/Cl (67C) [d] ENSURE targets for CRDM MG Set A Directio~al Overcurrent Relays are RESET (Mechanical Linkage on relay). (N/A other Unit) Relay INITIALS [1-RLY -085-DE/4DIAl (67A) [1-RLY-085-DE/4D/C] (67C) [2-RLY-085-DG/4D/Al (67A) [2-RLY -085-DG/4D/Cl (67C)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 64 of 77 Unit Date _ 8.5 Placing MG Set A In Service for Maintenanee(Continued) NOTE Generator voltage will drop slightly as the electrical load increases. [e] CLOSE MG Set A Load (GENERATOR) Breaker 52-1 USING [HS-85-12]. [f] IF MG Set A Load breaker 52-1 trips due to Directional Overcurrent Relay operation, THEN [1] RESET Directional Overcurrent Relays with Relay Target Reset Button on Relay panel. [2] RESET Directional Overcurrent Relay Targets. [3] RECLOSE MG Set A load Breaker 52-1 USING [HS-85-12]. [4] IF another trip of breaker 52-1 occurs, THEN REPEAT substeps [a], [b] and [e]. [5] IF breaker 52-1 trips the third time, THEN NOTIFY SM and System Engineering for assistance. [8] WHEN MAINTENANCE requires reactor trip/bypass breakers to be closed, THEN PERFORM the following: [a] ENSURE [1CB], Auxiliary 150-VAC Supply to Rod Drive System is CLOSED. (located in Panel L-115). [b] ENSURE lift coil disconnect switches, for Control Rods and Shutdown Rods are in the CONNECTED position (located on M-8).

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 65 of 77 Unit Date _ 8.5 Plac-ing MG Set A In Service for Maintenance(Continued) CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4) should never be held in STARTUP position for any extended period of time. Holding this switch in STARTUP position may cause damage to the counters. [c] MOMENTARILY PLACE [SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System, AND VERIFY group step counters are at zero steps. [d] ENSURE Reactor Trip Bypass breakers are in required alignment per Maintenance Procedure: BYPASS RACKED IN RACKED OUT BREAKER (~) (~) BYA D D BYB D D [e] ENSURE Reactor Trip breakers are in required alignment per Maintenance Procedure: TRIP RACKED IN RACKED OUT BREAKER (~) (~) RTA D D RTB D D [f] ENSURE control power is ON by GREEN indicating lights on M-4: (NA breakers not racked in) GREEN BREAKER INITIALS LIGHT RTA ON RTB ON BYA ON BYB ON

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 66 of 77 Unit Date- - - - 8.5 Placing MG Set A In Service for Maintenance(Continued) [g] ENSURE Rod Control switch [HS-85-5111] is in MID position. [h] IF unit is in Mode 3,THEN ENSURE requirements of Tech Spec 3.4.1.2 are met. [i] DEPRESS and HOLD FW Isol Reset pushbuttons [HS-3-99Al and [HS-3-99Bl.[C.1] U] IF maintenance being performed on Unit 1, THEN CLOSE Rx Trip Breakers by placing [1-RT-11, to CLOSE position. [k] IF maintenance being performed on Unit 2, THEN CLOSE Rx Trip Breakers by placing [2-HS-99-7], to CLOSE position. [I] VERIFY Reactor Trip Breakers/Reactor Trip Bypass breakers CLOSED by RED indicating lights on M-4: (NA breakers not closed) BREAKER RED LIGHT INITIALS RTA ON RTB ON BYA ON BYB ON [m] RELEASE FW Isol Reset pushbuttons [HS-3-99Al and [HS-3-99B].[C.1] [n] NOTIFY IMs to perform 1,2-PI-IFT-099-0P4.0, Verification of P4 Contacts.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 67 of 77 Unit Date _ 8.5 Placing MG Set A In Service for Maintenance(Continued) [9] WHEN desired to shutdown MG Set A, THEN PERFORM the following: NOTE The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional Overcurrent Relay contacts. [a] IF the reactor trip breakers are CLOSED, THEN

1. DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons

[HS-3-99Al and [HS-3-99B].

2. OPEN the reactor trip breakers.

3. RELEASE Feedwater Isolation Reset Pushbuttons [HS-3-99Al and [HS-3~99B].

[b] OPEN MG Set A Load (GENERATOR) Breaker 52-1 USING [HS-85-12]. NOTE Voltage will be maintained for a short time after opening the motor circuit breaker due to an intended time delay. [c] STOP CRD MG Set A by placing MOTOR Breaker 52A Circuit Control in the TRIP position USING [HS-85-1A]. [d] VERIFY MG Set A speed decreases.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 68 of 77 Unit Date _ 8.5 Placing MG Set A In Service for Maintenance(Continued) NOTE The following step maybe NA if returned to normal by the clearance process. [10] WHEN maintenance complete, AND Reactor Trip and Bypass breakers ready to return to normal, THEN PERFORM the following: [a] ENSURE Reactor Trip Bypass breakers BYA and BYB are OPEN and RACKED OUT. BYPASS RACKED OUT BREAKER OPEN (~) (~) BYA D D BYB D D [b] ENSURE Reactor Trip breakers are RACKED IN: TRIP RACKED IN BREAKER (~) RTA D RTB D [c] NOTIFY IMs to perform 1 ,2-PI-IFT-099-0P4.0, Verification of P4 Contacts. End of Section 8.5

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 69 of 77 Unit- - - - - - Date 8.6 Placing MG Set B In Service for Maintenance [1] ENSURE clearance in place to isolate power to Rod Control coils on reactor head AND RECORD Hold Order Number. [2] START CRD MG Set 8 by placing [HS-85-1 B] MOTOR Breaker 528 Circuit Control in the CLOSE position. D NOTE Allow 15 s~conds for the MG set to obtain full rated speed. [3] VERIFY generator speed increasing. [4] WHEN generator has increased to full speed, THEN [a] DEPRESS AND HOLD Gen Field Flash pushbutton. [b] WHEN voltage is > 250 volts, THEN RELEASE Gen Field Flash pushbutton. [5] IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with WTV Reg to a nominal 260 volts. NOTE Voltage may vary slightly between phases. [6] CHECK voltage approximately equal on all phases using voltmeter selector switch.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 70 of 77 Unit- - - - - - Date- - - - 8.6 Placing MG Set B In Service for Maintenance [7] WHEN Maintenance requires MG Set B Load Breaker to be closed THEN PERFORM the following: NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker. [a] ENSURE MG Set A Load (GENERATOR) Breaker 52-1 [BCTF-85-12l is RACKED IN. [b] ENSURE MG Set B Load (GENERATOR) Breaker 52-2 [BCTF-85-22l is RACKED IN. [c] ENSURE CRDM MG Set B Directional Overcurrent Relay Target Coils for are RESET (Panel Pushbutton). (N/A other Unit) Relay INITIALS [1-RLY-085-DF/3B/A] (67A) [1-RLY-085-DF/3B/C] (67C) [2-RLY-085-DH/3B/Al (67A) [2-RLY-085-DH/3B/C] (67C) [d] ENSURE targets for CRDM MG Set B Directional Overcurrent Relays are RESET (Mechanical Linkage on relay). (N/A other Unit) Relay INITIALS [1-RLY-085-DF/3B/A] (67A) [1-RLY-085-DF/3B/Cl (67C) [2-RLY-085-DH/3B/A] (67A) [2-RLY-085-DH/3B/Cl (67C)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 71 of 77 Unit- - - - - - Date _ 8.6 Placing MG SetB In Service for Maintenance NOTE Generator voltage will drop slightly as the electrical load increases. [e] CLOSE MG Set B Load (GENERATOR) Breaker 52-2 USING [HS-85-22]. [f] IF MG Set B Load breaker 52-2 trips due to Directional Overcurrent Relay operation, THEN [1] RESET Directional Overcurrent Relays with Relay Target Reset Button on Relay panel. [2] RESET Directional Overcurrent Relay Targets. [3] RECLOSE MG Set A load Breaker 52-2. [4] IF another trip of breaker 52-2 occurs, THEN REPEAT substeps [a], [b] and [c]. [5] IF breaker 52-2 trips the third time, THEN NOTIFY SM and System Engineering for assistance. [8] WHEN MAINTENANCE requires reactor trip/bypass breakers to be closed, THEN PERFORM the following: [a] ENSURE [1CB], Auxiliary 150-VAC Supply to Rod Drive System is CLOSED. (located in Panel L-115). [b] ENSURE lift coil disconnect switches, for Control Rods and Shutdown Rods are in the CONNECTED position (located on M-8).

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 72 of 77 Unit- - - - - - Date- - - - 8.6 Placing MG Set B In Service for Maintenance CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4) should never be held in STARTUP position for any extended period of time. Holding this switch in STARTUP position may cause damage to the counters. [c] MOMENTARILY PLACE [SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System, AND VERIFY group step counters are at zero steps. [d] ENSURE Reactor Trip Bypass breakers are in required alignment per maintenance procedure. BYPASS RACKED IN RACKED OUT BREAKER (~) (~) BYA D D BYB D D [e] ENSURE Reactor Trip breakers are in required alignment per main. tenance proce d ure. TRIP RACKED IN RACKED OUT BREAKER (~) (~) RTA D D RTB D D Cco, [f] ENSURE control power is ON by GREEN indicating lights on M-4: (NA breakers not racked in) GREEN BREAKER INITIALS LIGHT RTA ON RTB ON BYA ON BYB ON [g] ENSURE Rod Control switch [HS-85-51111 is in MID position.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 73 of 77 Unit Date _ 8.6 Placing MG Set B In Service for Maintenance [h] IF unit is in Mode 3,THEN ENSURE requirements of Tech Spec 3.4.1.2 are met. [i] DEPRESS and HOLD FW Isol Reset pushbuttons [HS-3-99Al and [HS-3-99Bl.[C.1] [j] IF maintenance being performed on Unit 1, THEN CLOSE Rx Trip Breakers by placing [1-RT-1], to CLOSE position. [k] IF maintenance being performed on Unit 2, THEN CLOSE Rx Trip Breakers by placing [2-HS-99-7], to CLOSE position. [I] VERIFY Reactor Trip Breakers/Reactor Trip Bypass breakers CLOSED by RED indicating lights on M-4: (NA breakers not closed) BREAKER RED LIGHT INITIALS RTA ON RTB ON BYA ON BYB ON [m] RELEASE FW Isol Reset pushbuttons [HS-3-99A] and [HS-3-99B].[C.1] [n] NOTIFY IMs to perform 1,2-PI-IFT-099-0P4.0, Verification of P4 Contacts.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 74 of 77 Unit Date _ 8.6 Placing MG Set B In Service for Maintenance [9] WHEN desired to shutdown MG Set B, THEN PERFORM the following: NOTE The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional Overcurrent Relay contacts. [a] IF the reactor trip breakers are CLOSED, THEN

1. DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons

[HS-3-99A] and [HS-3-99B]

2. OPEN the reactor trip breakers.

3. RELEASE Feedwater Isolation Reset Pushbuttons [HS-3-99Al and [HS-3-99Bl

[b] OPEN MG Set B Load (GENERATOR) Breaker 52-2 USING [HS-85-22]. NOTE Voltage will be maintained for a short time after opening the motor circuit breaker due to an intended time delay. [c] STOP CRD MG Set B by placing MOTOR Breaker 52B Circuit Control in the TRIP position. USING [HS-85-1B]. [d] VERIFY MG Set B speed decreases.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 75 of 77 Unit Date- - - - 8.6 Placing MG Set B In Service for Maintenance NOTE The following step maybe NA if returned to normal by the clearance process. [10] WHEN maintenance complete AND Reactor Trip and Bypass breakers ready to return to normal, THEN PERFORM the following: [a] ENSURE Reactor Trip Bypass breakers BYA and BYB are OPEN and RACKED OUT. BYPASS RACKED OUT BREAKER OPEN (-V) (~) BYA D D BYB D D [b] ENSURE Reactor Trip breakers are RACKED IN: TRIP RACKED IN BREAKER (~) RTA D RTB D [c] NOTIFY IMs to perform 1,2-PI-IFT-099-0P4.0, Verification of P4 Contacts. End of Section 8.6

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 76 of 77 9.0 RECORDS A. Completed copies of sections shall be transmitted to the Operations Superintendent's Secretary.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 77 of 77 SOURCE NOTES Page 1 of 1 IMPLEMENTING REQUIREMENTS REQUIREMENTS STATEMENT DOCUMENT STATEMENT [C.1] NC00940183003 Revised procedure to require feedwater 8Q94026311 isolation reset buttons to be held during LER327/94005 closure of reactor trip breakers. [C.2] LER328/94008 Revised procedure to operate the thrust switch in a more conservative method to minimize the possibility of step deviations greater than two steps during initial rod movement.

0. JPM B.1.d Page 10f 9 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORM*ANCE MEASURE B.1.d JPM FILLI'NG AND VENTING EXCESS LETDOWN PREPAREDI REVISED BY: Date/ VALIDATED BY:

Date/

APPROVED BY: Date/ (Operations Training Manager) CONCURRED: ** Date/ (Operations Representative)

Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.

             ** Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM B.1.d Page 2 of 9 Rev. 0 I NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPAREDI NUMBER REVISION AFFECTED REVISED BY: 0 New Y All v- Specify if the JPM change will require another validation (Y or N). See cover sheet for criteria.

JPM B.1.d Page 3 of 9 Rev. 0 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task: Filling and Venting Excess Letdown JAITA task:

       # 0040160101 (RO)      Place Excess Letdown in Service KIA Ratings:

004 Chemical And Volume Control System A4 Ability to manually operate and/or monitor in the control room (CFR 41.7 / 45.5 to 45.8) A4.06 Letdown isolation and flow control valves 3.6 / 3.1 Task Standard:

1) Excess letdown is filled and vented in accordance with 1-S0-62-6, Excess Letdown, section 8.1 Evaluation Method: Simulator __X _ In-Plant _

=======================================================================

Performer: NAME Start Time _ Performance Rating: SAT UNSAT Performance Time Finish Time _ Evaluator: SIGNATURE DATE

========.===============================================================

COMMENTS

JPM B.1.d Page 4 of 9 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Sequenced steps identified by an "s"

2. Any UNSAT requires comments

3. This task is to be performed using the simulator in Ie 6.

4. Ensure operator performs the following required actions for SELF-CHECKING;

a. Identifies the correct unit, train, component, etc.

b. Reviews the intended action and expected response.

c. Compares the actual response to the expected response.

Validation Time: CR. 9 min Local - - - - - Tools/Equipment/Procedures Needed: 1-S0-62-6

References:

Title Rev ~~o.

1. 1-S0-62-6 Excess Letdown 16

.===========================================================================

READ TO OPERATOR Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job* performance measure will be satisfied. Ensure you indicate. tome when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. Plant is in Mode 3.

2. Excess letdown system has been out of service for maintenance.

3. The work is complete and the system is ready to be filled and vented.

2. You are an extra RO on shift INITIATING CUES:

1. The SRO has directed you to fill and vent Excess Letdown.

2. You are to notify the SRO when you have completed filling and venting Excess Letdown in accordance with1-S0-62-6, Excess Letdown.

3. Section 4, Prerequisites Actions, has been completed.

JPM B.1.d Page 50f9 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 1.: Obtain the appropriate procedure. - SAT

                                                                                             -     UNSAT STANDARD:     Operator identifies 1-S0-62-6 and goes to section 8.1 "Filling and Venting Excess Letdown".

Start Time- - COMMENTS: STEP 2.: NOTE An AUO at panel O-L-2 will be needed to observe an increase in the - SAT RCDT level.

                                                                                              -     UNSAT Cue: When AUO is directed to O-L-2, Acknowledge the direction STANDARD: An AUO is directed to be stationed at panel O-L-2 to observe RCDT level.

COMMENTS: STEP 3.: [1] ENSURE [1-FCV~70-143] CCS water to Excess Letdown Heat Exchanger is - SAT OPEN.

                                                                                               -    UNSAT STANDARD:    Candidate determines l-FCV-70-143 is open by the red light lit above 1-HS~70-143A, EXCESS LETDOWN HX INLET ISOL, on O-M-278.

COMMENTS: STEP 4.: [2] OPEN [1-FCV-70-85] Excess Letdown Heat Exchanger CCS Flow Control. - SAT

                                                                                                -   UNSAT STANDARD:     Candidate places 1-HS-70-85A, EXCESS LETDOWN HX OUTLET ISOL, to the OPEN position on O-M-278 and Holds until the valve is full open (red light is lit and the green light light is dark.)                             Criti.cal Step COMMENTS:

JPM B.1.d Page 6 of 9 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 5.: [3] PLACE [1-FCV-62-59] Excess Letdown 3-way Divert Valve in DIVERT. - SAT

                                                                                                 -    UNSAT STANDARD: Candidate places 1-HS-62-59, EXCESS LTDN DIVERT, to the DIVERT position on 1-M-5. Right side red light will be lit, left side red light will be dark.                                                                               Critical
                                                                                                    .Step COMMENTS:

STEP 6.: [4] OPEN [1-FCV-62-54] Cold Leg Loop #3 Excess Letdown Isolation Valve. - SAT

                                                                                                 -    UNSAT STANDARD: Candidate places 1-HS-62-54A, Excess Letdown Isolation, to the OPEN position on 1-M-5. Red light above handswitch will be lit.

Critical COMMENTS: Step STEP 7.: [5] OPEN [1-FCV-62-55] Excess Letdown Containment Isolation Valve. - SAT

                                                                                                  -    UNSAT STANDARD: Candidate places 1-HS-62-55A, Excess Letdown Isolation, to the OPEN position on 1-M-5. Red light above handswitch will be lit.

Critical Step COMMENTS:

JPM B.1.d Page 7 of 9 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 8.: [6] OPEN [1-FCV-62-S6] Excess Letdown Flow Control Valve. - SAT Note: The procedure contains this note prior to the step - UNSAT "NOTE At the completion of step [6] a timed duration will be initiated." Cue: After the FCV is opened, state that 5 minutes has elapsed. Critical Step STANDARD: Candidates rotates handswitch 1-HIC-62-56, Excess LTDN Flow Control Valve, to the counter-clockwise to greater than the '0" position on 1-M-5. Evaluator Note: Temperature and pressure rise will be indicated on 1- TI-62-58 and 1-PI-62-57 respectively Cue: If Excess Letdown Hx Temp alarm comes in, state that the temperature is high but has stabilized. COMMENTS: STEP 9.: [7] OBSERVE level increase in RCDT for 5 minutes - SAT

                                                                                                -      UNSAT Cue: When AUO contacted, state "The RCDT level has been continuously increasing for the last 5 minutes-"

STANDARD: AUO is contacted to monitor RCDT level. (RDCT level can also be monitored on the ICS) COMMENTS: STEP 10.: 8] WHEN 5 minutes has elapsed, THEN CLOSE [1-FCV-62-S6] Excess - SAT Letdown Flow Control Valve.

                                                                                                  -     UNSAT STANDARD:        Candidates rotates handswitch 1-HIC-62-56, Excess LTDN Flow Control Valve, on 1-M-5, clockwise to the '0" position.                                   Critical Step COMMENTS:

JPM B.1.d Page 8 of 9 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 11.: [9] CLOSE the following valves: SAT VALVE UlENTIFICATIO:N lNITIAlS UNSAT l-FCV-62-55 Ex.;cl:.s.s Letdklvm Conlainrnent Isolaticn l-FCV-02.. Et4. C,old Leg Loc:p #3 Exc~ss Letdown Is*o.~-aiic:n Critical Step l-FCV-7"G'-B5 Ex:Css LetdCfim Heat Exchang?ef" CCS FCV Cue: If IV is requested, state "An individual will be assigned to performed the IV" STANDARD: Candidate closes the the listed valves by placing the respective handswitches (1-HS-62-55 & 1-HS-62-54 on 1-M-5, and 1-HS-70-85 on 0-M-27B)to the CLOSE position. Red light will go dark and green light will be lit. COMMENTS: STEP 12.: [10] PLACE [1-FCV-62-59] Excess Letdown 3-way Divert Valve in NORMAL. SAT UNSAT STANDARD: Candidate places 1-HS-62-59, EXCESS LTDN DIVERT, on 1-M-5 to the NORMAL position. Right side red light will be dark, left side red light will Critical be lit. Step COMMENTS: STEP 13.: Notifcation of completion of 1-S0-62-7 is made to the SRO. SAT UNSAT STANDARD: SRO is notified that Excess Letdown is filled and vented. Stop Time_ _ COMMENTS: End of JPM

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO TRAINEE:' I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. IN.ITIAL CONDITIONS:

1. Plant is in Mode 3~

2. Excess letdown system has been out of service for maintenance.

3. The work is complete and the system is ready to be filled and vented.

2. You are an extra RO on shift.

INITIATING CUES:

1. The SRO has directed you to fill and vent Excess Letdown.

2. You are to notify the SROwhen YO'u have completed filling and venting Excess Letdown in accordance with 1-S0-62-6, Excess Letdown.

3. Section 4, Prerequisites Actions, has been completed.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION 1-50-62-6" EXCESS LETDOWN Revision 16 QUALITY RELATED MS LEENERTS RESPONSIBLE ORGANIZATION: OPERATIONS

w. T. LEARY APPROVED BY:---------...;..~~;;;...;.;...~_----

EFFECTIVE DATE: 06/05/07 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION: Revised Attachment 2 to change position of 1-70-702C from CLOSED & CAPPED to LOCKED CLOSED & CAPPED and changed verification from IV to CV (NB070420). THIS PROCEDURE COULD AFFECT REACTIVITY

SQN EXCESS LETDOWN 1-S0-62-6 Rev: 16 1 Page 2 of 14 TABLE OF CONTENTS Page 1 of 1 Section Title Page

1.0 INTRODUCTION

3 1.1 Purpose*................................................................................................................. 3 1.2 Scope 3

2.0 REFERENCES

3 2.1 Performance* References..... 3 2.2 Developmental References.................................... 3 3.0 PRECAUTIONS AND LIMITATIONS 4 4.0 PREREQUISITE ACTIONS 5 5.0 STARTUP/STANDBY READINESS 6 6.0 N*ORMAL OPERATION 9 7.0 SHUTDOWN 10 8.0 INFREQUENT OPERATION 12 8.1 Filling and Venting Excess Letdown 12 9.0 RECORDS 14 ATTACHMENTS ATTACHMENT 1: POWER CHECKLIST 1-62-6.01 ATIACHMENT 2: VALVE CHECKLIST 1-62-6.02

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 30f 14

1.0 INTRODUCTION

1.1 Purpose To provide instructions for the operation of excess letdown. 1.2 Scope A. Placing excess letdown in service. B. Ta-king excess letdown out of service.

2.0 REFERENCES

2.1 Performance References None. 2.2 Developmental References A. 801-62.1, Chemical and Volume Control System B. 1-80-62-1, Chemical and Volume Control System C. TVA Drawings

1. 47W809-1

2. 47W859-2 D. SQN-VTM-1201-0010 Grinnell Valve vendor manual

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 4 of 14 3.0 PRECAUTIONS AND LIMITATIONS A. Failureto observe all posted radiation control requirements may lead to unnecessary radiation absorbed doses. B. When placing Excess Letdown in service to replace normal letdown, the charging flow temperature may cool enough to lower the ReS average temperature and may cause a change in reactivity. C. The fluid outlet temperature of the excess letdown heat exchanger-should not exceed 200°F. The maximum allowable temperature is 250°F. D. While placing the excess letdown heat exchanger in service the Rep seal leakoff flow may fluctuate, therefore periodic monitoring should be maintained. E. When Excess Letdown is placed in service an approximate increase of 100 CPM maybe observed on 1-RM-90-106A. This elevated radiation monitor reading should start to trend back to normal after approximately one hour. F. Operation of Excess Letdown with 1-TI-62-58 (Excess Letdn Temp) greater than 200°F will require that Systems Engineering be notified so that an evaluation of Grinnell valve maintenance can be conducted.

SQN EXCESS LETDOWN 1-S0-62-6 Rev: 16 1 Page 5 of 14 Date 4.0 PREREQUISITE ACTIONS NOTE Throughout this Instruction, where an IFITHEN statement exists, the step should be N/A if condition does not exist. [1] ENSURE Instruction to be used is a copy of effective version. [2] VERIFY CVCS system is in service in accordance with Valve Checklists 1-62-1.03 and 1-62-1.04. [3] ENSURE Attachment 1, Power Checklist 1-62-6.01 has been completed. [4] ENSURE Attachment 2, Valve Checklist 1-62-6.02 has been completed. [5] ENSURE Precautions and Limitations, Section 3.0 have been reviewed. [6] ENSURE each performer documents their name and initials:

               /""\        Print Name                         Initials I
            ~/'

('~ /t~~3 b/'t:>oK,5 ;;) [7] INDICATE below which performance section of this instruction will be used and the reason for this performance: o 5.0 STARTUP/STANDBY READ.INESS o 7.0 SHUTDOWN W8.0 INFREQUENT OPERATION REASON: ~c-l, c7 I

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 6of14 Date- - - - 5.0 STARTUP/STANDBY READINESS NOTE 1 When excess letdown is placed in service the containment radiation monitors may show some changes in particulate reading. NOTE 2 Coordinate the following steps with AUO stationed at O-L-2 to monitor RCDT for pump operation as required during the 50 gallon flush. [1] ENSURE [1-FCV-62-931 is in MANUAL and [a] OPERATE [1-FCV-62-931 USING [1-HIC-62-93A] as required to regulate charging flow to keep pressurizer level,on program. [b] OPERATE [1-FCV-62-89] USING [1-HIC-62-89A] as required to maintain Rep seal flows in limits. [2] NOTIFY RADCON that Excess Letdown is being placed in service. [3] ENSURE [1-FCV-70-1431 CCS water to the excess letdown heat exchanger is OPEN. [4] ENSURE [1-FCV-70-851 Excess Letdown Heat Exchanger CCS flow control valve is OPEN. NOTE Step [5] will prevent subjecting the cves piping downstream of the Excess Letdown HX to a temperature above the design value. [5] ENSURE [1-FI-70-841 is indicating greater than 230 gpm. [6] PLACE [1.-FCV-62-591 Excess Letdown 3-way Divert Valve in DIVERT.

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 7 of 14 Date- - - - 5.0 STARTUP/STANDBYREADINESS(Continued) CAUTION FCV 62-63 has replaced RCP seal leak-off isolation valves as the primary means for isolating seal flow. The normal letdown path for excess letdown will not be available if FCV-62-63 is CLOSED. NOTE Back flow through the RCP seals will occur should the RCP seal leakoff isolation valves fail to their OPEN position on loss of air or electrical p.ower. [7] IF less than 100 psig in RCS and [1-FCV-62-63l is CL*OSED and excess letdown will be aligned for NORMAL operation, THEN [a] ENSURE the following are CLOSED: VALVEID FUNCTION INITIALS 1-FCV-62-53 RCP's Seal Bypass 1-FCV-62-9 No. 1 Seal Return 1-FCV-62-22 NO.2 Seal Return 1-FCV-62-35 NO.3 Seal Return 1-FCV-62-48 NO.4 Seal Return [b] ENSURE [1-FCV-62-63]is OPEN. [8] OPEN [1-FCV-62-54] Cold Leg Loop #3 Excess Letdown isolation valve. [9] OPEN [1-FCV-62~55] Excess Letdown containment isolation valve.

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 8 of 14 Date- - - - 5.0 STARTUP/STANDBY READINESS(Continued) NOTE ICS point 1L2400A or the AUO stationed at 0-L-2 can be used to monitor RCDT for level increase during the 50 gallon flush. Reference the RCDT Level vs Volume table in TI-28. [10] OPEN [1-FCV-62-561 slowly to flush piping to RCDT. [11] WHEN approximately 50 gallons have flushed, THEN CLOSE [1-FCV-62-56], Excess Letdown Flow Control Valve. 1st IV [12] PLACE [1-FCV-62-59] Excess Letdown 3-way Divert Valve in NORMAL. 1st IV NOTE 1 Normally the temperature read on 1-TI-62-58 should be less than 200°F. If operation requires temperatures greater than 200°F, the pressure at 1-PI-62-64 (local indicator EI. 690 Pnl L-46) should be less than 100 psig to protect the Grinnell valves. NOTE 2 Operation above 200°F will require that Systems Engineering be notified to allow an evaluation of the need for valve maintenance. [13] OPEN [1-FCV-62-561 slowly to increase excess letdown flow to desired amount, not to exceed 240°F heat e*xchanger outlet temperature, as indicated on 1-TI-62-58. NOTE Placing Excess Letdown in service causes increased activity in various areas of the Auxiliary Building. [14] NOTIFY RADCON thatExcess Letdown has been placed in service. END OF TEXT

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 9 of 14 6.0 NORMAL OPERATION None.

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 10 of 14 Date 7.0 SHUTDOWN [1] IF letdown is to be placed in service, THEN RETURN to service per 1-S0-62-1. [2] C*LOSE [1-FCV-62-56] Excess Letd.own Heat Exchanger outlet valve. 1st IV [3] VERIFY [1-FCV-62-59] Excess Letdown 3-way valve in NORMAL. 1st IV [4] CLOSE [1-FCV-62-55] Excess Letdown containment isolation valve. 1st IV [5] CLOSE [1-FCV-62-54] Cold Leg Loop #3 Excess Letdown valve. 1st IV [6] IF charging is in service, THEN ADJUST seal injection flow to 6-11gpm using [1-FCV-62-89]. [7] IF auto operation is desired and system conditions will allow it, THEN PLACE [1-FCV-62-93] in AUTO. [8] NOTIFY RADCON that Excess Letdown is REMOVED from SERVICE.

SQN EXCES5LETDOWN 1-50-62-6 Rev: 16 1 Page 11 of 14 Date _ 7.0 SHUTDOWN [9] ENSURE [1-FCV-70-851 Excess Letdown HX CCS Flow Control Valve is CLOSED. 1st IV [10] ENSURE [1-HS-70-85Al is in the A-AUTO position. 1st IV [11] IF operation at greater than 200 of has occurred, THEN CONTACT Systems Engineering to evaluate Grinnell valve maintenance requirements. E*ND OF TEXT

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 12 of 14 Date- - - - 8.0" INFREQUENT OPERATION 8.1 Filling and Venting Excess Letdown NOTE An AUG at panel O-L-2 will be needed to observe an increase in the RCDT level. [1] ENSURE [1-FCV-70-1431 CCS water to Excess Letdown Heat Exchanger is OPEN. [2] OPEN [1-FCV-70-85l Excess Letdown Heat Exchanger CCS Flow Control. [3] PLACE [1-F"CV-62-59] Excess Letdown 3-way Divert Valve in DIVERT. [4] OPEN [1~FCV-62-54] Cold Leg Loop #3 Excess Letdown Isolation Valve. [5] OPEN [1-FCV-62-55] Excess Letdown Containment Isolation Valve. NOTE At the completion of step [6] a timed duration will be initiated. [6] OPEN [1-FCV-62-56] Excess Letdown Flow Control Valve. [7] OBSERVE level increase in RCDT for 5 minutes. [8] WHEN 5 minutes has elapsed, THEN CLOSE [1-FCV-62-561 Excess Letdown Flow Control Valve. 1st IV

SQN EXCESS LETDOWN 1-S0-62-6 Rev: 16 1 Page 13 of 14 Date------- 8.1 Filling and Venting Excess Letdown (Continued) [9] CLOSE the following valves: VALVE IDENTIFICATION INITIALS 1-FCV-62-55 Excess Letdown Containment Isolation st - IV 1~FCV-62-54 Cold Leg Loop #3 Excess Letdown Isolation st - IV 1-FCV-70-85 Excess Letdown Heat 'Exchanger CCS FCV st - IV [10] PLACE [1-FCV-62-59] Excess Letdown 3-way Divert Valve in NORMAL. 1st IV END OF TEXT

SQN EXCESS LETDOWN 1-S0-62-6 Rev: 16 1 Page 14 of 14 9.0 RECORDS Completed copies of all Sections shall be transmitted to the Operations Superintendents Secretary.

u. S c.... l S; a CD

JPM # 75AP Page 1 of 10 Rev. 8 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e JPM # 75-AP Steam Generator Tube Rupture (With MSIV Failure to Close) PREPAREDI REVISED BY: Date/ VALIDATED BY:

Date/

APPROVED BY: Date! (Operations Training Manager) CONCURRED: ** Date/ (Operations Representative)

Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.

             ** Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM # 75AP Page 2 of 10 Rev. 8 r NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/ NUMBER REVISION AFFECTED REVISED BY: 3 Transfer from WP. Minor enhancements. N 10/15/94 All HJ Birch 4 Incorporate Rev B changes. Changed to Y 9/16/95 All HJ Birch S/G #1 to force swap of TDAFW steam supply. pen/ink Added closed, to verify Atm Relief vlvs in N 12/7/95 5,6 HJ Birch auto. Also enhance standard for MSIV bypasses nota JPM critical task. E-O Rev chg only. N 2/6/97 4 HJ Birch pen/ink E~O revision had no impact N 8/11/98 All JP Kearney pen/ink E-O Rev chg only. N 9/23/99 4 SR Taylor pen/ink E-O Rev 22 chg only. E-3 Rev 12 minor N 09/05/01 ALL WR Ramsey changes 5 Incorporated pen/ink changes N 8/22/02 All J P Kearney 6 Updated to current revision and IC. N 8/10/04 All MG Croteau 7 Updated references and reordered steps N 10/28/200 ALL JJ Tricoglou to conform to the latest revision to E-3. 5 Deleted Critical Step 9 as this*step was deleted from the procedure 8 Update to E-3 rev 17, added candidate N All handout sheet, modified instructions and steps to reflect instruction revision and provide clarity. v - Specify if the JPM change will require another validation (Yor N). See cover sheet for criteria.

JPM # 75AP Page 3 of 10 Rev. 8 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task: Steam Generator Tube Rupture (With MSIV Failure to Close) JAlTA task # : 0000380501 (RO) KIA Ratings: 038EA1.32 (4.6 - 4.7) Task Standard: Steam Generator #1 isolated per E-3. Evaluation Method: Simulator __X_ _ In-Plant _

========================================================================

Performer:* NAME Start Time _ _-,-- Performance Rating: SAT UNSAT Performance Time Finish Time _ Evaluator: SIGNATURE DATE

========================================================================

COMMENTS

JPM # 75AP Page 4 of 10 Rev. 8 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Sequenced steps identified by an "s"

2. AnyUNSAT requires comments

3. Initialize simulator in IC #175.

4. If snapshot unavailable, then Initialize simulator in IC # 16 and Insert the following:

a. Activate malfunction IMF TH05A f:8.5 to initiate S/G tube rupture in S/G #1.

b. Activate malfunction IMF MS14A f:100, to fail open S/G Loop 1 MSIV.

c. Complete the actions of E-O thru step 12, which will transition the crews to E-3

d. Complete any required actions in ES-0.5. Including closing the TD AFW LCVs, but do not put handswitches in pull-to-Iock.

e. Complete the first three ste.ps in E-3.

f. Actuate a MANUAL reactor trip and safety injection, take all actions up through Step 3 of E-3.

5. Freeze the simulator until the operator is ready to begin the JPM.

6. Ensure operator performs the following required actions for SELF-CHECKING;

a. Identifies the correct unit, train, component, etc.

b. Reviews the intended action and expected response.

c. Compares the actual response to the expected response.

Validation Time: CR. 12 mins Local _ Tools/Equipment/Procedures Needed: E-3

References:

F~eference Rev No. A. E-O Reactor Trip or Safety Injection 29 B. E8-0.5 Equipment Verifications 0 C. E-3 Steam Generator Tube Rupture 17

=======================================================

Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS: Unit 1 has experienced a SGTR. A manual safety injection was initiated and E-O implemented. E-O and E.S-0.5 have been completed and a transition to E-3 has been made. Steps 1 through 3 of E-3 have been completed and S/G #1 has been identified as the ruptured S/G. INITIATING CUES: You are the eRO and are directed to continue with the actions/responses of 6-3, beginning at Step 4. Inform the SRO when you are ready to determine the Target Core Exit Thermocouple temperature.

JPM # 75AP Page 5 of 10 Job Performance Checklist: STEP/STANDARD SAT/UNSAT STEP 1.: Obtain appropriate copy of procedure. - SAT STANDARD: Operator obtains a copy of E-3 and continues at step 4 as directed. - UNSAT COMMENTS: Start Time- - STEP 2.: [4.a] ADJUST Ruptured S/Gs atmospheric relief controller setpoint to - SAT 87% in AUTO. (1040 psig)

                                                                                           -     UNSAT STANDARD: Operator adj.usts PIC-1-6A to 87% and ensures the controller is in auto.

Critical Step COMMENTS: SToEP 3.: [4.b] CHECK Ruptured S/G atmospheric relief handswitch in P-AUTO - SAT and CLOSED.

                                                                                            -    UNSAT STANDARD: Operator checks S/G #1 atmospheric relief HS, FCV-1-6, on 1-M-4in P-AUTO and checks green light LIT abovehandswitch.

COMMENTS: STEP 4: [4.c] CLOSE TD AFW pump steam supply from Ruptured S/G FCV - SAT 15 (S/G #1) or FCV-1-16 (SIG #4).

                                                                                             -   UNSAT STANDARD: Operator closes FCV-1-15 and verifies closed by GREEN light LIT ON 1-M-4 [Critical part of step]. May verify that FCV-1-16, S/G #4, auto opens or may open valve manually, approx 1 minute later, with red light    Critical Step LIT, not critical).

COMMENTS: STEP 4.: [4.d] VERIFY RupturedS/G blowdown isolation valves Closed. - SAT STANDARD: Operator verifies FCV-1-7 and FCV~1-181 CLOSED as indicated by - UNSAT green indication lights above handswitch 1-HS-1-7/181 on 1-M-4. COMMENTS:

JPM # 75AP Page 6 of 10 Job Performance Checklist: STEP/STANDARD SAT/UNSAT STEP 5.: [4.e] CLOSE Ruptured S/G MSIV and MSIV Bypass Valve. - SAT Note: SIG #1 MSIV will NOT close and the operator MUST go to theRNO - UNSAT column at this time. STANDARD: Attempts to close MSIV FSV-1-4. Recognizes the MSIV failed to close, by the red light LIT, and goes to RNO to isolate the S/G. COMMENTS: STEP 6.: [4.e.1] CLOSE IntactS/G MSIVs and MSIV bypass valves. - SAT Cue: When operator dispatches an AUO to close SG #1 MSIV with EA~1-1 UNSAT acknowledge the direction. Critical Step STANDARD: Operator closes intact S/G MSIVs and verifies their bypasses closed as indicated by blue and green lights LIT on HS-1-11 ,-22, & -29 MSIVs and Green lights LIT on HS-1-147,-148,-149,-150 bypasses. [Ensuring the bypasses closed is not a JPM critical task since valves are already closed.] COMMENTS: STEP 7.: [4.e.2] Dispatch operator to perform EA-1-1, Closing MSIVs Locally, for - SAT any MSIV or MSIV bypass valve which fails to close.

                                                                                                -   UNSAT Cue:         If operator dispatches an AUO to close SG #1 MS/V with EA-1-1 acknowledge the direction.

STANDAR.D: Operator dispatches an AUO to close MSIV FSV-1-4 using EA-1-1. COMMENTS: STEP 8.-: [4.e.3] Isolate steam header - SAT

PLACE Condenser steam dumps in OFF
ENSURE steam dump valves CLOSED. - UNSAT STANDARD: Operator verifies Condenser Steam dumps are closed as indicated by Critical Step green position indicating lights LIT on1-XX-55-4A and places the handswitch(s) 1-HS-1-1 03A and/or 1-HS-1-1 03B in the OFF position on 1-M-4.

COMMENTS:

JPM # 75AP Page 7 of 10 Job Performance Checklist: STEP/STANDARD SAT/UNSAT STEP 9.: CLOSE FCV-47-180, HP Steam Seal Supply Isolation - SAT STANDARD: Operator Verifies Steam seals closed as indicated by green light LIT on - UNSAT 1-HS-47-180 OR AUO dispatched to close local isolation valve on 1-M-2. Critical Step COMMENTS: STEP 10.: ENSURE FCV-47-181, HP Steam Seal Supply Bypass CLOSED. - SAT

                                                                                             -    UNSAT STAN.DARD: Operator Verifies HP steam to MFW pump turbine closed as indicated by green light LIT on 1-HS-47-181 on 1-M-2.

COMMENTS: STEP 11 ..: CLOSE MSR HP Steam supply isolation valves. - SAT

                                                                                              -    UNSAT STANDARD:    Operator closes HP steam to MSRs as indicated by green position indicating lights LIT on 1-XX-1-145, MSR HP Steam Supply Status,            Critical Step on 1-M-2 for each of the valves. Two valves on each of the six MSR's have to be closed from the handswitches on 1-M-2.

COMMENTS: STEP 12.: DISPATCH operator to locally isolate steam header USING EA- - SAT 1-4, Local Isolation of the Steam header in the Turb Bldg.

                                                                                               -   UNSAT C*ue:       When operator dispatches an AUO to isolate steam header USING EA-1-4, acknowledge the direction and provide feedback that the             Critical Step traps have been isolated per EA-1-4.

STANDARD: Operator directs AUO to isolate the steam header traps per*EA-1-4, Local Isolation of the Steam Header in Turb. Building. COMMENTS: STEP 13.: [4.e.4] USE intact S/Gs atmospheric relief for steam dumps. - SAT STANDARD: Operator addresses that the atmospheric reliefs will now have to use for - UNSAT RCS temp control. COMMENTS:

JPM # 75AP Page 8 of 10 Job Performance Checklist: STEP/STANDARD SAT/UNSAT STEP 14.: [5] MONITOR Ruptured S/G level: - SAT

a. CHECK narrow range level greater than 10 % [25 % ADV]

b. WHEN ruptured S/G level is greater than 10 % [25 % ADV] THEN - UNSAT STOP feed flow to Ruptured S/G.

1) STOP feed flow to ruptured S/G

2) ENSURE Turbine Driven AFW LeV for ruptured S/G in CLOSE PULL TO LOCK. Critical Step Cue: IF level is <10 % state level is now 15%.

STANDARD: Operator continues AFW flow to SG #1 until the level is ?: 10 % on LIS-3-42, 39, 38. THEN the*AFW flow is isolated to the SG #1 by closing the MD AFW and TD AFW level control valves. MD AFW valves closed by depressing the push button on 1-HS-3-164A, then rotating the switch counterclockwise to the MANUAL or MANUAL BYPASS position and placing switch to RAMP CLOSED TD AFW valve closed by momentarily placing 1-HS-3-174 to the CLOSE position and pulling out to PULL TO LOCK. (not critical) Note: When valves are closed the green lights on XX-3~148 for SG #1 will be LIT. COMMENTS: STEP 15.: [6] VERIFY Rupture S/G ISOLATED from Intact S/G(s): - SAT a.CHECK either of the following conditions SATISFIED:

Rupture S/G MSIVs and MSIV bypass valves CLOSED - UNSAT OR
MSIVs and MSIV bypass valves CLOS*ED on Intact S/Gs to be used forcooldown.

STANDARD: Operator determines the intact S/G MSIVs are by the green lights LIT on handswitches 1-HS-1-11 A, 1-HS-1-22A, and 1-HS-1-29A. Determines intact S/G MSIV bypasses are closed by green lights LIT on 1-HS-1-148, 1-HS-1-149,1-HS-1-150 COMMENTS: STEP 16.: b. Check S/G #1 or #4 S/G ruptured. - SAT STANDARD: Operator determines S/G #1 is ruptured and continues to the next sub- - UNSAT step (6.c.). COMMENTS:

JPM # 75AP Page 9 of 10 Job Performance Checklist: STEP/STANDARD SAT/UNSAT STEP 17.: c. Check TDAFW pump steam supply from rupturedS/G SAT ISOLATED:

FCV-1-15 (S/G#1) or FCV-1-16 (SIG #4) CLOSED . - UNSAT STANDARD: Operator verifies FCV-1-15 closed by GREEN light LIT on handswitch. 1-HS-1-15A on1 ~M-4 (Closed earlier in the JPM)

COMMENTS: STEP 18.: [7] CHECK Ruptured S/G pressure greater than 550 psig (Unit 1) - SAT or 425 psig (Unit 2)

                                                                                        -   UNSAT STANDARD: Operator determines the ruptured S/G ( S/G #1) is greater than 500 psig as indicated on 1-PI-11-2A, 1-PI-11-2B, and 1-PI-11-5 COMMENTS:

STEP. 19.: Notify SRO that the #1S/G is isolated. - SAT STANDARD: Operator*informs SRO that he/she is ready to determine the Target Core - UNSAT Exit Thermocouple temperature. Stop Time__ COMMENTS: END OF JPM

Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be* performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be sati*sfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the han*dout sheet I provided you. IN,ITIAl CONDITIONS: Unit 1 has experienced a SGTR. A manual safety injection was initiated and E-O implemented. E-O and ES-O.5 have been completed and a transition to E-3 has been made~ Steps 1 through 3 of E-3 have been completed and S/G #1 has been identified as the ruptured S/G. INITIATING C*.UES: You are the eRO and are directed to continue with the actions/responses of E-3, beginning at Step 4. Inform theSROwhen you are ready to determine the Target Core Exit Thermocouple temperature.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY PROCEDURE E-3 STEAM GENERATOR TUBE RUPTURE Revision 17 QUALITY RELATED PREPARED/PROOFREAD BY: _ D. A. PORTER

                              .............~ ............~------

RESPONS1BLE ORGANIZATION: OPERATIONS

w. T. LEARY EFFECTIVE DATE: 10/20107 REVISION DESCRIPTION: Updated title of EA-201-3 (07000399)~ Clarified guidance on initiating cooldown with S/G atmospheric relief valves in Substep 8.c.RNO (07001129). Reworded Substep 4.e RNO for PER 127171 (07001167,07001333,07001569).

This procedure contains a Foldout Page and a Handout Page (2 copies).

SQN STEAM GENERATOR TUBE RUPTURE E~3 Rev. 17 FOLDOUT PAGE 51 REINITIATION CRITERIA IF 81 has been terminated AND either of the following conditions occurs:

ReS subcooling based on core exit TICs less than 40 of, OR
Pressurizer level CANNOT be maintained greater than 10% [20% ADV],

THEN

a. ESTABLISH ECCS flow by performing one or both of the following:

ESTABLISH CePIT flow as necessary USING Appendix C
START CCPs or 51 pumps manually as necessary.

b. GO TO ECA-3.1, SGTR and LOCA - SubcooJed Recovery.

EVENT DIAGNOSTICS

IF both trains of shutdown boards deenergized, THEN GO TO ECA-D.O, Loss of All AC PoweL
IF any S/G pressure dropping in an uncontrolled manner or less than 140 psig AND S/G NOT isolated AND S/G NOT needed for ReS cooldown, THEN GO TO E-2, Faulted Steam Generator Isoiation.
IF any Intact S/G has level rising in an uncontrolled manner OR has abnormal radiation, THEN STOP any deliberate ReS cooldown or depressurization and GO TO E-3 Step 1.

TANK SWITCHOVER SETPOINTS

IF CST level less than 5%,

THEN ALIGN AFW suction to ERCW.

IF RWST level less than 27%,

THEN GO TO ES-1.3, Transfer to RHR Containment Sump. Page 1a of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 HANDOUT Page 1 of3 STEP I ACTION FOP IF 51 has been terminated AND either of the following conditions occurs:

ReS subcooling based on core exit TICs less than 4CPF OR
PZr level CANNOT be maintained greater than 10°.!c> [20% ADV},

THEN ESTABLISH ECCS flow by performing one or both of the following:

ESTABLISH CePIT flow as necessary USING Appendix C
START CCPs or 81 pumps manually as necessary.

GO TO ECA-3.1. IF any S/G pressure dropping in an uncontrolled manner or less than 140 psig FOP AND S/G NOT isolated AND S/G NOT needed for ReS cooldown, THEN GO TO E-2, Faulted Steam Generator Isolation. FOP IF any Intact S/G has level rising in an uncontrolled manner OR has abnormal radiation, THEN STOP any deliberate ReS cooldown or depressurization and GO TO E-3 Step 1. FOP IF CST level less than 5%, THEN ALIGN AFW suction to ERCW. FOP IF RWST leve' less than 270/0, THEN GO TO ES-1.3, Transfer to RHR Containment Sump.

1. MONITOR at least one Rep RUNNING.

1.b (If all Reps stopped) WHEN step 32 completed OR E-3 exited, RNO THEN RESUME monitoring ruptured loop T-cold.

2. MONITOR Rep trip criteria:

At least one CCP or 81 pump RUNNING AND ReS pressure less than 1250 psig *

3. MONITOR indications of Ruptured 8/G(s).

3.a WHEN ruptured 8/G(5) identified, RNO THEN PERFORM Steps 4 through 8. 4.b. WHEN Ruptured S/G(s) pressure less than 1040 psig, RNO THEN ENSURE S/G atmospheric relief closed. 5.a MAINTAIN feed flow to Ruptured S/G UNTIL level greater than 10% [250/0 ADV]. RNO S.b WHEN Ruptured S/G level greater than 10% [250/0 ADV], THEN STOP feed flow to ruptured S/G. 8.b. WHEN ReS pressure less than 1960 psig, THEN BLOCK low steamline pressure 51. 8.c.6) WHEN T-avg less than 540°F, THEN BYPASS steam dump interlock. Page 1b of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 HANDOUT Page 2 of3 STEP ACTION B.d WHEN core exit TICs less than target temperature, THEN

1) STOP ReS cooldown.

2) MAINTAIN core exit TICs less than target temperature~

9.a. (if Intact S/G level Jess than 10% [25% ADV]) RNO MAINTAIN total feed flow greater than 440 gpm and 16.c UNTIL level greater than 100/0 [250/0 ADV] in at least one S/G . 9.b MAINTAIN Intact S/G narrow range levels between 20% [250/0 ADV] and 50%.

10. MONITOR pressurizer PORVs and block valves:

12. MONITOR AC busses energized from start busses.

15.d. MONITOR ReS pressure greater than 300 psig . 16.d. MAINTAIN core exit TICs less than target temperature.

17. (if ruptured S/G pressure dropping)

RNO MAINTAIN pressure of Intact S/Gs used for cooldown at least 250 psi below ruptured S/G(s):

MAINTAIN ReS cooldown rate less than 10CfF/hr.

19.d. CONTINUE ReS depressurization UNTIL any of following conditions satisfied: an d

Both of the following:

20.b. 1) ReS press less than ruptured S/G pressureAND

2) Pressurizer Jevel greater than 10% [200/0 ADV]

OR

Pressurizer level greater than 65%

OR

ReS subcooling based on core exit TICs less than 4CfF.

21.RNO (if ReS pressure dropping) MONITOR for indication of leakage from pressurizer PORV.

26. CONTROL charging flow to maintain pressurizer level..

27. MONITOR ECCS flow NOT required:

a. ReS sUbcooling based on core exit TICs greater than 40 of

b. Pressurizer Jevel greater than 10% [20 0h ADV].

29. MONITOR if letdown can be established. (pzr level greater than 20 0h [35% ADV])

31.8 WHEN ReS pressure is less than 700 psig, RNO THEN ISOLATE CLAs. Page1cof41

SQN STEAM GENERATOR TUBE RUPTURE E..3 Rev. 17 HANDOUT Page 3 of3 STEP ACTION

32. CONTROL ReS pressure and charging flow to minimize ReS-to-secondary leakage:

RUPTURED S/G RUPTURED S/G RUPTURED S/G LEVEL LEVEL RISING LEVEL DROPPING GREATER THAN 84% [80% ADV] AND STABLE PZRLEVEL Less than 20°./c>

RAISE charging fiow.
RAISE charging flow.
RAISE charging flow.

[35% ADV]

DEPRESSURIZE RCSUSING
MAINTAIN ReS and Ruptured S/G(s)

Substep 32.b. pressures equal. PZRLEVEL Between

DEPRESSURIZE RCSUSING
TURN ON pressurizer heaters.
MAINTAIN ReS and Ruptured S/G(s) 200/0 [35°k> ADV] Substep 32.b. pressures equal.

and 50% PZRlEVEL Between

REDUCE charging flow.
TURN ON pressurizer heaters.
MAINTAIN ReS and Ruptured S/G(s) 50% and 65%
DEPRESSURIZE RCSUSING pressures equaL SUbstep 32. b.

Greater than 650/0

REDUCE charging flow.
TURN ON pressurizer heaters.
MAINTAIN ReS and Ruptured S/G(s) pressures equal.

32.c. MONITOR ReS pressure less than 1040 psig.

34. MONITOR if containment spray should be stopped. (pressure less than 2rO psig)

35. MONITOR if containment vacuum control should be returned to normal: (less than 1.0 psig).

38. MAINTAIN pressurizer at saturation temperature for ruptured S/G pressure USING pressurizer heaters.

41. MONITOR Rep status. (Rep #2 running) 41.a.4) MONITOR natura' circulation Of NO Rep can be started).

RNO 4

42. MONITOR jf source range channels should be reinstated. (IRM flux less than 10- 0/0) 42.f. WHEN shutdown monitor ALARM LEOs darkAND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL. [M13]

Page 1d of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 HANDOUT Page 1 of3 STEP ] ACTION FOP IF 81 has been terminated AND either of the foJJowing conditions occurs:

ReS subcooling based on core exit TICs less than 40'F OR
pzr level CANNOT be maintained greater than 10% [20% ADV],

THEN ESTABLISH ECCS flow by performing one or both of the following:

ESTABLISH CePIT flow as necessary USING Appendix C
START CCPs or SI pumps manually as necessary.

GO TO ECA-3.1. IF any S/G pressure dropping in an uncontrolled manner or less than 140 psig FOP AND S/G NOT isolated AND S/G NOT needed for ReS cooldown, THEN GO TO E-2, Faulted Steam Generator Isolation. IF any Intact S/G has level rising in an uncontrolled manner FOP OR has abnormal radiation, THEN STOP any deliberate Res cooldown or depressurization and GO TO E...3 Step 1. FOP IF CST level less than 50/0, THEN ALIGN AFW suction to ERCW. FOP IF RWST level Jess than 27°ftJ, THEN GO TO ES-1.3, Transfer to RHR Containment Sump.

1. MONITOR at least one Rep RUNNING.

1.b (If all Reps stopped) WHEN step 32 completed OR E..3 exited, RNO THEN RESUME monitoring ruptured roop T-cold.

2. MONITOR Rep trip criteria:

At least one CCP or 81 pump RUNNING AND ReS pressure less than 1250 psig .

3. MONITOR indications of Ruptured S/G(s).

3.a WHEN ruptured S/G(s) identified, RNO THEN PERFORM Steps 4 through 8. 4.b. WHEN Ruptured S/G(s) pressure less than 1040 psig, RNO THEN ENSURE S/G atmospheric relief closed. 5.a MAINTAIN feed flow to Ruptured S/G UNTIL level greater than 10°h, [25% ADV]. RNO 5.b WHEN Ruptured S/G level greater than 100/0 [250/0 ADV], THEN STOP feed flow to ruptured S/G. 8.b. WHEN ReS pressure less than 1960 psig, THEN BLOCK low steamline pressure 51. B.c.6) WHEN T-avg less than 540°F, THEN BYPASS steam dump interlock. Page 1e of 41

SQN STEAM GENERATOR TUBE RUPTURE E~3 Rev. 17 HANDOUT Page 2 of3 STEP ACTION B.d WHEN core exit TICs less than target temperature, THEN

1) STOP ReS cooldown.

2) MAINTAIN core exit TICs less than target temperature.

9.a. (if Intact S/G Jevelless than 100/0 [25% ADV]) RNO MAINTAIN total feed flow greater than 440 gpm and 16.c UNTIL level greater than 100/0 [250/0 ADV] in at least one S/G~ 9.b MAINTAIN Intact S/G narrow range levels between 20% [25% ADV] and 50%.

10. MONITOR pressurizer PORVs and block valves:

12. MONITOR AC busses energized from start busses.

15.d. MONITOR Res pressure greater than 300 psig. 16.d. MAINTAIN core exit TICs less than target temperature.

17. (if ruptured S/G pressure dropping)

RNO MAINTAIN pressure of Intact S/Gs used for cooldown at least 250 psi below ruptured S/G(s):

MAINTAIN ReS cool down rate less than 10QJF/hr, 19.d. CONTINUE ReS depressurization UNTIL any of following conditions satisfied:

and

Both of the following:

20.b. 1) ReS press less than ruptured S/G pressureAND

2) Pressurizer Jevel greater than 10% [20% ADV]

OR

Pressurizer level greater than 650/0 OR
ReS subcooling based on core exit TICs less than 4CfF.

21.RNO (if ReS pressure dropping) MONITOR for indication of leakage from pressurizer PORV.

26. CONTROL charging flow to maintain pressurizer level.

27. MONITOR ECCS flow NOT required:

a. ReS subcooling based on core exit TICs greater than 40 of

b. Pressurizer level greater than 10% [20% ADV].

29. MONITOR if letdown can be established. (pzr level greater than 20% [35°10 ADV])

31.a WHEN ReS pressure is less than 700 psig t RNO THEN ISOLATE CLAs. Page 1f of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 HANDOUT Page 3 of 3 STEP ACTION

32. CONTROL ReS pressure and charging flow to minimize RCS-to-secondary leakage:

RUPTURED S/G RUPTURED S/G RUPTURED S/G LEVEL LEVEL RISING LEVEL DROPPING GREATER THAN 84% [80% ADV] AND STABLE PZRLEVEL Less than 20%

RAISE charging flow.
RAISE charging flow.
RAISE charging flow.

[35% AD\/]

DEPRESSURIZE Res USING
MAINTAIN ReS and Ruptured S/G(s)

Substep 32.b. pressures equal. PZRLEVEL Between

DEPRESSURIZE Res USING
TURN ON pressu rizer heaters.
MAINTAIN ReS and Ruptured S/G(s) 200/0 [35% ADV] Substep 32.b. pressures equal.

and 500~ PZR LEVEL

REDUCE charging
TURN ON
MAINTAIN ReS Between flow. pressu rizer heaters. and Ruptured S/G(s) 50% and 650/0
DEPRESSURIZE pressures equal.

RCSUSING Substep 32.b. Greater than 65%

REDUCE charging
TURN ON
MAINTAIN ReS flow. pressurizer heaters. and Ruptured S/G(s) pressures equal.

32.c. MONITOR ReS pressure less than 1040 psig.

34. MONITOR if containment spray should be stopped. (pressure less than 2.0 psig)

35. MONITOR if containment vacuum control should be returned to normal: (less than 1.0 psig).

38. MAINTAIN pressurizer at saturation temperature for ruptured S/G pressure USING pressurizer heaters.

41. MONITOR Rep status. (Rep #2 funning) 41.a.4) MONITOR natural circulation (if NO Rep can be started).

RNO 4

42. MONITOR if source range channels should be reinstated. (lRM flux less than 10- %)

42.t WHEN shutdown monitor ALARM LEDs darkAND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL. [M13] Page 19 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 1.0 PURPOSE This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture. 2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 ENTRY CONDITIONS E-O Reactor Trip or Safety Injection:

Secondary radiation.
S/G level rising in an uncontrolled manner.

E-1, ES-1.2, and ECA-2.1 Foldout Page

S/G level rising in an uncontrolled manner..

E-1 Loss of Reactor or Secondary Coolant:

Secondary radiation.
S/G level rising in an uncontrolled manner.

ES-1.2 Post LOCA Cooldown and Depressurization:

S/G level rising in an uncontrolled manner.

E-2 Faulted Steam Generator Isolation:

Secondary radiation.

ES-3.1 Post - SGTR Cooldown Using Backfill:

S/G level rising in an uncontrolled manner..

ES-3.2 Post - SGTR Cooldown Using Slowdown:

S/G level rising in an uncontrolled manner.

ES-3.3 Post - SGTR Cooldown Using Steam Dump:

S/G level rising in an uncontrolled manner.

(continued on next page.) Page 2 of 41

SQN STEAM G.ENERATOR TUBE RUPTURE E..3 Rev. 17 2.1 ENTRY CONDITIONS (Continued) ECA-2.1 Uncontrolled Depressurization of All Steam Generators:

Secondary radiation.

ECA-3.1 SGTR and LOCA - Subcooled Recovery:

S/G fevel rising in an uncontrolled manner.

ECA-3.2 SGTR and LOCA - Saturated Recovery:

S/G level rising in an uncontrolled manner.

ECA-3.3 SGTR Without Pressurizer Pressure Control:

S/G level rising in an uncontrolled manner.
Pressurizer pressure control restored.

FR-H.3 Steam Generator High Level:

Secondary Radiation.

3.0 OPERATOR ACTIONS Page 3 of 41

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev. 17 [ STEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED NOTE This procedure has a foldout page.

1. MONITOR at least one Rep RUNNING. IF all Reps are STOPPED, THEN PERFORM the following:

a. SUSPEND monitoring ruptured loop T-cold indication on PTS status tree.

b. WHEN step 32 is completed OR E-3 is exited J THEN RESUME monitoring ruptured loop T-cold indication on PTS status tree.

2. MONITOR Rep trip criteria:

a. CHECK the following: a. GO TO Step 3.

ReS pressure less than 1250 psig ..........

AND

At least one CCP OR 81 pump RUNNING.

b. STOP Reps.

Page 4 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

3. MONITOR indications of Ruptured S/G(s):

a. IDENTIFY Ruptured S/G(s) as a. WHEN Ruptured S/G(s) identified, indicated by any of the following: THEN PERFORM Steps 4 through 8.

Unexpected rise in any S/G narrow range level. GO TO Step 9.

OR

High radiation from any S/G sample.

OR

RADCON survey of main steam Jines and S/G blowdown lines.

OR

High radiation on any main steamline radiation monitor.

Page 5 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev~ 17 I STEP 11 ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED CAUTION Isolating both steam supplies to the TO AFW pump when it is the only source of feed flow will result in loss of secondary heat sink.

4. ISOLATE flow from Ruptured 8/G(s):

8. ADJUST Ruptured S/G(s) atmospheric relief controller setpoint to 87% in AUTO. (1040 psig)

b. CHECK Ruptured S/G(s) b. WHEN Ruptured S/G(s) pressure atmospheric relief hand switch in less than 1040 psig, P-AUTO and valve(s) CLOSED. THEN PERFORM the following:

1) VERIFY atmospheric relief CLOSED.

2) IF atmospheric relief NOT closed, THEN CLOSE atmospheric relief.

IF Ruptured S/G(s) atmospheric relief CANNOT be closed, THEN DISPATCH personnel to close atmospheric relief USING EA-1-2, Local Control of S/G PORVs.

c. CLOSE TD AFW pump steam c. IF at least one MD AFW pump running, supply from Ruptured S/G THEN FCV-1-15 (S/G #1) or ISOLATE steam to TD AFW pump FCV-1-16 (3/G #4). USING FCV-1-17 or FCV-1-18.

IF TO AFW pump is still running, THEN DISPATCH operator to locally close steam supply from ruptured S/G FCV-1-15 or FCV-1-16. [West Valve Vault Room]

d. VERIFY Ruptured S/G(s) blowdown d. CLOSE valve(s).

isolation valves CLOSED. (Step continued on next page.) Page 6 of 41

E-3 SQN STEAM GENERATOR TUBe RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

4. e. CLOSE Ruptured S/G(s} MSIV and e. PERFORM the following:

MSIV bypass valve.

1) CLOSE Intact S/G MSIVs and MSIV bypass valves.

2) DISPATCH operator to perform EA..1-1, Closing MSIVs Locally, for any MSIV or MSIV bypass valve which fails to close.

3) ISOLATE steam header:

PLACE condenser steam dumps in OFF. [M-4]

ENSURE steam dump valves CLOSED. [M-4]

CLOSE FCV--47-180, HP steam Seal Supply Isolation. [M-2]

ENSURE FCV-47-181 HP Steam Seal Supply Bypass CLOSED. [M-2]

CLOSE MSR HP steam supply isolation varves. [M-2] DISPATCH operator to locally isolate steam header USING EA-1-4, Local Isolation of Steam Header in Turb Bldg.

4) USE Intact S/G(s) atmospheric relief for steam dump.

IF any Ruptured S/G CANNOT be isolated from at least one Intact S/G, THEN GO TO ECA-3.1, SGTR and LOCA - Subcooled Recovery. Page 7 of 41

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED CAUTION Feeding a S/G that is Faulted and Ruptured increases the potential for an uncontrolled ReS cooldown and S/G overfill. This option should NOT be considered UNLESS needed for Res cooldown.

5. MONITOR Ruptured S/G(s) level:

a. CHECK narrow range level a. MAINTAIN feed flow to greater than 10% [25% ADV]. Ruptured S/G UNTIL level greater than 10% [25% ADV].

b. WHEN ruptured S/G level is greater than 10% [25% ADV],

THEN PERFORM the following:

1) STOP feed flow to ruptured S/G.

2) ENSURE Turbine Driven AFW LeV for ruptured S/G in CLOSE PULL TO LOCK.

Page 8 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP IIACTION/EXPECTED RESPONSE I J RESPONSE NOT OBTAINED

6. VERIFY Ruptured S/G ISOLATED from Intact S/G(s):

a. CHECK either of the foUowing a. DO NOT CONTINUE this procedure conditions SATISFIED: UNTIL one of conditions satisfied.

Ruptured S/G MSIVs and MSIV bypass valves CLOSED OR
MSIV(s) and MSIV bypass valve(s)

CLOSED on Intact S/G(s) to be used for ReS cooldown.

b. CHECK S/G #1 or S/G #4 ruptured. b. GO TO Step 7.

c. CHECK TDAFW pump steam supply c. DO NOT CONTINUE this procedure from ruptured S/G ISOLATED: UNTIL ruptured S/G steam supply isolated by one of the following:

FCV-1-15 (S/G #1) or FCV-1-16 (S/G #4) CLOSED
FCV-1-15 (S/G #1) or FCV-1-16 (S/G #4) CLOSED OR
FCV-1-17 or FCV-1-18 CLOSED OR
TDAFW pump TRIPPED.

7. CHECK Ruptured S/G pressure GO TO ECA-3.1, SGTR and LOCA-greater than 550 psig (Unit 1) Subcooled Recovery.

or 425 psig (Unit 2). Il Page 9 of41 l~

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP] (ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED NOTE Blocking low steamline pressure SI as soon as pressurizer pressure is less than 1960 psig will prevent an inadvertent MSIV closure and keep t~e condenser available for steam dump.

After the low steamline pressure 81 signal is blocked, main steamline isolation will occur if.the high steam pressure rate setpoint is exceeded.
The 1250 psig Rep trip criterion is NOT applicable after ReS cooldown is initiated in the following step.

8. INITIATE ReS cooldown:

a. DETERMINE target core exit TIC temperature based on Ruptured S/G pressure:

Lowest Ruptured Target Core Exit S/G pressure (psig) TiC Temp (OF) 1100 or greater 497 1050 -1099 492 1000 - 1049 486 950 - 999 480 900 - 949 473 850 - 899 467 800 - 849 460 750 -799 453 700 - 749 445 650 - 699 437 600 - 649 428 550 - 599 419 500 - 549 410 450 - 499 399 425 - 449 393 (Step continued on next page.) Page 10 of41

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev~ 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

8. b. WHEN Res pressure less than 1960 psig, THEN PERFORM the following:

1) BLOCK low steamline pressure SL

2) CHECK STEAMLINE PRESS ISOUSI BLOCK RATE ISOL ENABLE permissive LIT.

[M-4A, A4]

c. DUMP steam to condenser c~ IF steam dumps NOT available) from Intact S/G(s) at maximum THEN achievable rate: OPEN atmospheric relief valves for Intact S/G(s)

1) CHECK condenser available:

C-9 condenser interlock RAISE AFW flow to intact S/Gs permissive LIT. [M-4A, E6] as necessary to support cooldown.
Intact S/G MSIVs OPEN. IF local control of atmospheric reliefs is necessary,

2) PLACE steam dumps in OFF. THEN DISPATCH personnel to dump steam

3) ENSURE steam dumps in at maximum achievable rate steam pressure mode USING EA-1-2, Local Control of S/G with demand less than 25%k PORVs.

4) PLACE steam dumps in ON.

IF NO Intact S/G available, THEN

5) ADJUST steam dump demand PERFORM the following:

to FULLY OPEN three cooldown valves.

USE Faulted S/G.

6) WHEN T-avg is tess than 540°F, OR THEN

GO TO ECA-3.1) SGTR and BYPASS steam dump interlock. LOCA - Subcooled Recovery.

7) RAISE AFW flow to intact S/Gs as necessary to support cooldown.

(Step continued on next page.) Page 11 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

8. d. WHEN core exit TICs less than target temperature determined in Substep 8.a, THEN PERFORM the following:

1) CLOSE steam dumps or S/G atmospheric reliefs to stop cooldown.

2) REDUCE AFW flow as necessary to stop cooldown.

MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10% [25 0ft, ADV] in at least one Intact S/G.

3) MAINTAIN core exit TICs less than target temperature USING steam dumps or atmospheric reliefs.

Page 12 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

9. MAINTAIN Intact S/G narrow range levels:

a. Greater than 10% [25% ADV] a. MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10% [25% ADV]

in at least one Intact S/G. IF at least 440 gpm AFW flow CANNOT be established, THEN ESTABLISH main feedwater or condensate flow USING EA~2-2, Establishing Secondary Heat Sink Using Main Feedwater or Condensate System

b. Between 20% [25% ADV] and 50%. b. IF level in any Intact S/G continues to rise in an uncontrolled manner, THEN STOP ReS cool down and GO TO Step 1.

Page 13 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 (STEP IIACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED CAUTION Any time a pressurizer PORV opens, there is a possibility that it may stick open.

10. MONITOR pressurizer PORVs and block valves:

a. Power to block valves AVAILABLE a. DISPATCH personnel to restore power to block valves USING EA-201-1 , 480 V Board Room Breaker Alignments.

b. Pressurizer PORVs CLOSED b. IF pressurizer pressure less than 2335 psig, THEN CLOSE pressurizer PORVs.

IF pressurizer PORV CANNOT be closed, THEN CLOSE its block valve. IF pressurizer PORV remains open AND associated block valve CANNOT be closed, THEN GO TO ECA-3.1 , SGTR and LOCA

c. At least one block valve OPEN. c.

                                                       - Subcooled Recovery.

OPEN one block valve UNLESS closed to isolate an open PORV. Page 14of41

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

11. RESET 81 signal.

12. MONITOR AC busses energized ENSURE diesel generators supplying from start busses. shutdown boards.

WHEN shutdown power restored, THEN ENSURE safeguards equipment running as necessary.

13. ENSURE Phase A and Phase B RESET.

14. CHECK control air established ESTABLISH control air to containment to containment: [Panel 6K and 6L] USING EA-32-1, Establishing Control Air to Containment.

1-FCV-32-80 (2-FCV-32-81)

Train A essential air OPEN

1-FCV-32-102 (2-FCV-32-103)

Train B essential air OPEN

1-FCV-32-110 (2-FCV-32-111) non-essential air OPEN.

Page 15 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 ISTEP IIACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

15. DETERMINE if RHR pumps should be stopped:

a. CHECK RHR pump suction a. GO TO Step 16.

aligned from RWST.

b. CHECK ReS pressure b. GO TO Step 16..

greater than 300 psig.

c. STOP RHR pumps and c. IF pump(s) CANNOT be stopped PLACE in A-AUTO. in A-AUTO t THEN PLACE affected RHR pump(s) in PULL TO LOCK.

d. MONITOR ReS pressure d. IF ReS pressure dropping greater than 300 psig. uncontrolled, THEN START RHR pumps.

Page 16 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 ISTEP IIACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

16. CHECK if Res cooldown should be stopped:

8. CHECK core exit TICs 8. DO NOT CONTINUE this procedure less than target temperature UNTIL core exit TICs less than target determined in Substep 8.a. temperature.

b. CLOSE steam dumps or atmospheric reliefs to stop cooldown.

c. REDUCE AFW flow as necessary to stop cooldown .

MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10% [25% ADV] in at least one Intact S/G.

d. MAINTAIN core exit TICs less than target temperature USING steam dumps or atmospheric reliefs.

Page 17 of41

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

17. CHECK Ruptured S/G(s) pressure MAINTAIN pressure of Intact STABLE or RISING. S/Gs used for cooldown at least 250 psi below ruptured S/G(s):

SLOWLY DUMP steam from Intact S/Gs
MAINTAIN Res cooldown rate less than 1GO°F/hr.

IF Intact S/G(s) used for cooldown CANNOT be maintained at least 250 psi below ruptured S/G(s)r THEN GO TO ECA-3.1 SGTR and LOCA ... t Subcooled Recovery.

18. CHECK ReS subcooling based on core GO TO ECA-3.1, SGTR and LOCA-exit TICs greater than 60°F. Subcooled Recovery.

Page 18 of41

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE I [R~SPONSE NOT OBTAINED

19. DEPRESSURIZE Res to minimize break flow and to refill pressurizer:

a. CHECK normal pressurizer spray a. GO TO Cautions prior to Step 20.

AVAILABLE~

b. INITIATE maximum available pressurizer spray.

c. CHECK depressurization rate c. GO TO Cautions prior to Step 20.

ADEQUATE.

d. CONTINUE depressurization UNTIL any of the following conditions SATISFIED:

Both of the following:

1) ReS pressure less than Ruptured S/G(s) pressure AND

2) Pressurizer level greater than 10% [20% ADV].

OR

Pressurizer level greater than 65%.

OR

Res subcooling based on core exit TICs less than 40°F.

(step continued on next page) Page 19 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE IIRESPONSE NOT OBTAINED

19. e. CLOSE spray valve(s):

1) Normal spray valves. 1) STOP Reps #1 and 2.

IF ReS pressure continues to drop, THEN STOP additional Rep as necessary.

2) Auxiliary spray valves. 2) ISOLATE auxiliary spray line.

f. GO TO Caution prior to Step 22.

=--

Page 20 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 , STEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED CAUTION

Depressurizing the ReS using a pressurizer PORV may cause PRT rupture with resulting abnormal containment conditions.
Excessive cycling of a pressurizer PORV increases the potential for PORV failure.

NOTE Upper head voiding may occur during ReS depressurization if no Reps are running. This may result in rapidly rising pressurizer level.

20. DEPRESSURIZE ReS USING one pressurizer PORV to minimize break flow and to refill pressurizer:

a. CHECK at least one pressurizer 8. PERFORM the following to establish PORV AVAILABLE auxiliary spray:

1) ENSURE at least one SI pump RUNNING.

IF NO 81 pump running, THEN GO TO ECA-3.3, SGTR Without Pressurizer Pressure Control.

2) ENSURE at least one CCP RUNNING.

3) CLOSE CePIT inlet valves FCV-63-39 and FCV-63-40.

4) CLOSE CePIT outlet valves FCV-63-25 and FCV-63-26.

5) OPEN charging line isolation valves FCV-62-90 and FCV-62-91.

6) ESTABLISH auxiliary spray USING EA-62-4 r Establishing Auxiliary Spray.

(step continued on next page) Page 21 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

20. a. (Continued) IF auxiliary spray established, THEN GO TO Step 19.b.

                                                         ----~

IF auxiliary spray CANNOT be established, THEN GO TO ECA-3.3, SGTR Without Pressurizer Pressure Control.

b. OPEN one pressurizer PORV UNTIL any of the following conditions SATISFIED:

Both of the following:

1) ReS pressure less than Ruptured S/G(s) pressure AND

2) Pressurizer level greater than 10% [200/0 ADV].

OR

Pressurizer level greater than 650/0.

OR

ReS subcooling based on core exit TICs less than 40°F.

(step continued on next page) Page 22 of 41

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

20. c. CLOSE pressurizer PORV. c. CLOSE block valve.

d. CLOSE spray valve(s):

1) Normal spray valves 1) STOP Reps #1 and 2~

IF ReS pressure continues to drop. THEN STOP additional Rep as necessary. I-

2) Auxiliary spray valves. 2) ISOLATE auxiliary spray line.

21. CHECK ReS pressure RISING. CLOSE pressurizer PORV block valve.

IF pressure continues to drop, THEN PERFORM the following:

1) MONITOR the following conditions for indication of leakage from pressurizer PORV:

Acoustic Monitoring System
Tail pipe temperatures PRT indications.

2) GO TO ECA-3.1, SGTR and LOCA-Subcooled Recovery.

Page 23 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED CAUTION Any delay in terminating 51 after termination criteria are met may cause Ruptured S/G(s) overfilL

22. CHECK if ECCS flow should be terminated:

a. ReS subcooling based on core exit a. GO TO ECA-3.1 , SGTR and LOCA-TICs greater than 40°F. Subcooled Recovery.

b. Secondary heat sink: b.

IF neither condition satisfied J THEN

Narrow range level in at least one Intact S/G greater than 10% [25% ADV]

OR GO TO ECA-3.1, SGTR and LOCA-Subcooled Recovery.

Total feed flow to S/Gs greater than 440 gpm AVAILABLE.

c. ReS pressure STABLE or RISING.

d~ Pressurizer level c. d. GO TO ECA-3.1, SGTR and LOCA - Subcooled Recovery. GO TO Step 6. greater than 10% [20 0h ADV].

e-Page 24 of 41

E..3 SQN STEAM GENERATOR TUBE RUPTURE Rev~ 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

23. STOP the following ECCS pumps:

a. STOP 81 pumps and a. IF any 81 pump(s) CANNOT be PLACE in A-AUTO. stopped in A-AUTO, THEN ENSUREaffectedpump~)

in PULL TO LOCK.

b. CHECK offsite power b. ENSURE one CCP in supplying shutdown boards. PULL TO LOCK.

GO TO Step 24.

c. STOP all BUT one CCP and c. IF CCP CANNOT be stopped PLACE in A-AUTO. inA-AUTO, THEN ENSURE one CCP in PULL TO LOCK.

24" ISOLATE CePIT: IF cePIT flowpath CANNOT be isolated from MeR,

8. CLOSE inlet isolation varves THEN FCV-63-39 and FCV-63-40. CLOSE affected CePIT valves USING EA-201-3, Operation of Motor..

b. CLOSE outlet isolation valves Operated Valves from Outside MeR.

FCV-63-26 and FCV-63...25. Page 25 of 41

SQN STEAM GENERATOR TUBE RUPTURE E*3 Rev. 17 ISTEP) IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

25. ESTABLISH charging flow:

a. CLOSE seal water flow control valve FCV-62-89.

b. OPEN charging flow isolation valves b. IF power available, FCV-62-90 and FCV-62-91. THEN OPEN affected valve from Rx MOV Board USING EA-201-3, Operation of Motor-Operated Valves from Outside MeR.

G. ENSURE normal or alternate charging isolation valve FCV-62-86 or FeV-62-8S OPEN.

d. ESTABLISH desired charging flow USING seal water and charging flow control valves FCV-62-89 and FCV-62-93.

26. CONTROL charging flow to maintain pressurizer level.

Page 26 of 41

E..3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP IIACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED 27.. MONITOR ECCS flow NOT required: a~ ReS 5ubcooling based on core exit a. ESTABLISH ECCS flow manually 0 T/Cs greater than 40 F. by performing one or both

                                                      . of the following:

ESTABLISH CePIT flow as necessary USING App . C.
START CCPs or 81 pumps manually as necessary.

GO TO ECA-3 . 1, SGTR and LOCA -

b. Pressurizer level Subcooled Recovery.

b. CONTROL charging flow to maintain greater than 10% [200/0 ADV]. pressurizer level.

IF pressurizer level CANNOT be maintained, THEN PERFORM the following:

1) ESTABLISH ECCS flow manually by performing one or both of the following:

ESTABLISH CePIT flow as necessary USING App. C.
START CCPs or 81 pumps manually as necessary.

2) GO TO ECA-311~ SGTR and LOCA ... Subcooled Recovery.

Page 27 of 41

E~3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

28. CHECK veT makeup control system: ADJUST controls as necessary.

a. Makeup set for greater than ReS boron concentration.

b. Makeup set for automatic control.

29. MONITOR if letdown can be established:

a. CHECK pressurizer level a. GO TO Step 30.

greater than 20 0k [35% ADV].

b. ESTABLISH letdown USING EA-62-5, b. ESTABLISH excess letdown Establishing Normal Charging and USING EA-62-3, Establishing Letdown. Excess Letdown..

Page 28 of 41

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev. 17 [STEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

30. DETERMINE if CCP suction can be aligned to VeT:

a. CHECK CCP suction a. IF ECCS pumps aligned for ALIGNED to RWST. sump recirculation, THEN EVALUATE terminating sump recirculation USING EA-63-6, Terminating Sump Recirculation.

GO TO Step 31.

b. ENSURE VCT level is greater than 20%.

c. OPEN VeT outlet valves LCV-62-132 and LCV-62-133 and PLACE in PULL A-P-AUTO.

d. CLOSE RWSTvalves LCV-62-135 and LCV-62-136 and PLACE in PULL A-P-AUTO.

e. ENSURE VeT cover gas established USING EA-O-8, Establishing VeT Cover Gas.

Page 29 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

31. DETERMINE if CLAs should be isolated:

a. CHECK ReS pressure a. WHEN ReS pressure is less than 700 psig. less than 700 psig, THEN PERFORM Substeps 31.b, CJ and d.

GO TO Step 32.

b. CHECK the following: b. GO TO ECA-3.1, SGTR and LOCA

                                                            ... Subcooted Recovery.

ReS subcooling based on core exit TICs greater than 40°F -....
Pressurizer level greater than 10% [20% ADV].

I 1 p- c. CHECK power to CLA isolation valves c. DISPATCH personnel to restore AVAILABLE. power to CLA isolation valves USING EA-201 ...1, 480 V Board Room Breaker Alignments.

d. CLOSE CLA isolation valves. d. IF power available to affected valve(s),

THEN CLOSE affected valve(s) USING EA-201-3 Operation of J Motor-Operated Valves from Outside MeR. IF any CLA valve CANNOT be closed, THEN VENT unisolated CLA(s) USING EA-63-1 Venting Unisolated 1 Cold Leg Accumulator. Page 30 of41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE ] IRESPONSE NOT OBTAINED 32.. CONTROL Res pressure and charging flow to minimize RCS-to-secondary leakage:

a. PERFORM appropriate action(s) from table:

RUPTURED S/G RUPTURED S/G RUPTURED S/G LEVEL LEVEL LEVEL RISING DROPPING GREATER THAN 84% [800/0 ADV] AND STABLE PZR LEVEL Less than 200/0

RAISE charging RAISE charging
RAISE charging

[35% ADV] flow. flow. flow.

DEPRESSURIZE
MAINTAIN ReS Res USING and Ruptured Substep 32.b. S/G(s) pressures equal.

Between DEPRESSURIZE TURN ON MAINTAIN ReS 20% [350/0 ADV] Res USING pressurizer heaters. and Ruptured and 50o~ Substep 32.b. S/G(s) pressures equal. Between

REDUCE charging TURN ON MAINTAIN ReS 50% and 65% flow. pressurizer heaters. and Ruptured S/G(s) pressures
DEPRESSURIZE equal.

RCSUSING Substep 32.b. Greater than 65% REDUCE charging TURN ON MAINTAIN ReS flow. pressurizer heaters. and Ruptured S/G(s) pressures equal.. (step continued on next page) Page 31 of41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE I [RESPONSE NOT 081AINED

32. b. USE normal pressurizer spray b. IF letdown in service l as required by SUbstep 32.a. THEN ESTABLISH auxiliary spray USING EA-62-4, Establishing Auxiliary Spray.

IF letdown NOT in service OR auxiliary spray CANNOT be established, THEN USE one pressurizer PORV.

c. MONITOR ReS pressure c. PERFORM the following:

less than 1040 psig.

1) MAINTAIN ReS subcooling based on core exit TICs greater than 40°F.

2) DEPRESSURIZE ReS USING Substep 32.b. UNTIL Res pressure less than 1040 psig.

3) MAINTAIN ReS and Ruptured S/G(s) pressures less than 1040 psig.

33. CHECK at least one Rep RUNNING. RESUME monitoring ruptured loop T-cold indication on PTS status tree..

Page 32 of41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 J STEP I J ACTION/EXPECTED RESPONSE I 'RESPONSE NOT OBTAINED

34. MONITOR if containment spray should be stopped:

8. CHECK any containrnent spray pump a. GO TO Step 35.

=--

RUNNING.

b. CHECK containment pressure b. GO TO Step 35.

=--

less than 2.0 psig.

c. CHECK containment spray suction c. NOTIFY TSC to determine aligned to RWST. when one or both trains of cntmt spray should be stopped.

WHEN directed by TSC, THEN PERFORM Substeps 34.d through 34.f. GO TO Step 35.

d. RESET Containment Spray signal. =--

e. STOP containment spray pumps and PLACE in A-AUTO.

f. CLOSE containment spray discharge valves FCV-72-2 and FCV-72-39.

Page 33 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

35. MONITOR if containment vacuum control should be returned to normal:

a. GO TO Step 36.

=--

a. CHECK containment pressure less than 1.0 psig.

b. ENSURE containment vacuum relief isolation valves OPEN:

[Panel 6K or M-9]

FCV-30-46
FCV-30-47
FCV-30-48.

36. DETERMINE if diesel generators should be stopped:

a. VERIFY shutdown boards a. ATTEMPT to restore offsite ENERGIZED from start busses. power to shutdown boards USING EA-202-1, Restoring Offsite Power to 6900 V Shutdown Boards.

b. STOP any unloaded diesel generators and PLACE in standby USING EA-82-1, Placing DIGs in Standby.

1 Page 34 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev, 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

37. DISPATCH personnel to perform EA-O-3 J Minimizing Secondary Plant Contamination.

38. MAINTAIN pressurizer liquid at saturation temperature for ruptured S/G pressure:

OPERATE pressurizer heaters as necessary.

39. CHECK Rep cooling NORMAL: ESTABLISH cooling to Reps USING EA-68-3, Establishing Rep

Rep CCS flow Cooling.
Rep seal injection flow.

Page 35 of 41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTE~ II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

40. DETERMINE jf Rep seal return flow should be established:

a. VERIFY Rep seal injection flow a. GO TO Step 41.

established.

b. VERIFY CCS cooling to seal water b. ESTABLISH CCS cooling to seal heat exchanger NORMAL: water heat exchanger.

SEAL WATER HX OUTLET IF CCS cooling to seal water heat FLOWITEMP ABNORMAL exchanger CANNOT be established, alarm DARK. THEN

[M-27B-B, A6 (M-27B-D, A7)]. GO TO Step 41.

c. ENSURE the following: c. GO TO Step 41.

VeT pressure greater than 13 psig. [M-6]
RCDT pressure [O-L-2]

less than VeT pressure.

d. OPEN seal return isolation valves FCV-62-61 and FCV-62-63.

Page 36 of 41

SQN E-3 STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP I IACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED CAUTION Loss of all Rep seal cooling may cause Rep seal damage and will require a TSC status evaluation prior to restarting affected Reps. NOTE Loop 2 Rep and associated spray valve will provide adequate spray flow for Res pressure control. If Loop 2 is not available, all three remaining Reps may be required to ensure adequate spray flow"

41. MONITOR Rep status:

a. CHECK Rep #2 RUNNING. a. ATTEMPT to start Rep(s) to provide normal pzr spray:

1) IF all Rep seal cooling has preViously been lost l THEN NOTIFY TSC to initiate Rep restart status evaluation.

2) IF RVLIS upper range indication less than 104%,

THEN PERFORM the following: RAISE pressurizer level to greater than 90o~ OR until level stops rising . RAISE ReS subcooling based on core exit TICs to greater than 76°F. OPERATE pzr heaters as necessary to raise pzr liquid temperature to saturation.

3) ESTABLISH conditions for starting RCP(s) USING EA-68-2, Establishing Rep Start Conditions.

(step continued on next page) Page 37 of 41

SQN STEAM GENERATOR TUBE RUPTURE E*3 Rev. 17 ISTEP IIACTION/EXPECTED RESPONSE I, RESPONSE NOT OBTAINED

41. a~ (Continued) 4) IF Rep start conditions established, THEN START Rep #2 (if available)

OR Reps #1" 3 t and 4. IF NO Rep can be started, THEN MONITOR natural circulation USING EA-68-6, Monitoring Natural Circulation Conditions. IF natural circulation CANNOT be verified, THEN RAISE steam dump rate.

b. STOP RCP(s) NOT needed for normal pressurizer spray.

Page 38 of41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

42. MONITOR if source range channels should be reinstated:

a. CHECK intermediate range flux a. GO TO Step 43.

less than 10- 4 % power on operable channels.

b. CHECK source range channels b. REINSTATE source range channels REINSTATED. by simultaneously placing both SRM TRIP RESET-BLOCK switches to RESET position. [M-4]

c. SELECT one SRM and one IRM on NR-45 recorder.

d. ENSURE audio count rate operation.

e. RESET shutdown monitor alarm setpoints. [M-13]

f. WHEN shutdown monitor ALARM LEOs dark AND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL.

[M-13]

43. SHUT DOWN unnecessary plant equipment:

REFER TO O-GO.. 12, Realignment of Secondary Equipment Following ReactorlTurbine Trip. Page 39 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 17 ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

44. PERFORM EA-O-9, Post Trip Administrative Requirements and Recovery Actions.

NOTE Backfill method is slow but preferred since it minimizes radiological releases and facilitates processing of contaminated reactor coolant. Slowdown method is slow but minimizes radiological releases and eliminates boron dilution and secondary chemistry effects on ReS. Steam dump method is fast but may involve ra dialogical releases and water hammer concerns (if water exists in the steamlines).

45. DETERMINE appropriate post-SGTR cooldown method:

a. SELECT appropriate procedure:

ES-3.1, Post-SGTR Cooldown Using Backfill. OR ES-3.2, Post-SGTR Cooldown Using Slowdown. OR

ES-3.3, Post-SGTR Cooldown Using Steam Dump.

              --_l1li"---

b. GO TO selected procedure.

END Page 40 of41

E-3 SQN STEAM GENERATOR TUBE RUPTURE Rev. 17 Page 1 of 1 APPENDIX C ESTABLISHING CePIT FLOW

1. ENSURE CCP suction aligned to one of the following:

RWST with level greater than 27°j{, o OR
RHR pump discharge USING ES-1.3, Transfer to RHR Containment Sump. o

2. CLOSE charging flow isolation valves FeV-52-S0 and FCV-62-91. o

3. OPEN CePIT outlet valves FCV...63-26 and FCV-63-25. o

4. OPEN CePIT inlet valves FCV-63-39 and FCV-63-40. o END OF TEXT Page 41 of 41

JPM 22-AP2 Page 1 of 18 Rev 3 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f JPM 22-AP2 CALIBRATE POWER RANGE NUCLEAR INSTRUMENTATION PR*EPAREDI REVISED BY: Date/ VALIDATED BY:

Date/

APPROVED BY: Date! (Operations Training Manager) CONCURRED: ** Date/ (Operations Representative)

Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM,or individual step changes that do not affect the flow of the JPM.

             ** Operations Concurrence required for new JPMs and changes that affect the flow *of the JPM (if not driven by a procedure revision).

JPM 22-AP2 Page 2 of 18 Rev 3 I NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/ NUMBER REVISION AFFECTED REVISED BY: 0 Created from JPM 22. Y 8/2/04 All MG Croteau 1 Updated References N 10/5/05 All JJ Tricoglou 2 Updated References. Minor format N 2/15/07 All RH Evans changes. 3 Added detail to steps and standards All v- Specify if the JPM change will require another validation (Y or N). See cover sheet for criteria.

JPM 22-AP2 Page 3 of 18 Rev 3 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task: Calibrate the Power Range Nuclear Instrumentation JAITA task:

       # 0150050201              (RO)

KIA Ratings: 015000 A1.01 (3.5 - 3.8) 015020 G9 (3.4 - 3.3) 015020 G13 (3.3 - 3.6) 015000 A4.02(3.9 - 3.9) Task Standard:

1) EaCh channel of Power Range instrumentation (on its power range "A" drawer) will indicate within acceptance 'criteria tolerances of the calorimetric.

2) The unit is not tripped by a power range neutron flux rate trip.

Evaluation Method: Simulator __ X_ _ In-Plant - - -

=======================================================================

Performer: NAME Start Time - - - Performance Rating: SAT UNSAT Performance Time Finish Time ------ Evaluator: SIGNATURE DATE

=======================================================================

COMMENTS

JPM 22-AP2 Page 4 of 18 Rev 3 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Sequenced steps identified by an "s"

2. AnyUNSAT requires comments

3. This task is to be performed using the simulator in IC #16.

[Rx Power should be ~ 100 0/0]

4. MANUALLY ADJUST N-41 and N-43 power to between 100.5 and 101.00/0. ENSURE all other NIS reactor power indications are between 99.5 and 100.50/0.

5. Ensure operator performs the following required actions for SELF-CHECKING;

a. Identifies the correct unit, train, component, etc.

b. Reviews the intended action and expected response.

c. Compares the actual response to the expected response.

Validation Time: CR. 27 min Local _ _~_...:..-- Tools/Equipment/Procedures Needed: 0-SI-OPS-092-078.0, Sections 3.0, 6.1,6.2, Appendix D

References:

F~eference l-itle Rev No,

1. 0-SI-OPS-092-078.0 Power Range Neutron Flux Channel Calibration By 18 Heat Balance Comparison

====================="============================================

READ TO OPERATOR Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. The unit is at steady state conditions with all NIS channels and LEFM operable.

INITIATING CUES:

1. You are theCRO and the US has directed you to perform.O-SI-OPS-092-078.0.

2. Section 4.0 of 0-SI-OPS-092-078.0 has been completed.

3. Notify the US when the Sihas been completed and any necessary adjustments have been made.

JPM 22-AP2 Page 5 of 18 Rev 3 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 1.: Obtain the appropriate procedure. SAT UNSAT STANDARD: Operator identifies O-SI-OPS-092-078.0and goes to section 6.0 "Performance" . Start Time_ _ COMMENTS: STEP 2.: [1] VERIFY availability of LEFM calorimetric power: SAT [aj CHECK LEFt~l s.tatus NO:Rf\{AL :Ctn ICS {NSSS .and BOP} UNSAT CUrT:'ot Calcritnetrrc Data s.cre;e.:rL

                            "{ES                NC~

o 0 [bI CHECK LEFfs{ Core Themlal Pewer (ICS point 0211,s) sho-#i.n~g g~:<od {gre'en) data. YES N{) o [c] CHEC.K LEFrit1lv1FVV he,ader te:rrq:<<rature {ICS point T85C2M.A.) greater ti~v3m or equai to 2SD:::Fv YES N:Q a STANDARD: Operator pulls up LEFM ICS screen and points, then annotates procedure that LEFM calorimetric power is available. COMMENTS:

JPM 22-AP2 Page 6 of 18 Rev 3 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 3.: [2] IF LEFM calorimetric power NOT available OR ICScomputer NOT SAT available, THEN .... PERFORtA the folk~vling: UNSAT Ie] IF LEFM c~JOrinl:etr,:c* power CANNOT be rest.ored in tirT:i:e to OOP1:lplete this 5.unte*:::Hance~ THEN' PERFOR'" .the -foHow~ng. .

1.: R.EDUGE reactor pC~tler t~

98J'~~ (341*1 ()i1VJt). or ;'ess U.S1NG V t 11-8 {if d"iaHah4e} orN:;SA 2.. :WHE\N reactor pO'i~ie:r is less* thang8.7"~~,.

THEN CONTINUE this. ~ns:ructIon 'U*s;in:g alternate power ind5cati ens as 5.p;<JE<c::me(i be!kt\Y. STANDARD: Operator marks the 4 sub steps (a, b, c.1, & c.2) N/A because the LEFM was determined to be available in the previous step. COMMENTS:

JPM 22-AP2 Page 7 of 18 Rev 3 Job Performance Checklist sTEP/sTANDARD sAT/UNSAT STEP 4.: [3] DETERMINE reactor core power level by performing the applicable SAT appendix below. UNSAT RCS AT greater th3~n j5~~~ .and A CJ LEF't1 :CJC*re the:rm:3il pOtf<~r (U211,B) .avajlabre' {step (1] acc~¥t;!kc:e criteria r;l:E:t) RGS ATbetw*een t:~~lJ) and 4D%.and :6 a LE F}t1 -(;SDre tnennal p~:<:ti'r (U211 B}N(t~T av*ailabtE' xG.S ~ T grea,:er than 4D~;'~ C Cl LEF't.1 :core the;f:fna~ pC{ttef (:U2118) N::DT a'Jailab4e

but tcs po~nt U1118 is available RG.S AT 9lreater than 4-D~'&and [) Cl lCS corE: therrnaI pCtl.i"er indic:aiicn (U1 t tS and U2t tEl NOT a'ia~J3ible AND RECORD below the ( N/A power if using printout from ICS) 0/0 Rated Core Thermal Power = 0/0 Cue: Inform the operator that the ICS printer is not available.

Cue: If candidate asks if the engineering procedure O-PI-SXX-OOO-022.2 has been performed, state that it has not been performed. STANDARD: Operator determines Appendix A. is applicable to determine the reactor power level. COMMENTS:

JPM 22-AP2 Page 8 of 18 Rev 3 Job Performance Checklist STEP/STANDARD SAT/UNSAT EVALUATOR NOTE: The following steps are from Appendix A. STEP 5.: [1] ENSURE S/G blowdown flows are updated by performing the following functions onlCS: [a] SELECT "NSS & BOP". [b] SELECT "CALORIMETRIC FUNCTION MENU". [c] SELECT "UPDATE OPERATOR ENTERED SLOWDOWN FLOW" P;8RFORtAone 0:1 the falhrrt#lfrt:Q opt::~~ns (\Nl.~~ opbonnot used) 1 ~ IF using :CC411puter p:~~~nt if 2:26:tAl SiG To1:a!§ Slo¥/dcvln flo'vi, THEt4 SAT fa) 'VERlfY ~*Oint v-a.:j::!j':E is. updLa'bng (chang;:iniQ vaiktes).. UNSAT (b) If ~:c:f.nputer po:j::nt is. ~iOT ulpdatingL J T:HE.N NOTIFY}t1 :~13 that pc:int is nc4 upda.tlrtg c;nd inltia1eVVCt.. ('a] RECORD Icc~d read~ngs fo;! SIG ble-\u.dc~tJn fktVI:: [ReS BLO:WI)O\'VN flOW LOOP (GP'~}. 2 3 4 FI-1i-"164 Ib]i E:t4SURE b-fcf'-J~dc-{\~\n uDvrs. above entered :~n ICS.. VIAIT a minirnun1 e:f to minut.es to allow prograrTl b,:; a.ccurately re'fle~::::t n:E'~i"l Jialue.. Cue: The blowdown flow point is updating and manual blowdown flows are not required. STANDARD: Operator determines blowdown flow is updating and marks substeps 1b, all of substep 2 N/A. COMMENTS: j

JPM 22-AP2 Page 9 of 18 Rev 3 Job Performance Checklist STEP/STAN*DARD SAT/UNSAT STEP 6.: [2] SELECT "DISPLAY CURRENT CALORIMETRIC DATA" on ICS SAT Calorimetric menu AND PERFORM one of the following: UNSAT _ _ _ _ _ M\¥t

                                                                    ._----     ~~~

OR* rbl P\RlNT po\ver ie'V"'el a:nd N~S ll'a~UeS AND* ATTACH re[fl*Oft to th@s instnJ'ctJcn. Cue: Inform the operator that the printer is not available. STANDARD: Operator records U2118 and U1127 values. COMMENTS: EVALUATOR NOTE: The operator should transistion back to section 6.1 at the completion of Appendx A. The following steps are from Section 6.1. STEP 7.: [4] RECORD "AS FOUND" power level from each of the four NIS A Channel SAT drawers. UNSAT P'OW:EjRRAN*GE ~, AS-fOU:N'D"~ CHANt*rEt N.'IS POl.VER t.%}:

                                  \t~J-41

():, 1-~:2-50tnt5B 1

                                  \r4-42 LXI-Si2-50C~~B )

N-4~3

{X.I-@:2-a001B)

N-44 tX:I-2i2-5GrTIf6;B J STANDA*RD: Operator records NIS power range readings from the A channel drawers on 1-M-13 on1-XI-92-5005B,50068, 50078, and 50088 COMMENTS:

JPM 22-AP2 Page 10 of 18 Rev 3 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 8.: [5] COMPARE NIS indication with core thermal power level. SAT [a] CHECK appropriate box to indicate whether the following "as-found" ACCEPTANCE CRITERIA were satisfied. UNSAT ACCEPTAN,CE CRITERiA: The indicatedNlS power le'tel recorded i:n st$p [4] is equal10 the core thermal: pewer le~~ei- recorded iin step {31 >~r as W-s*tedon the ~~rintedco'PY ~D wtihin +/- 2.0 }:~rce:rft. YES filA NJSGhanneoI N-41 Cl a NmSChannet N4.2 o a N:::S Channe*;l N-43 o Q: N:::S Channe:i N*-44 o Q: STANDARD: Operator CHECKS to determine if NIS channels are within ~ 2%. Then, Checks YES for all NIS channels. COMMENTS: STEP 9.: [b] IF any NIS channels were inoperable during the performance of SAT this instruction, THEN: NOTIFY applicable unit SRO that this SI must be UNSAT performed on all inoperable NIS channels when they are returned to service. STANDARD: Since all were operable per the initiating conditions, the operator marks this substep N/A. COMMENTS: STEP 10.: [6] VERIFY that all NIS channel indications are within +/-3 percent of the SAT determined core thermal power level. YES NO UNSAT Q a STAN.DARD: Operator checks the YES*box. COMMENTS:

JPM 22-AP2 Page 11 of 18 Rev 3 Job Performance Checklist STEP/STAN DARD SAT/UNSAT STEP 11.: [7] IF a NIS channel was more than 3 percent in error in the non- - SAT conservative direction (core thermal> NIS) THEN NOTIFY Engineering to determine if the calibration error - UNSAT impacts operability of the NIS high flux trip. STANDARD: Operator marks this step N/A. COMMENTS: STEP 12.: [8] CHECK appropriate box to indicate whether the following "as-found" - SAT acceptance criteria were satisfied:

                                                                                                -   UNSAT ACCEPTANCE CRITERIA:                The indicated NIS power level recorded in step [4] is less than or equal to 100.5 percent.

YES NO NIA N::1S *C;n,.anne::[ N*-41 Q :0 Q Ni:iS e,ho*anne':; N**-42 U :Q Q N::[SChanne{ N-43 Q :0 Q i~,ESC\h'.*anne:-: N*-4.; 0 'Q Q STANDARD: The operator checks NO forN-41 and N-43 and checks YES for other 2 channels. COMMENTS: STEP 13.: [9] IF any channel does not meet acceptance criteria, OR NIS Channel - SAT adjustment is desired ,THEN PERFORM adjustment of section 6.2 - UNSAT AND/OR REDUCE reactor power not to exceed 100 percent. STANDARD: Operator continues on to section 6.2. COMMENTS:

JPM 22-AP2 Page 12 of 18 Rev 3 Job Performance Checklist STEP/STANDARD SAT/UNSAT EVALUATOR NOTE: The following steps are from Section 6.2

                                                                                             -    SAT STEP 14.:  [1]   IF calculated average power in Section 6.1 or on printed copy and differs by more than 30/0 from average RCS delta T, THEN                            -    UNSAT NOTIFY Engineering to determine the cause.

STANDARD: Operator determines calculated average power and average delta T does not differ by more than 3% by comparing calculated average power against delta T from ICS or use 1-M-5 delta T instruments and N/As this step. COMMENTS: STEP 15.: [2] VERIFY reactor power has remained constant (~ 0.5%) since - SAT performance of section 6.1.

                                                                                              -   UNSAT STANDARD:      Operator ensures power has remained stable since he/she took the readings.

COMMENTS: STEP 16.: [3] IF NIS power range channel is inoperable - SAT THEN REQUEST Instrument Maintenance to Bypass inoperable NIS channel in - UNSAT accordance with O-PI-IXX-092-001.0. STANDARD: Operator N/As this step since aU power range instruments are operable. COMMENTS: STEP 17.: [4] ENSURE all NIS power range channels are operable or bypassed with no - SAT bistables tripped.

                                                                                                -  UNSAT STANDARD:       Operator verifies no bistables tripped by monitoring Trip status panel, 1-XX-55-5, bistable lIights on 1-M-5. (Initial conditions had all channels operable)

COMMENTS:

JPM 22-AP2 Page 13 of 18 Rev 3 Job Performance Checklist STEP/STAN DARD SAT/UNSAT STEP 18.: [5] ENSURE rod control system is in MANUAL in accordance with 0-SO-85-1 - SAT

                                                                                           -     UNSAT STANDARD:      Operator turns HS-85~511 0, ROD CONTROL MODE SELECTOR, to the MANUAL position. Should refer to 0~SO-85-1. A laminated sheet is available.

COMMENTS: Evaluator Note: Procedure contains a note stating Steps [6J ,through [9J must be completed on one NIS channel before proceeding to the next channel. Operator must adjust the N-41'and N-43, may choose to adjust all 4 channels. STEP 19.: [6] IF rate trip exists '(or occurs) on the NIS channel being calibrated, THEN - SAT CLEAR that channels trip signal (momentarily set RATE MODE switch to - UNSAT RESET position) and annunciator XA-55-6A,. "NC-41U or NC-41K NIS POWER RANGE HIGH NEUTRON FLUX RATE," before proceeding to the next NIS channel.

                                                           'Trip Cleared    Ni,A.

N ~S Ch,anne~~ ~i-41 0 ~O NlSGhanne,* N-42 U 0 Critical Step Nis Ghann ei.~ ~J-43: Q ;Q N'~S C.th1inne,~~ N-44 0 :0 STANDARD: Operator verifies NO rate trip signals are inon ANY of the PR and the annunciator is clear.

CRITICAL PORTION: If rate trip occurs the operator resets it prior to continuing to the next channel.

COMMENTS:

JPM 22-AP2 Page 14 of 18 Rev 3 Job Performance Checklist STEP/STANDARD SAT/UNSAT STEP 20.: [7] ADJUST gain potentiometer on associated channel's power range B drawer to bring that channel's indicated power level to within +/-. .5% of the N-41 adjustment calorimetric power recorded in section 6.1 or listed on the printed copy. AND SAT ENSURE gain potentio~et~r latch re-engaged. __ UNSAT J4.djusiment Required NJS Ch~annet N41 a CI NISChanne;; ti-42 a Q N-43 adjustment N~S Gh*anne*§ N-4.3 a U a Q SAT STANDARD: Operator must adjust N41 and N43 to satisfy criteria. The operator UNSAT should repeat the above step prior to adjusting the second PRo (only the bold portion of the standard is critical) COMMENTS: Critical Step STEP 21.: [8] IF fine gain potentiometer on power range B drawer will not provide enough adjustment to satisfy the calibration requirements of step [7], THEN REQUEST Instrument Maintenance to adjust the coarse gain (resistor R312, Coarse Level Adjust) inside the applicable power range drawer, AND READJUST fine gain potentiometer to achieve calibration requirements specified in step [7]. It,djustrrtent Reql1!ired r~ iSChannefi t4-41: o N ~S Ch*anne~ N-42 o t~J lSCih.anne*ili t4-43: o N lSChanne1 N-44 o STANDARD: Operator marks step as N/a because the fine gain will provide the needed adjustment. COMMENTS:

JPM 22-AP2 Page 15 of 18 Rev 3 Job Performance Checklist STEP/STAN DARD SAT/UNSAT STEP 22.: [9] IF additional NIS channel(s) require calibration, THEN N-41 adjustment RETURN to step [6] SAT Evaluator note: Procedure step f6] is JPM step 19 _UNSAT STANDARD: Operator may return to step [6] to adjust either N41 or N43 or other 2 N-43 adjustment channels if desired. After adjustments to Nls is complete, the operator continues to the next step SAT COMMENTS: UNSAT STEP 23.: [10] WHEN NI*S adjustments have been completed, THEN SAT RECORD the "as left" power level from NIS power range channels. UNSAT POWER RA:NGE ~"A.s-LEFT*** CH,ANN.El NIS POJ'/ER (£>/.3}

                                     ~4-42   (;\J-92-5000'8:)
                                     ~4-4:3. CXJ-92-5007B)

NJ-44 tXi-Q2-5008B J STANDARD: Operator records the readings from each of the 4 PR Nls. COMMENTS: STEP 24.: [11] IF NIS power range* channel is inoperable, THEN SAT REQUEST Instrument Maintenance to remove Bypass on inoperable NIS channel in accordance with O-PI-IXX-092-001.0. UNSAT STANDARD: Operator NIAs this step since all Nls are operable. COMMENTS:

JPM 22-AP2 Page 16 of 18 Rev 3 Job Performance Checklist STEP/STAN DARD SAT/UNSAT STEP 25.: [12] CHECK appropriate box to indicate whether the following "as left" - SAT acceptance criteria were satisfied.

                                                                                                                        -   UNSAT ACCEPTAN:CE CHITERlA.:          T.he indrc.ated NIS patNer leve!: recorded in step (1 OJ is wrthin +/- 0".5 percent the: cal*oMfmeftrk: p-o'werieve! lreoorded in SectonG.1 01' a:s Jisted en the printed copy.

YES t~o NlA NWS Ch.anne:~ N-41 Cl a Q 1-'-.ns Channe:t N-42 U :Q Q Ni:;S ChanneJ N-43 Q Q Q Nl\tS Ch.anne;~ N-44. a :Q u~ STANDARD: Operator checks YES box for N41, N42, N43, & N44, all being within

!:. .5% (of 100 % ).

COMMENTS: STEP 26.: [13] IF acceptance criteria were NOT satisfied for any NIS channel, THEN - SAT NOTIFY Shift Manager that acceptance criteria were 'NOT met and another performance of this test is necessary, - UNSAT subsequently action 2 of LCO 3.3.1.1 (Unit 1) orLCO 3.3.1 (Unit 2) must be satisfied if the other performance does not meet acceptance criteria. STANDARD: Operator N/As this step. COMMENTS: STEP 27.: [14] RETURN rod control system to AUTO in accordance with O-SO-85-1. - SAT Cue: When operator acknowledges the 3 minute wait in the note preceding the - UNSAT step, Inform the operator that 3 minutes have elapsed. STANDARD: Operator places control rod bank selector"switch to the AUTO after waiting at least 3 minutes for signal to decay. Should refer to O-SO-85-1. A laminated sheet is available. COMMENTS:

JPM 22-AP2 Page 17 of 18 Rev 3 Job Performance Checklist STEP/STAN DARD SAT/UNSAT STEP 28.: Notify SRO that the NIS channels have been calibrated. SAT STANDARD: Operator notifies the SRO that the SI has been completed and all power UNSAT range nuclear instruments have been adjusted to meet the acceptance criteria. Stop Time_ _ COMMENTS: END of JPM

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate tome when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIO.NS: The unit is at steady state conditions with all NIS channels and LEFM operable. INITIATING CUES: You are the CRO and the US has directed *you to perform 0-SI-OPS-092-078.0. Section 4.0 of 0-SI-OPS-092-078.0 has been completed. Notify the US when the 51 has been completed and any necessary adjustments have been made.

...""" ~¥ '" ........... ~ ....

             . ...  ~ .
                      " .1.1'.....'. .-...,'_"'.

TVAN STANDARD SPP-8.2 PROGRAMS AND SURVEILLANCE TEST PROGRAM Date 06-04*2004 PROCESSES , Page 25 of 29 r l SURVEILLANCE TASK SHEET (STS) Page 1 of 1 SURVEILLANCE TASK SHEET (ST5) Work Order Page of SI Key ----,.p.....~C~ Procedure No. 0 *~f-OPS-oq1.-0?R.U OH""l"".c;~------:-------i1 Title _...L..rP'l...;;;.;.lc~~p.....;;,,;o.G~~_(=__~~~~~~t-t~G-~~£'r'-1=-~[l,l~ ltf..L.-~~A.L...---i' j

                                                                                                                                                                                                  '1
                                                                                                                                                                                            ,,-.!1(~11 /

Y!1v Perf. Section \ J t ~O , I O.fi.:.> /*r "1/1 il C(!xl- /pg'ALN' Test Reason -~S*e.-:",H"'="';'f:~ c:.. t\(J";",'-;"-r~~p~--= r(2.~~F~OQJ'1~M---:-(?l.t .t-A-~""':;ttt~/!J'-+~tr-a-v-£Iio-n-to-B+3~-J.g i-n:"'!-S~R-O- I Dat'e Time Data Sheets --------------i1 .I / Due -----.....-.----------i! V' Extension

                                                                                          ---~------------H rv1ax. Extension                                                                                                                                                           Start Date            Time
                                                                                          --------------!l Frequency     -----------..---,;.....;,-.--!l EO ASME Xl
                                                                                          --------------11 APP Mode                                                                                                                                                         Completion Date          Time Performance ~1ode
                                                                                          --------------11
                                                                                           ---------------il Operational Condition          --==------,=---.;.......;...----~-il Dry Cask Storage              O*Yes                      0 No Subsequent Reviews - - - - - - - - - - - - - - i l Instruction' Test Director/lead Performer                                          Date
                                                           ~~~~~~.....;,-.~~~-~~~~~~~~~~~A~e~aoceC~~aRe~ewSRO                                                                                                                                             Date           Time (ASME Xl Sis require review within
                                                            '--~~-------__11--~--~-~_+_~-+_~---11                                                                                     96 hours)                        .

Independent Reviewer Date ANII (If required) . Date Copy of STS sent to Scheduling

                                                                                                                                         .,                                                                                                           Initials            Date Remark:                                                                         -

Section No. Men Our. Hrs Section No. Men Our. Hrs

                                                                                                                                                                                                                        ~.
                                                                                                                                                                                                                       !~-------    Section               No. Men        Our. Hrs k__-Se--*           ---

euoo No. Men Our. Hrs I i.

                                                          . TVA 40753[06-20041                                                                                                Page 1 of 1                                                                    SPP-8.2-1 [06.04-20041

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SURVEILLANCE INSTRUCTION O-SI-OPS-092-078.0 POWER' RANGE NEUTRON FLUX CHANNEL CALIBRATION BY HEAT BALANCE COMPARISON Revision 18 QUALITY RELATED PREPARED/PROOFREAD BY: ~---------------- w. T.LEARY RESPONSI BLE ORGAN IZATION: _O.;;...;p.......E~R A~T...-....;IO__.N. ; . ",; ;,S _ APPROVED BY: KEITH PERKINS EFFECT'IVE DATE:03/30/06 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION: Revised to add a.note.directing that consistency between channels be considered when determining if adjust is desired. This is a minor change. THIS PROCEDURE COULD AFFECT REACTIVITY.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 2 of 33 TABLE OF CONTENTS Page 1 of 2 Section Title Page TABLE OF CONTENTS 2

1.0 INTRODUCTION

4 1.1 Purpose 4 1*.2 Scope 4 1.2.1 Surveillance Test to be Performed 4 1.2.2 Requirements Fulfilled 4 1.2.3 Modes 4 1.3 Frequency and Conditions 4 2.*0 REFERENCES* 5 2.1 Performance *References 5 2.2 Developmental References 5 3.0 PRECAUTIONS AND LIMITATIONS 5 4..0 PREREQUISITE ACTION*S .....................................*........................................................ 7 4.1 Preliminary Actions 7 4.2 Measuring a*nd Test Equipment, Parts, and Supplies 7 4.3 Field Preparations 7 4.4 Approvals and Notifications 7 5.0 ACCEPTANCE CRITERIA 7

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 3 of 33 TABLE OF CONTENTS Page 2 of 2 Section Title Page 6.0 PERFORMANCE ;. 8 6.1 As-Found Data 8 6.2 NIS Channel Adjustment 14 7.0 POST PE.RFORMANCE ACTIVITY 18 APPENDICES APPENDIX A: CALCULATION OF CORE THERMAL POWER LEVEL USING LEFM 19 APPENDIX B: SUBSTITUTION OF RCS ~T AT LOW POWER LEVELS (~400/0 WITH LEFM NOT AVAILABLE) 22 APPENDIX C: CALCULATION OF CORE THERMAL POWER LEVEL USING U1118 (> 40% WITH LEFM NOT AVAILABLE) 23 APPENDIX D: CALCULATION OF CORE THERMAL POWER LEVEL WITH PLANT COMPUTER INOPERABLE (RCS ~T GREATER THAN 400/0) 26 SOURCE NOTES 33

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 4 of 33

1.0 INTRODUCTION

1.1 Purpose This Surveillance Instruction (SI) provides detailed steps for ensuring proper calibration of the power range neutron flux channels. 1.2 Scope 1.2.1 Surveillance Test to be Performed This Instruction performs a comparison between the power level calculated by the Nuclear Instrumentation System (NIS) power range neutron flux channels and the "true" power level as determined by a secondary system heat balance based value. If necessary, the power range channels are adjusted to agree with the "true" power level. This instruction also verifies availability of Leading Edge Flow Meter (LEFM) calorimetric power. 1.2.2 Requirements Fulfilled Performance of this Instruction completely fulfills Technical Specification (TS) Surveillance Requirement (SR) 4.3.1.1.1.8.2 (Table 4.3-1, item 2, note 2) and Technical Requirements Manual (TR) 4.3.3.15.1. 1.2.3 Modes A. Applicable Mode - 1 (above 15 percent power). B. Performance Mode - 1 (above 15 percent power). 1.3* Frequency and Conditions This test must be performed at least once every 24 hours when the reactor power level is greater than 15 percent. [C.3] To ensureNIS accuracy, this test should be performed when directed by O-GO-4 or O-GO-5. In the event that the Plant Computer is unavailable, provisions have been incorporated in this procedure to fulfill the SR requirements. [C.5]

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 5 of 33

2.0 REFERENCES

2.1 Performance References O-PI-SXX-OOO-022.2, Calorimetric Calculation. (Optional) 2.2 Developmental References A. SQN Technical Specifications. B. SPP-8.1, Conduct of Testing C. NP-STD-4.4.7, Attachment 1, Writer's Guide for Technical Documents D. 0-PI-NUC-092-082.0, Post Startup NIS Calibration following Core Load. E. Memo from Reactor Engineering ~ RIMS S57 941219 934 F. Integrated Computer System Critical Design Requirements and Operator's Guide. 3.0 PRECAUTIONS AND LIMITATIONS A. Reactor power must remain constant (+/- 0.5°/0) during the performance of Sections 6.1 and 6.2. Itis desirable for any required NIS adjustment be made promptly during performance of these sections. B. Average ReS temperature (T avg) should be maintained within 0.5°F of RCS reference temperature (Tref)' C. Caution should be exercised when adjustingNIS power range instrumentation to minimize the potential for a channel trip. D. Only one NIS channel shall be adjusted at a time. If a rate trip occurs, the channel's trip signal and annunciator on panel XA-55-6A, "NC-41 U or NC-41 K NIS POWER RANGE HIGH NEUTRON FLUX RATE" must be cleared before proceeding to the next NISchannel.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 6 of 33 3.0 PRECAUTIONS AND LIMITATIONS (Continued) E. Operations and Engineering should be notified if larger than normal channel adjustments (as determined by the SRO) are required to bring the power range channels into alignment with calculated core thermal power. [C.4] An operability concern may exist if excessive error in the non-conservative direction adversely impacts the NIS high flux trip setpoint. The 3% tolerance for calibration error on the high flux trip setpoints was selected using the extrapolated error from the 30% power level. F. The reactor cores have been loaded with a low leakage -loading pattern which can affectNIS Reactor Power level indications such that differences greater than the Acceptance Criteria can occur between NIS and true power level. The impact of the NIS non-linearity due to low leakage loading pattern isin the conservative direction, since NISindicated power rises faster than true power during a power increase. 0-GO-5 may direct performance of this procedure to ensure excessive errors in the non-conservative direction do not exist. During plant restarts, Reactor Engineering may perform 0-PI-NUC-092-082.0 at 40/0 power to provide an initial NIS correction for startup. G. Technical Specifications require aheatbalance calculation for adjustment of theNIS when the Plant is above 15% power within 24 hours. If the Leading Edge Flow Meter (LEFM) is available, ICS point U2118 is required to be used for the heat balance when greater than 15% power (TRM 3.3.3.15). If LEFM is NOT available, then Loop ~T data should be used between 15 and 40% power due to potential inaccuracies in the feedwater -flow venturi heat balance below 40%. If LEFM is NOT avai-Iable above 40%, then venturi-based calorimetric power (U1118) should be used.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT" BALANCE COMPARISON Page 7 of 33 J Unit- - -I- - - Date )'XJ b!.!.rIi ( 4.0 PR"EREQUISITE ACTIONS NOTE During the performance of this Instruction, any "IFITHEN" statement may be marked N/A when the corresponding stated condition does not OCCUL 4.1 Preliminary Actions [1] ENSURE Instruction to be used is a copy of effective version _()Il and Data Package Cover Sheet is attached. !'J{;- 4.2 Measuring and Test Equipment, Parts, and Supplies None; 4.3 Field Preparations [1] ENSURE reactor power and RCS average temperature are stable. 4.4 Approvals and Notifications [1] NOTIFY SRO of test performance. 5.0 ACCEPTANCECRITERIA A. The indicated "as-found" power level from each operable NIS neutron flux channel must equal the core thermal power level to within +/- 2.0%. B. The indicated "as-left" power level from each operable NIS neutron flux channel that was adjusted must equal the core thermal power level to within

                +/- 0.5%.

c. If the criteria stated above are NOT satisfied, the SRO shall be notified and Action Requirement 2 of TS Table 3.3-1 satisfied.

D. LEFM shall be used for the plant calorimetric measurement for power range NIS calibration by heat balance comparison. If this criteria is NOT satisfied, the SRO shall be notified and the applicable action of TRM 3.3.3.15 shall be entered.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092~078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 8 of 33 Unit- - - - - - Date- - - - - 6.0 PERFORMANCE 6.1 As-Found Data NOTE 1 The following step determines if LEFM is available to satisfy TRM 3.3.3.15. If LEFM is NOT available, operators should notify US, document status and continue with next step. NOTE 2 Main feedwater temperature must be greater than or equal to 250°F for reliable LEFM data. [1] VERIFY availabi-lity of LEFM calorimetric power: [a] CHECK LEFM status NORMAL on ICS (NSSS and BOP) Current Calorimetric Data screen. YES NO o 0 [b] CHECK LEFM Core Thermal Power (ICS point U2118) showing good (green) data. YES NO o 0 [c] CHECK LEFM MFW header temperature- (ICS point T8502MA) greater than or equal to 250°F. YES NO o 0 ACCEPTANCE CRITERIA: LEFM is available based upon the indications above.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 9 of 33 Unit- - - - - - Date- - - - - 6.1 As-Found Data NOTE With LEFM unavailable, AFD limit lines in COLR must be made more restrictive by 1% and Rod Insertion Limit lines in COLR must be raised by 3 steps. These adjustments are automatically applied in ICS. [2] IF LEFM calorimetric power NOT available OR ICS computer NOT available, THEN PERFORM the following: [a] ENTER applicable action of TRM 3.3.3.15. [b] ENSURE work order initiated as required. [c] IF LEFM calorimetric power CANNOT be restored in time to complete this surveillance, THEN PERFORM the following:

1. REDUCE reactor power to 98.7°1b (3411 MWt) or less USING U1118 (if available) orNIS.

2. WHEN reactor power is less than 98.7%,

THEN CONTINUE this instruction using alternate power indications as specified below.

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1 &*2 HEAT BALANCE COMPARISON Page 10 of 33 Unit- - - - - - Date- - - - - 6.1 As-Found Data NOTE If Engineering has performed 0-PI-SXX-000-022.2, then the applicable section{s)of 0-PI-SXX-OOO-022.2 may be used in place of Appendix C orO to obtain the current calorimetric power. [3] DETERMINE reactor core power level by performing the applicable appendix below: CONDITION APPENDIX ../ ReS L1 T greater than 15'% and 0 A LEFM core thermal power (U2118) available (step [1] acceptance criteria met) RCS L1 T between 15% ahd400~ and 0 B LEFM core thermal power (U2118) NOT available RCS L1Tgreater than 40% 0 C LEFM core thermal power (U2118) NOT available but ICS point U1118 is available RCS L1T greater than 400/0 and D 0 ICS core thermal power indication (U1118 and U2118) NOT available AND RECORD below (N/A power if using printout from ICS):

              % Rated Core Thermal Power      =    -----

o~

SQN POWER RANGE NEUTRON FLUX O~SI-OPS-092--078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 11 of 33 Unit- - - - - - Date- - - - - 6.1 As-Found Data (Continued) NOTE Data for an inoperable NIS channel may be marked N/A. [4] RECORD "as-found" power level from each of the four NIS power range A channel drawers: POWER RANGE " AS-FOUND" CHANNEL NIS POWER (°10) N-41 (XI-92-5005B) N-42 (XI-92-5006B) N-43 (XI-92-5007B) N-44 (XI-92-5008B) NOTE The following step is performed to satisfy Tech Specs. [5] COMPARE NIS indication with core thermal power level. [a] CHECK appropriate box to indicate whether the following "as-found" acceptance criteria were satisfied: ACCEPTANCE CRITERIA: The indicated NIS power level recorded in step [4] is

                                 . equal to the core thermal power level recorded in step [3] or as listed on the printed copy to within +/- 2.0 percent.

YES NO N/A NIS Channel N-41 0 0 0 NIS ChannelN-42 0 0 0 NIS Channel N-43 0 0 0 NIS Channel N-44 0 0 0 RO orSRO

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 CHANNEL CALIBRATIONBY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 12 of 33 Unit- - - - - - Date- - - - - 6.1 As-Found Data (Continued) [b] IF any NIS channels were inoperable during the performance of this Instruction, THEN NOTIFY applicable unit SROthat this SI must be performed on all inoperable NIS channels when they are returned to service. [6] VERIFY that all NIS channel indications are within

                  +/-3 percent of the determined core thermal power level.

YES NO o o [7] IF a NIS channel was more than 3 percent in error in the non-conservative direction (core thermal power> NIS), THEN NOTIFY Engineering to determine if the calibration error impacts operability of the NIShigh flux trip. [8] CHECK appropriate box to indicate whether the following "as-found" acceptance criteria were satisfied: ACCEPTANCE C.RITERIA: The indicated NIS power level recorded in step [4] is less than or equal to 100.5 percent. YES NO N/A NIS ChannelN-41 0 0 0 NIS Channel N-42 0 0 0 NIS Channel N-43 0 0 0 NIS Channel N-44 0 0 0 RO or SRO

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 13 of 33 Unit~----- Date- - - - - 6.1 As-Found Data (Continued) NOTE Consistency between the four NIS PR channels is to be considered when determining if an adjustment is desired. [9] IF any channel does not meet acceptance criteria, OR NIS Channel Adjustment is desired,THEN PERFORM adjustment using section 6.2 AND/OR REDUCE reactor power not to exceed 100 percent. END OF TEXT

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 14 of 33 Unit- - - - - - Date- - - - - 6.2 NIS Channel Adjustment NOTE 1 Performance of this section is required only for those PR *channels designated by the Reactor Operator or that did not satisfy the acceptance criteria in Section 6.1. All other NISchannels may be marked N/A. NOTE 2 During the performance of Section 6.2, data required for an inoperable NIS channel may be marked N/A. [1] IF calculated average power in Section 6.1 or on printed copy differs by more than 3% from average ReS delta T, THEN NOTIFY Engineering to determine the cause. [2] VERIFY reactor power has remained constant (+/- 0.5 %) since performance of Section 6~ 1. NOTE The inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels. [3] IF NIS power range channel is inoperable, THEN REQUEST Instrument Maintenance to Bypass inoperable NIS channel in accordance with 0-PI-IXX-092-001.0. [4] ENSURE all NIS power range channels are operable or bypassed with no bistables tripped. [5] ENSURE rod control system is in MANUAL in accordance with 0-SO-85-1 . D

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 15 of 33 Unit- - - - - - Date- - - - - 6.2 NIS Channel Adjustment (Continued) NOTE 1 Steps [6] through [9] must be completed on one NIS channel before proceeding to the next channel. NOTE 2 NIS channels in the following step may be performed outof sequence. [6] IF a rate trip exists (or occurs) on the NIS channel being calibrated, THEN CLEAR that channels trip signal (momentarily set RATE MODE switch to RESET position) and annunciator on panel XA-55-6A, "NC-41UorNC-41 K NIS POWER RANGE HlGH NEUTRON FLUX RATE," before proceeding to the next NIS channel. Trip Cleared N/A NIS Channel N-41 o o NIS Channel N-42 o o NIS Channel N-43 o o NIS Channel N-44 o o First Person- - - - - - - CV _ NOTE The gain potentiometers have latches which must be disengaged prior to adjustment, and re-enga*ged following adjustment. [7] ADJUST gain potentiometer on associated channel's power range B drawer to bring that channel's* indicated power level to within +/- 0.5% of the calorimetric power recorded in Section 6.1 or as listed on the printed copy. AND ENSURE gain potentiometer latch re-engaged. [C.2] Adjustment Required N/A NIS Channel N-41 0 0 NIS Channel N-42 0 0 NISChannel N-43 0 0 NIS Channel N-44 0 0 First Person _ CV -

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 16 of 33 Unit- - - - - - Date --~-- 6.2 NIS .Channel Adjustment (Continued) [8] IF fine gain potentiometer on power range B drawer will not provide enough adjustment to satisfy the calibration requirements of step [7], THEN REQUEST Instrument Maintenance to adjust the coarse gain (resistor R312, Coarse Level Adjust) inside the applicable power range drawer, AND READJUST fine gain potenti'ometer to achieve calibration requirements specified in step -[7]. Adjustment Required N/A NIS Channel N-41 o o NIS Channel N-42 o o NIS Channel N-43 o o NIS Channel N-44 o o First Person ~_ CV--------,.- [9] , IF additional NIS channel(s) require calibration, THEN R*ETURN TO step -[6]. [10] WHEN NIS adjustments have been completed, THEN RECORD "as-left" power level from NIS power range channels. POWER RANGE " AS-LEFT" CHANNEL NIS POWE*R (%) N-41 (XI-92-5005B) N-42 (XI-92-5006B) N-43 (XI-92-5007B) N-44 (XI-92-5008B) First Person _ IV _

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 17 of 33 Unit- - - - - - Date- - - - - 6.2 NIS Channel Adjustment (Continued) [11] IF NIS power range channel is inoperable, THEN REQUEST Instrument Maintenance to remove Bypass on inoperable NIS 'channel in accordance with 0-PI-IXX-092-001.0. [12]. CHECK appropriate box to indicate whether the foHowing "as-left" acceptance criteria were satisfied. ACCEPTANCE CRIT:ERIA: The indicated NIS power level recorded in step [10] is within +/-O.5 percent the calorimetric power level recorded in Section 6.1 or as listed on the printed copy. YES NO N/A NIS Channel N-41 o o o NIS Channel N-42 o o o NIS Channel N-43 o o o NIS Channel N-44 o o o RO or SRO [13] IF accepta.nce criteria were NOT satisfied for any NIS channel, THEN NOTIFY Shift Manager that acceptance criteria were NOT met and another performance of this test is necessary, subsequently action 2 of LCO 3.3.1.1 (Unit 1) or LCO 3.3.1 (Unit 2) must be satisfied if the other performance does not meet acceptance criteria. NOTE NIS channel adjustment may cause step change in input to rod control. A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off. [14] RETURN Rod Control System to AUTO in accordance with 0-SO-85-1. D END OF TEXT

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 18 of 33 7.0 POST PERFORMANCE ACTIVITY [1] NOTIFY SRO that test has been completed.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATIONBY Rev: 18 1&2 HEAT BALANC*E COMPARISON Page 19 of 33 Unit - - - APPENDIX A Date- - - Page 1 of 3 CALCULATION OF CORE THERMAL POWER USING LEFM NOTE 1 ICS allows two options for blowdown flows: Option #1 (Preferred) -use point [F2261.A] which requires no operator entered data (computer automatically updates the blowdown flows)*. Option #2 - use manually enteredS/G blowdown flow rates. NOTE 2 Computer point [F2261Alis more accurate than flow indicators located in the fan rooms. If the computer point is inoperable and blowdown flows from the FIS's are used, then indicated core thermal power may be a slightly differentvalue. [1] ENSURE S/G blowdown flows are updated by performing the following functions on ICS: [a] SELECT "NSSS AND BOP". D [b] SELECT "CALORIMETRIC FUNCTION MENU". D [c] SELECT "UPDATE OPERATOR ENTERED BLOWDOWN FLOW" on menu AND PERFORM one of the following options (N/A option not used): D

1. IF using computer point [F2261Al S/G Total Blowdown Flow, T*HEN (a) VERIFY point value is updating (changing values). D (b) IF computer point is NOT updating, THEN NOTIFY MIG that point is not updating and initiate WOo D

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 20 of 33 Unit - - - APPENDIX A Date- - - Page 2 of 3 NOTE Local readings of steam generator blowdown flow are obtained from Panel L-357.

2. IF manually updating blowdown flows, THEN

[a] RECORD local readings for S/G blowdown flow: RCS SLOWDOWN FLOW LOOP (GPM) 1 FI-1-152 2 FI-1-156 3 FI-1-160 4 FI-1-164 [b] ENSURE blowdown flows above entered in ICS. [c] IF blowdown flows were updated, THEN WAIT a m*inimum of 10 minutes to allow program to accur.ately reflect new value. D

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATIONBY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 21 of 33 Unit APPENDIX A Date Page 3 of 3 NOTE ICS printout may be used to documentpower level and NIS values. Since core thermal power fluctuates, a slight deviation may exist between the recorded core thermal power value (if used) and the printed sheet value (if used). SI acceptance is satisfied in the body of the instruction. [2] SELECT "DISPLAY CURRENT CALORIMETRIC DATA" on ICS Calorimetric menu AND PERFORM one of the following: D [a] RECORD the following: LEFM Core Thermal Power (U2118) ---_-----. Mwt Percent Rated Core Thermal Power (U 1127) ----- 0/0 OR [b] PRINT power level and NIS' values AND ATTACH report to this instruction. D

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 22 of 33 Unit - - - APPENDIX B Date-_--:.-- Page 1 of 1 SUBSTITUT*ION OF RCS i\T AT lOW POWER LEVELS (~ 40% WITH LEFM NOT AVAILABLE) NOTE 1 RCS delta T loops (~TO) are aligned to results of a secondary-side heat balance. Consequently, using i\Ts to adjust NIS at .Iow power levels still satisfies the requirement to use heat balance. Loop i\T is used to avoid potentially non-conservative errors in NIS power range indication if adjustments were made based upon an inaccurate secondary heat balance at a*low feedwater flowrate. At low power levels the traditional seco*ndary-side heat balance (U 1118) is not as accurate as Reactor Coolant Loop ~T'8. NOTE 2 This appendix should NOT be used if LEFM is operable. [1] CALCULATE the average RCSdelta T using control board indications or computer point for average RCS ~T. Loop A (TI-68-2D) °/0 PLANT COMPUTER Loop B (TI-68-25D) °/0 OR U0485 o~ Loop C (TI-68-44D) °/0 Loop D (TI~68-67D) °/0 Total °/0 -;- (4) =Avg ---~

                                                                                              °/0

[2] RECORD average RCS delta T as the core thermal power level 0/0.

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 23 of 33 Unit - - - APPENDIXC Date- - - Page 1 of 3 CALCULATION OF CORE -THERMAL POWER LEVEL USING U1118 (> 40% WITH LEFM NOT AVAILABLE) NOTE 1 This appendix is used when RCS L1T is greater than 40% and LEFM (U2118) NOT available, butlCS and U1118 are available. NOTE 2 ICSallows two options for blowdown flows: Option #1 (Preferred) - use point [F2261A] which requires no operator entered data (computer automatically updates the blowdown flows). Option #2 - use manually entered S/G blowdown flow rates. NOTE 3 Computer point [F2261A] is more accurate than flow indicators located in the fan rooms. If the computer point is inoperable and blowdown flows from the FIS's are used in the calculation of U1118, then expect U1118 to indicate a different value and adjustment of NIS may be required. [1] ENSURE S/G blowdown flows are updated by performing the following on les: [a] SELECT "NSSS AND BOP". D [b] SELECT "CALORIMETRIC FUNCTION MENU" D [c] SELECT "UP-DATE OPERATOR ENTERED SLOWDOWN FLOW' on menu AND PERFORM one of the following options (N/A option not used): D

1. IF using computer point [F2261A] S/G Total Slowdown Flow, THEN

[a] VERIFY point value is updating (changing values). D [b] IF computer point is NOT updating, THEN NOTIFY MIG that point is not updating and initiate WOo D

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 24 of 33 Unit - - - APPENDIXC Date- - - Page 2 of 3 NOTE Local readings of steam generator blowdown flow are obtained from Panel L-357.

2. IF manually updating blowdown flows, THEN

[a] RECORD local readings for S/G blowdown flow: Res BLOWDOWN FLOW LOOP (GPM) 1 FI-1-152 2 FI-1-156 3 FI-1-160 4 FI-1-164 [b] ENSURE blowdown flows above entered in ICS. [c] IF blowdown flows were updated, THEN WAIT a minimum of 10 minutes to allow program to accurately reflect new value. D

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 25 of 33 Unit - - - APPENDIXC Date- - - Page 3 of 3 NOTE ICS -printout may be used to document power level and NIS values. Since core thermal power fluctuates, a slight deviation may exist between the recorded core thermal power value (if used) and the printed sheet value (if used). SI acceptance is satisfied in the body of the instruction. [2] SELECT "DISPLAY CURRENT CALORIMETRIC DATA" on ICS Calorimetric menu AND D PERFORM one of the following: [a] RECORD the following: Venturi Core Thermal Power (U1118) Mwt Percent Rated Core Thermal Power (U1127) 0/0 OR [b] PRINT power level and NIS values AND ATTACH report to this instruction. D [3] IF any value isa blue "NCAl" quality, THEN PERFORM the following: [a] IF cause of bad data is unknown, THEN REQUEST assistance from MIG or ICS computer engineer. D [b] INITIATE WO if required. D [c] GO TO Appendix D. D

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 26 of 33 Unit - - - APPENDIX D Date- - - Page 1 of 7 CALCULATION OF CORE THERMAL POWER LEVEL W.ITH INOPERABLE PLANT COMPUTER (RCS ~ T Greater Than 400/0) NOTE 1 This appendix provides guidance determining calorimetric power when ICS core thermal power indication (U 1118 and U2118) is unavailable with power above 40% and the computer cannot be restored in time to complete SR 4.3.1.1.1. NOTE 2 0-PI-SXX-000-022.2 requires several hours from initiation until completion of power calculation. [1] IF O-PI-SXX-000-022.2 will be used for calorimetric data, THEN PERFORM the following: [a] NOTIFY Systems Engineering to perform manual calorimetric calculation using 0-PI-SXX~OOO-022.2. D [b] MARK remaining steps "N/A" in this appendix. D

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATIONBY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 27 of33 Unit - - - APPENDIX D Date- - - Page 2 of 7 NOTE 1 The remaining steps determine core thermal power by manually entering calorimetric data on opposite unit's ICS computer. This method requires adding 3.5% to the calculated power level for additional conservatism due to greater errors associated with indicator error and readability. Therefore, power level should be reduced to less than or equal to 96.5% before performance. NOTE 2 Calorimetric calculation on opposite unit's ICS assumes that blowdown flow is identical on each unit. This error is accounted for in the 3.50/0 correction factor. [2] IF opposite unit's ICS will be used to perform a calorimetric calibration, THEN PERFORM the following: [a] ENSURE reactor power less than or equal to 96.5%. D [b] ENSURE reactor power and RCS temperature stable. D

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 28 of 33 Unit - - - APPENDIX D Date- - - Page 3 of 7 NOTE 1 If ICSis unavailable, LE~M Feed flow and feed temperature may still be available onLEFM panel [LOCL-500-R183] in Aux Inst Rm. NOTE 2 MFW header temp must be greater than 250°F for reliable LEFM data. [3] IFLEFM feed flow and feed temperature is available on local LEFM panel, THEN PERFORM the following: [a] RECORD the following data: Paramete*r Indication Reading Loop 1 Feedwater Pressure PI-3-37 [M-3] psig Loop 2 Feedwater Pressure PI~3-50 [M-3] psig Lo.op 3 Feedwater Pressure PI-3-92 [M-3] psig Loop 4 Feedwater Pressure PI-3-105 [M-3] psig Loop 1 S/G Pressure PI-1-2A or 28 [M-4] psig Loop 2 S/G Pressure I PI-1-9Aor 9B [M-4] psig Loop 3 S/G Pressure PI-1-20A or 20B [M-4] psig Loop 4 S/GPressure PI-1-27Aor 278 [M-4] psig Total Feedwater Flow LEFM Ibm/hr Feedwater Temperature LEFM of (must be > 250°F) IV [b] SELECT Calorimetric Main Menu screen on other unit's ICS computer. D (step continued on next page)

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 29 of 33 Unit APPENDIX D Date Page 4 of 7 [3] (Continued) [c] SELECT LEFMSpecial Offline Calorimetric on Calorimetric Menu. D [d] ENTER data in ICS from table in substep 3 [a]. [e] SELECT function key F3 to execute calculation. D [f] PRINT calorimetric results. D [g] VERIFY data was correctly entered in ICS from table in substep 3 [a]. IV [h] RECORD Total S/G Thermal Power from calorimetric printout:

                             - - - -MWt

[i] CALCULATE percent power corresponding to item [h] _ _ _ _MWt ==

                                                    - - - 0/0 34.55 NOTE           The following step adds 3.5% to calorimetric power to compensate for additional errors in this method. The corrected power value below should be used in Section 6.1.

U] CAL*CULATE corrected core thermal power: (substep [i]) % + 3.5 °lb == ------ 0/0 [k] VERIFY substeps [g] through U]. IV

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 30 of 33 Unit APPENDIX D Date Page 5 of 7 NOTE 1,2-PI-ICC-003-036.0 provides details on required test equipment for feedwater temperature measurement.* [4] IF LEFM feed flow and feed temperature is NOT available, THEN PERFORM the fol"lowing: [a] NOTIFY MIG or Systems Engineering to install precision temperature monitoring 'equipment in feedwater header temperature wells TW-3-197 an.d TW-3-198 [TB el. 685]. D [b] RECORD average feedwater header temperature:

                                    - - - - - of MIG or Eng IV (step continued on next page)

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 31 of 33 Unit APPENDIX D Date Page 6 of 7 [4] (Continued) [c] RECORD the following data: Parameter Indication Reading Loop 1 Feedwater Press PI-3-37 [M-3] psig Loop 2 Feedwater Press PI-3-50 [M-3] psig Loop 3 Feedwater Press PI-3-92 [M-3] psig Loop 4 Feedwater Press PI-3-105 [M-3] psig Loop 1 S/G Pressure PI-1-2A or 2B [M-4] psig Loop 2 S/G Pressure PI-1-9A or 9B [M-4] psig Loop 3 S/G Pressure PI-1-20Aor 20B [M-4] psig Loop 4 S/G Pressure PI-1-27A or*27B [M-4] psig Loop 1 Feedwater Flow FI-3-35A or 35B [M-4] Ibm/hr Loop 2 Feedwater Flow FI-3-48A or 48B [M-4] Ibm/hr Loop 3 Feedwater Flow FI-3-90A or 90B [M-4] Ibm/hr Loop 4 Feedwater Flow FI-3-1 03A or 103B [M-4] Ibm/hr IV [d] SELECT Calorimetric Main Menu screen on other unit's ICS computer. D [e] SELECT Special Offline Calorimetric on Calorimetric Menu. D (step continued on nextpage)

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 32 of 33 Unit APPENDIX D Date Page 7 of 7 [4] (Continued) [f] ENTER data in ICS "from substeps 4 [b] and 4 [c]. [g] SELECT function key F3 to execute calculation. o [h] PRINT calorimetric results. o [i] VERIFY data from substeps 4 [b] and 4 [c] was correctly entered in ICS. IV U] RECORD Total S/G Thermal Power from calorimetric printout: _ _ _ _MWt [k] CALCULATE percent power corresponding to item Ul _ _ _ _MWt == 34.55

                                                      ------ 0/0 NOTE           The following step adds 3.5% to calorimetric power to compensate for additional errors in this method. The corrected power value below should be used in Section 6.1.

[I] CALCULATE corrected core thermal power: (substep [k]) % + 3.5 % == ___ % [m] VERIFY substeps U] through [I]. IV

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 CHANNEL CALIBRATION BY Rev: 18 1&2 HEAT BALANCE COMPARISON Page 33 of 33 SOURCE NOTES Page 1 of 1 REQUIREMENTS SOURCE IMPLEMENTING STATEMENT DOCUMENT STATEMENT Ensure calculation of thermal INPO SER 89-23 C.1 power is correct before CAQR sao 90052 calibrating excore detectors. Excore detectors should be INPO SER89-09 C.2 calibrated based on best available power indication. NIS *power range calibrations INPO SOER 90-03 C.3 should be performed periodically following power ascension above 15 % power. Careful consideration and INPO SOER90-03 C.4 caution should be exercised before adjusting nuclear instrumentation. Operations and Engineering Management should be notified if larger than normal channel adjustments are required. 0-SI-OPS-092-078.0 will be LER 328/91005 C.5 revised to allow the use of a 810 910819 844 Plant Computer program to provide an increased frequency of the performan'ce of thi"s procedure.

co JPM # 46-1 Page 1 of 13 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g JPM # 46-1 SHUTDOWN THE DIESEL GENERATORS (1A-A & 18-8) PREPARED/ REVISED BY: Date/ VALIDATED BY:

Date/

APPROVED BY: Date/ (Operations Training Manager) CONCURRED: ** Date/ (Operations Representative)

Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.

             ** Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM # 46-1 Page 2 of 13 Rev. 0 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/ NUMBER REVISION AFFECTED REVISED BY: 0 Initial Issue ALL v - Specify if the JPM change will require another validation (Y or N). See cover sheet for criteria.

JPM # 46-1 Page 3 of 13 Rev. 0 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task: Shutdown the Diesel Generators (1 A-A & 18-8) JAiTA task # : 0640060101 (RO) KIA Ratings: 064K1.01 (4.. 1/4.4) 064A1.08 (3.1/3.4) 064A2.04 (2.7/3.0) 064A2.08 (2.5/2.7) 064A2.13 (2.6/2.8) 064A3.03 (3.4/3.3) 064A3.06 (3.3/3.4) 064A4.06 (3.9/3.9) 064A4.01 (4.0/4.3) Task Standard: Diesel Generators "1 A-A" & "18-8" have been shutdown in accordance with EA-82-1. Evaluation Method: Simulator __ X_ _ In-Plant --'""--

=======================================================================

Performer: NAME Start Time -,--_ _ Performance Rating: SAT UNSAT Performance Time Finish Time - - - Evaluator: SIGNATURE DATE

============.===========================================================

COMMENTS

JPM # 46-1 Page 4 of 13 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps identified by an asterisk (*)

2. Sequenced steps identified by an "s"

3. Any UNSAT requires comments

4. Initialize simulator in IC #191.lf IC-191 not available, reset to IC #5 Trip the reactor, use 1-M-1 handswitchto emergency start the diesels generators. Close TDAFW level control valves.

5. When directed to perform section 4.2, set BOTH RF EGR11 and EGR12to TEST and THEN BOTH back to NORMAL* to reset the DIG start signal. Set EGR07 and EGR 08 to RESET to reset the 86LOR for the DGs

6. Acknowledge/reset alarms on all panels.

7. This scenario will require a console operator.

8. Ensure operator performs the following required actions*for SELF-CHECKING;

a. Identifies the correct unit, train, component, etc.

b. Reviews the intended action and expected response.

c. Compares the actual response to the expected response.

Validation Time: CR. 20 mins Local ....,....-- Tools/Equipment/Procedures Needed: EA~82-1 ,

References:

Reference Title Rev No. EA-82-1 DIGs in Standb 2

=============~===============================================================

READ. TO OPERATOR Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handoutsheet I provided you. INITIAL CONDITIONS:

1. The Unit tripped due to an* inadvertent safety injection.

2. The safety injection has been terminated and the plant has been stabilized in MODE 3.

3. The Diesel Generators have been running unloaded for 2 hours and 40 minutes.

4. The status file is complete and there are no outstanding configuration log entries present for the Diesel Generators.

INITIATING CUES:

1. You are the Unit 1 CRO and have been directed to shutdown the Unit 1 Diesel Generators per EA-82-1.

2. The 1A-A DIG is to be shutdown first.

3. All Shutdown Boards are energized by offsite power and the SI signal has been reset.

4. Inform the SM when 1A and 1B DIGs have been shutdown per EA-82-1.

JPM # 46-1 Page 5 of 13 Rev. 0 Job Performance Checklist: STEP/STANDARD SAT/UNSAT STEP 1.: Obtain appropriate copy of procedure. SAT UNSAT STANDARD: Operator obtains a copy of EA-82-1 and procedes to Section 4.1. Start Time__ COMMENTS: STEP 2.: 1. SELECT DIG to be shut down: SAT

DIG 1A-A _ _
DIG 18-8 _ _ UNSAT
DIG 2A-A _ _
DIG 28-B STANDARD: Operator checks 1A-A and 18-B diesel generators being selected.

COMMENTS: STEP 3.: 2. IF EA-202-1 was NOT used to unload the selected DIG, SAT THEN DISPATCH AUO to perform Section 4.2 to reset selectedD/G UNSAT emergency start signal. Critical Step Cue: Role Playas AVO and accept EA-82-1, Section 4.2. Report that you will report to him when complete. Booth Operator: Set BOTH RF EGR11 and EGR12 to TEST and THEN BOTH back NORMAL to reset the DIG start signal. Then, setEGR07 and EGR 08 to RESET Cue: After performing the above~ Role Playas AVO and report EA-82-1, Section 4.2 complete. STANDARD: Operator dispatches AUO with EA-82-1, section 4.2. COMMENTS: STEP 4.: 3. GO TO appropriate section based on table below: SAT UNSAT THEN OlG DIG DIG DIG rF SELECTED DIG 1A-A 18--8 2A-A 2B-B GO to SECTION

                                                                                  ,.J   .l         "t}
                                                     ~ticn4 .. 3~

Unloaded greaterihaR: 2 h~.ffS, Purging: DiG Combustibles. o o o o Section 4~4" Unloaded tess than 2 hours, £nutting C\Q"\vn OlG. o o o o STANDARD: Operator determines that section 4.3 is the appropriate section since the DIG has been running unloaded more than 2 hours. (also checks the 1A-A and 1B-B boxes.) COMMENTS:

JPM # 46-1 Page 60f 13 Rev. 0 Job Performance Checklist: STEP/STANDARD SAT/UNSAT NOTE: The following steps are from section 4.3. SAT STEP 5.: 1. POSITION selected DIG MODE SELECTOR switch to PARALLEL: UNSAT DiG MODE SElECTOR S'wrrCH PARAlLEL*4 HS...S2-1'g Criti'cal Step

                        'lB-B H3-B2-7a              D' 28-8             H5-82-1o:08 STANDARD: Operator places O-HS-82-18, DG 1A-A MODE SELECTOR, to PARALLEL.

COMMENTS: STEP 6.: 2. TURN selected DIG SYNCHRONIZE switch to SYN: SAT rUG SYNCHRONiZE SWITCH UNSAT 1A,-A 1-HS--57-47 t.J 18-9 1-HS-57-14 Critical Step 2A-A .2-HS--57-47 28-9 2-HS-57-14 STANDARD: Operator places O-HS-57-47 DG 1A-A SYNCHRONIZE, to SYN. COMMENTS: STEP 7.: 3. ENSURE selected DIG VOLTAGE REGULATOR switch *in PULL-P- SAT AUTO: UNSAT DiG VOLTAGE REGULATOR PUlL-P-AUTO ~ S'WITCH 1A.-A

H S-8:2 -4 2: D:

2A-A. HS-a-2*~-72: 28-B HS-S2:-1:Q.2 o STANDARD: Operator verifies O-HS-82-12, DG 1A-A VOLTAGE REGULATOR to PULL-P-AUTO. COMMENTS:

JPM # 46-1 Page 7 of 13 Rev. 0 Job Performance Checklist: STEP/STAN DARD SAT/UNSAT STEP 8.: 4. ADJUST running voltage to match incoming voltage USING DIG SAT VOLTAGE REGULATOR switch: UNSAT IN:=eOMI1NG RUNN:IN:G DlG VOLT.AGE MATCHE0 4 VOLTAGE 'VOLTAGE Critical Step E1-82-5 EI-82-35 El-82-e4, o El-82-M EI-82-95; STANDARD: Operator adjusts 0-HS-82-:12, DG 1A-A VOLTAGE REGULATOR, to match voltages on O-EI-82.,.4 and O-EI-82-5. COMMENTS: STEP 9.: 5. ADJUST selected DIG SPEED CONTROL switch UNTIL associated synchroscope rotating slowly in FAST direction: SAT DlG SPEED CONTROL S)'NCHROSCOPE SLOV4'lY [IN FAST UNSAT

                                             ,SWITCH                                  DIRECTIO:N'~:

HS-82..*13 ;<;1-82-1 0; Critical Step 18-8 HS-82-43 X!-82-,31 0

2.A-A 28-8 STANDARD: Operator adjust 0-HS-82-13 until synchroscope O-XI-82-1 is rotating slowly in the fast direction.

COMMENTS: STEP 10.: 6. WHEN synchroscope needle is at 12 o'clock" position, THEN CLOSE selected DIG output breaker: SAT 016 DiG OUTPUT CLOSED *i UNSAT BREA;KER

                                                                       'l-H8-57-46A                    Critical Step XJ-82-31              '1-HS-51-'73A            o 2A-A           Xl-82-e~1             2-HS-57-46A              o 28-B                                 2-HS-57-73,A.            0, STANDARD: Operator places 1-HS-57-46A to the close position when synchroscope O-XI-82-1is at the 12 O'clock position resulting in the closing of the DG electrical breaker as indicated by Red Light LIT above the breaker handswitch.

COMMENTS:

JPM # 46-1 Page 8 of 13 Rev. 0 Job Performance Checklist: ( STEP 11.: STEP/STANDARD

7. ADJUST selected DIG SPEED CONTROL switch to raise DIG MW load SAT/UNSAT to 1.6 MW: SAT DIG UNSAT HS-*8::2-*~*3 Eli-92**'1 OA o Critical Step HS-8-2-43 o LA-.A. HS-a2-7:3 o 28-8 El-B-2-'1 :DOA, o STAND.ARD: Operator intermittently places O-HS-82-13 to RAISE until the MW loading on O-EI-82-1 OAincreases to 1.6 mw.

COMMENTS: STEP 12.: 8. MAINTAIN +1 MVAR (OUT) for selected DIG, WHILE paralleled with offsite power: SAT DlG VOLTAGE UNSAT

D/G REGULATOR S~\IITC:H iDlG M:EG.A.VARS +1 MVAR '1.'

lA-A HS-82-12 o Critical Step 18-8 HS-8242 o HS-82-I2 o 2B-8 £:1-82-1D'l A o STANDARD: Operator places O-HS-82-12 to RAISE to establish the MVAR loading on O-EI-82-11A to +1 MVAR outgoing, then maintains this MVAR loading as the DG is loaded 'by intermittently placing O-HS-82-12 to RAISE. COMMENTS: STEP 13.: 9. DISPATCH an AUO to selected DIG building to monitor stack exhaust WHILE loading selected DIG. SAT Cue: Role Playas AUO acknowledge the direction to monitor theD/G UNSAT 1A-A exhaust stack. STANDARD: Operator dispatches an AUO to the DIG building to monitor DIG 1A-A exhaust. COMMENTS:

JPM # 46-1 Page 9 of 13 Rev. 0 Job Performance Checklist: STEP/STANDARD SAT/UNSAT STEP 14.: 10. LOAD selected DIG to 4.0 MW USING its DIG SPEED CONTROL switch WHILE observing the following guidelines: SAT

a. IF stack exhaust smoke becomes twice as dense as normal during loading, THEN UNSAT STOP DIG loading UNTIL condition clears.

b. WHEN exhaust smoke returns to normal, THEN Critical Step CONTINUE DIG loading.

c. DO NOT CONTINUE this procedure UNTIL the following conditions are met:

DIG load at 4.0 MW AND
Stack exhaust NORMAL.

Cue: When the AUO is asked,*state the exhaust has cleared up and now appears normal. STANDARD: Operator loads the DIG 1A-A to 4.0 MW by intermittently placing O-HS-82-13 to RAISE until theMW loading on 0-EI-82-10A increases to 4.0 mw. COMMENTS: STEP 15.: 11. ADJUST selected DIG SPEED CONTROL switch to lower DIG MW load to 0.5 MW: SAT DiG SPEEDCO:NTROL S*~'ITC*H UNSAT HS-d2-'13 o HS-:E2-43 o Crit.ical Step H5-32-73 o STANDARD: Operator places O-HS-82-13 to LOWER until the MWloading on 0-EI-82-10A reduces to 0.5 mw. COMMENTS: STEP 16.: 12. ADJUST selected DIG VOLTAGE REGULATOR switch to lower DIG MVAR load to zero: SAT

                              ;016      DIG VOLTAGE         .Qj'-G MEGAVARS      0 VAR,!          UNSAT REGULATOR SWITC.H lA-A         H5-82-12                                   o      Critical Step HS-82-42                                   o 2A-A         HS-82-72                E~,"",B2-7tA       D 2B-8        HS-S2-1G2               El~82-*1:Q 1A       o STANDARD: Operator places O-HS-82-12 to LOWER until the MVAR loading on 0-EI-82-11A reduces to o.

COMMENTS:

JPM # 46-1 Page 10 of 13 Rev. 0 Job Performance Checklist: STEP/STAN DARD SAT/UNSAT STEP 17.: 13. PLACE selected DIG output breaker control switch to TRIP: SAT DiG [hfG O:~UTPUT8REAKER

1-iHS-57-46.A. o UNSAT

                            *1B,.;6              '1 ~HS-*5J -13A                    o Critical Step
                           .2A-A                .2-H3-51-46.A.                      o 2**H3-0:1-13.A.                     o STANDARD: Operator places 1-HS 46A to the TRIP position.

COMMENTS: STEP 18.: 14. GO TO Section 4.4 to shut down DIG. SAT STANDARD: Operator goes to section 4.4 to shut down the DIG 1A-A. UNSAT COMMENTS: Evaluator Note: The following steps are from Section 4.4 STEP 19.: 1. VERIFY selected DIG unloaded with output breaker open: SAT DIG DlGOUTPUT BREAKER UNLOADED 8. OUTPUT UNSAT BREA.KER HANDSWITCH BREAKER OPEf4 ~ D 18-8 o 2A-A 1@22 2-HS..*54-45A o 28-8 o STANDARD: Operator verifies DIG 1A-a output breaker open by green light LIT over Handswitch 1-HS-54-46A. C'OMMENT'S: STEP 20.: 2. PLACE selected D/G(s) CONTROL START-STOP switch to STOP: SAT DIG CO:NTROl UNSAT DiG START-S*TOP SY~lTCH: H~S-B2-14 o Critical Step 18-9 o HS~B2-74 u 28-8 u NOTE: Operator may elect to turn the synchroscope on to verify D/G goes to idle speed when HS is placed to stop. ST*ANDARD: Operator places handswitch 0-HS-82~14, on panel 0-M-26, to the STOP. COMMENTS:

JPM # 46-1 Page 11 of 13 Rev. 0 Job Performance Checklist: STEP/STANDARD SAT/UNSAT STEP 21.: 3. WHEN selectedD/G(s) has run at idle speed (400 rpm) for 10 minutes, SAT THEN VERIFY DIG shuts down and speed drops to zero: UNSAT DiG

lA,-A u

o 2B-iB NOTE: Override AN:OVRDN[905] to OFF to clear the 40 RPM running alarm. When alarm clears, CUE: 10 minutes have elapsed Cue: If A-Va notified, play role and state: DIG is now at zero speed. STANDARD: Operator addresses need to monitor this step. They may contact the AUO to have himlher contact the UO when speed is zero. COMMENTS: STEP 22.: 4. ENSURE selected DIG MODE SELECTOR switch in PUSH IN UNIT SAT position: UNSAT OiG

1 A.-~A,. 1-H*S-B2:-1,8

lB-B; :1--HS-82-4:B o

2B~B o STANDARD: Operator places handswitch 1-HS-82-18, on pan~1 0-M-26, to be in PUSH TO UNIT position. COMMENTS: STEP 23.: 5. ENSURE selected DIG SYNCHRONIZE switch is in OFF: SAT DlG* UN"SAT u

1-H*S-57-14 o 2A-A 2-H*S-57-47 o 2-HS-57-74 o STANDARD: Operator places handswitch 1-HS-57-47, on panel 0-M-26, in the OFF position.

COMMENTS:

JPM # 46-1 Page 12 of 13 Rev. 0 J0b Performance Checklist: STEP/STANDARD SAT/UNSAT STEP 24.: 6. WHEN selected D/G(s) have cooled, SAT THEN ENSURE ERCW valves to DIG heat exchangers closed: UNSAT

O/G Critical Step l-HS~67-6SA tA.--A 1-HS.-<67--e=;eA. :0 1- H~57--f!i7~A,. o 1-HS~57-e~5A. =0

0 2-H,S-=B7--67A. :0 LH-B 2-HS-67-e5.A. o Cue: Play role of AUO: I will monitor DIG temperature and ensure DG 1A-A ERCW valves are closed when DIG reaches ambient temp.

STANDARD: Operator addresses need to monitor this step. They may contact the AUO to have himlher monitor DIG temperatures and shut the ERCW valve,1-FCV-67-66, when the DIG is at ambient conditions. -COMMENTS: STEP 25.: 7. GO TO Section 4.1, step in effect. SAT STANDARD: Operator returns to section 4.1 and determines the other DG needs to UNSAT be shutdown. Cue: When candidate returns to section 4.1 to shutdown the*other Diesel Generator, state "We'll stop here. " Stop Time__ COMMENTS: End of JPM

Directions to Trainee: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for thisjob performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. The Unit tripped due to an inadvertent safety injection.

2. The safety injection has been terminated and the plant has been stabilized in MODE 3.

3. The Diesel Generators have been running unloaded for 2 hours and 40 minutes.

4. The status file is complete and there are no outstanding configuration log entries present for the Diesel Generators.

INITIATING CUES:

1. You are the Unit 1 eRa and have been directed to shutdown the Unit 1 Diesel Generators per EA-82-1.

2. The 1A-A DIG is to be shutdown first.

3. All Shutdown Boards are energized by offsite power and the SI signal has been reset.

4. Inform the SM when 1A and 1B D/Gshave been shutdown per EA-82-1.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY ABNORMAL PROCEDURE EA-82-1 PLACING DIGs IN STANDBY Revision 2-QUALITY RELATED PREPARED/PROOFREAD BY:- Marie -Hankins

                                            -~~...;;....;;..;;~~--------

RESPONSIBLE ORGANIZATION: OPERATIONS

                                                    -----..;.~-------

APPROVED BY: ...;;;..;J.~A;.;...;.D=-V..:...;O=-=R...;.:.A...;.:.K~ _ EFFECTIVE DAT-E: 26 May 03 REVISION DESCRIPTION: Revised section 4.4 to add steps to place the Mode Selector switch in PUSH IN UNIT position and turn the Sync Switch to OFF. This is an intent change. Added HS UNID for D/G output breakers in section 4.4 step 1. Added a note in section 4.1 to clarify DIG's have not been returned to TS operability but are place-d ina condition for Auto Restart, if required prior to exiting the EOP's. This is a non-intent change.

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 page 2 of 16 1.0 PURPOSE To shut down unloaded DIGs and place the DIGs in a standby condition. If a DIG has been running unloaded greater than 2 hours, thisEAP will load it to purge combustibles and then unload it and shut it down. 2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 Entry Conditions A. E-O, Reactor Trip or Safety Injection. B. E-1, Loss of Reactor or Secondary Coolant. C. E-3, Steam Generator Tube Rupture. D. ECA-2.1, Uncontrolled Depressurization of All Steam Generators. E. ECA-3.1, SGTR and LOCA - Subcooled Recovery. F. ECA-3.2, SGTR and LOCA - Saturated Recovery. G. ECA-3.3, SGTR Without Pressurizer Pressure Control. H. ES-1.1, 81 Termination. I. ES-1.2, Post LOCA Cooldown and Depressurization. 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions A. If the accountability siren sounds, the operator should continue performing this procedure. The SOS will remain aware of procedure progress and location of performing personnel. 3.2 Limitations A. This EAP does NOT meet all procedural and Technical Specification requirements for returning the DIGs to a full standby condition. This procedure only returns the DIGs to a condition for auto-re*start to ensure availability if needed prior to exiting the EOPs.

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 3 of 16 4.0 OPERATOR ACTIONS 4.1 Section Applicability

1. SELECT DIG to be shut down:

DIG 1A-A
DIG 1B-B
DIG 2A-A
D/G28-8 _ _

NOTE If EA-202-1 was used to unload the selected DIG, then the DIG emergency start signal and the shutdown board blackout relays have already been reset.

2. IF EA-202-1 was NOT used to unload the selected DIG, THEN DISPATCH AUO to perform Section 4.2 to reset selected DIG emergency start signal. D

3. GO TO appropriate section -based on table below:

THEN DIG DIG DIG DIG IF SE-LECTED DIG 1A-A 1B-B 2A-A 28-8 GO TO SECTION

                                                                    ~       ~     ~      ~

Section 4.3, Unloaded greater than 2 hours, Purging DIG Combustibles. D D D D Section 4.4, Unloaded less than 2 hours, Shutting Down DIG. D D D D

SQN EA-82-1 PLACING DIGs IN *STANDBY Rev. 2 1,2 Page 4.of 16 4.1 Section Applicability (Continued)

4. IF another DIG to be shut down, THEN GO TO Step 4.1.1 D NOTE This procedure places the DIG's in a condition for Auto-Restart, if required prior to exiting the EOP's.Restoration to T8 operability and procedural requirements for standby alignment is performed after the EOP's are exited.

5. RETURN TO procedure and step in effect. D END OF SECTION

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 5 of 16 4.2 Resetting DIG Auto Start Signals NOTE Performance of Steps 4.2.1 and 4.2.2 are required the first time this section is performed but their performance is not required on subsequent passes through this section.

1. NOTIFY UO to verify SI reset. D

2. RESET DIG emergency start signals by performing the following:

[6.9 KV shutdown board room]

a. PLACE all DIG [43T(Ll] switches to TEST:

SHUTDOWN BOARD LOGIC SWITCH TEST PANEL ~ 1A-A 43T(L) D 18-8 43T(L) D 2A-A 43T(L) D 28-8 43T(L) D

b. VERIFY emergency start signals RESET by observing amber lights lit SHUTDOWN BOARD LOGIC PANEL AMBER LIGHT LIT

1A-A D 18-8 D 2A-A 0 28-8 D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 6 of 16 4.2 Resetting DIG Auto Start Signals (Continued) C. PLACE 8.11 DIG [43T(L)] switches to NOR: SHUTDOWN BOARD LOGIC PANEL SWITCH NOR

1A-A 43T(L) D 18-8 4~T(L) D 2A-A 43T(L) D 28-8 43T(L) D

3. PERFORM the following:

a. VERIFY DIG [86 LOR] red lights DARK:

DIG RELAY BOARD RED LIGHT DARK

1A-A D 18-8 D 2A-A D 28-8 D

b. PLACE selected DIG [86 LOR] switch to RESET:

DIG RELAY BOARD SWITCH RESET

1A-A 86 LOR D 18-8 86 LOR D 2A-A 86 LOR D 28-8 86 LOR D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 7 of 16 4.2 Resetting DIG Auto Start Signals (Continued)

4. GOTO Section 4.1, step in effect. D END OF SECTION

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1;2 Page 8 of 16 4.3 Purging DIG Combustibles CAUTION Only one diesel shall be operated in parallel with off-site power at any time. NOTE This section purges the DIG of any combustibles accumulated during the unloaded condition prior to shutting down the DIG.

1. POSITION selected DIG MODE SELECTOR switch to PARALLEL:

DIG MODE SELECTOR SWITCH PARALLEL ~ 1A-A HS-82-18 D 18-8 HS-82-48 D 2A-A HS-82-78 D 28-8 HS-82-108 D

2. TURN selected DIG SYNCHRON1ZE switch toSYN:

DIG SYNCHRONIZE SWITCH SYN~ 1A-A 1-HS-57-47 D 18-8 1-HS-57-74 D 2"A-A 2-HS-57-47 D 2"8-8 2-HS-57-74 D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 9 of 16 4.3 Purging DIG Combustibles (Continued)

3. ENSURE selected DIG VOLTAGE REGULATOR switch in PULL-P-AUTO:

DIG VOLTAGE REGULATOR PULL-P-AUTO ~ SWITCH 1A-A HS-82-12 D 18-8 HS-82-42 D 2A-A HS~82-72 D 28-8 HS-82-102 D

4. ADJUST running voltage to match incoming voltage USING DIG VOLTAGE REGULATOR switch:

INCOMING RUNNING DIG VOLTAGE MATCHED ~ VOLTAGE VOLTAGE 1A-A EI-82~4 EI-82-5 D 18-8 EI-82-34 EI-82-35 D 2A-A EI-82-64 EI-82-65 D 2"8-8 EI-82-94" EI-82-95 D

5. ADJUST selected DIG SPEED CONTROL switch UNTIL associated synchroscope rotating slowly in FAST direction:

SPEED CONTROL SLOWLY IN FAST DIG SYNCHROSCOPE SWITCH DIRECTION ~ 1A-A HS-82-13 XI-82-1 D 18-8 HS-82-43 XI-82-31 D 2A-A HS-82-73 XI-82-61 D 28-8 HS-82-103 X"I-82-91 D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 10 of 16 4.3 Purging DIG Combustibles (Continued) NOTE When closing the DIG output breaker at 12 o'clock position, consideration should be given to speed of rotation of synchroscope needle and time it takes to close the breaker.

6. WHEN synchroscope needle is at 12 o'clock" position, THEN CLOSE selected DIG output breaker:

DIG OUTPUT DIG SYNCHROSCOPE CLOSED ~ BREAKER 1A-A XI-82-1 1-HS-57-46A D 18-8 XI-82-31 1-HS-57-73A D 2A-A XI-82-61 2-HS-57 ~46A D 28...8 XI-82-91 2-HS-57-73A D

7. ADJUST selected DIG SPEED.CONTROL switch to raise DIG MW load to 1.6 MW:

SPEED CONTROL DIG SWITCH DIG MEGAWATTS 1.6 MW ~ 1A-A HS-82-13 EI-82-10A D 18-8 HS-82-43 EI-82-40A D 2A-A HS-82-73 EI-82-70A D 28-8 HS-82-103 EI-82-100A D

8. MAINTAIN +1 MVAR (OUT) for selected D/G,WHILE paralleled with offsite power:

DIG VOLTAGE DIG REGULATOR SWITCH DIG MEGAVARS +1 MVAR " 1A-A HS-82-12 EI-82-11A D 18-8 HS-82-42 EI-82~41A D 2A-A HS-82-72 EI-82-71A D 28-8 HS-82-102 EI-82-101A D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 11 of 16 4.3 Purging DIG Combustibles (Continued)

9. DISPATCH an AUO to selected DIG building to monitor stack exhaust WHILE loading selected DIG. D

10. LOAD selected DIG to 4.0 MW USING its DIG SPEED CONTROL switch WHILE observing the following guidelines:

a. IF stack exhaust smoke becomes twice as dense as normal during loading, THEN STOP DIG loading UNTIL condition clears. D

b. WHEN exhaust smoke returns to normal, THEN CONTINUE DIG loading. D C. DO NOT CONTINUE this procedure UNTIL the following conditions are met:

DIG load at 4.0 MW D AND
Stack exhaust NORMAL. D

11. ADJUST selected DIG SPEED CONTROL switch to lower DIG MW load to 0.5 MW:

DIG SPEED CONTROL SWITCH 0.5 MW ~ 1A-A HS-82-13 D 18-8 HS-82-43 D 2A-A HS-82-73 D 28-8 HS-82-103 D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 12 of 16 4.3 Purging DIG Combustibles (Continued)

12. ADJUST selected DIG VOLTAGE REGULATOR switch to lower DIG MVAR load to zero:

DIG VOLTAGE DIG REGULATOR SWITCH DIG MEGAVARS o MVAR" 1A-A HS-82-12 EI-82-11A D 18-8 HS-82-42 EI-82-41A D 2A-A HS-82-72 EI-82-71A D 28-8 HS-82-102 EI-82~1 01A D

13. PLACE selected DIG output breaker control switch to TRIP:

DIG DIG OUTPUT BREAKER TRIPPED" 1A-A 1-HS-57-46A D 18-8 1-HS-57-73A D 2A-A 2-HS-57-46A D 28-8 2-HS-57-73A D

14. GOTO Section 4.4 to shut down DIG. D END OF SECTION

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 13 of 16 4.4 Shutting Down DIG

1. VERIFY selected DIG unloaded with output breaker open:

DIG OUTPUT BREAKER UNLOADED & OUTPUT DIG BREAKER HANDSWITCH BREAKER OPEN ~ 1A-A 1912 1-HS-54-46A D 18-8 1914 1-HS-57-73A D 2A-A 1922 2-HS-54-46A D 28-8 1924 2-HS-57-73A D

2. PLACE selected D/G(s) CONTROL START-STOP switch to STOP:

DIG DIG CONTROL STOP -V START-STOP SWITCH 1A-A HS-82-14 D 18-8 HS-82-44 D 2A-A HS-82-74 D 28-8 HS-82-104 D

3. WHEN selected D/G(s) has run at idle speed (400 rpm) for 10 minutes, THEN VERIFY DIG shuts down and speed drops to zero:

DIG ZERO RPM-v 1A~A D 18-8 D 2A-A D 28-8 D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 14 of 16 4.4 Shutting Down DIG (Continued)

4. ENSURE selected DIG MODE SELECTOR switch in PUSH IN UNIT position:

DIG MODE SELECTOR SWITCH PUSH IN UNIT ~ 1A-A 1-HS-82-18 D 18-8 1-HS-82-48 D 2A-A 2-HS-82-78 D 28-8 2-HS-82-108 D 5". ENSURE selected DIG SYNCHRONIZE switch is in OFF: DIG SYNCHRONIZE SWITCH OFF ~ 1A-A 1-HS-57-47 D 18-8 1-HS-57-74 D 2A-A 2-HS-57-47 D 2B-8 2-HS-57-74 D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 15 of 16 4.4 Shutting Down DIG (Continued)

6. WHEN selected O/G(s) have cooled, THEN ENSURE ERCW valves to DIG heat exchangers closed:

DIG ERCW TO DIG HEAT EXCHANGERS CLOSED ~ 1-HS-67-66A D 1A-A 1-HS-67-68A D 1B~B 1-HS-67-67A D 1-HS-67-65A D 2-HS-67-66A D 2A-A 2-HS-67-68A D 2-HS-67-67A D 2B-B 2-HS-67-65A D

7. GO TO Section 4.1, step in effect. -0 END OF TEXT

SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 16 of 16

5.0 REFERENCES

None.}}

ML080720575: Difference between revisions

Latest revision as of 05:54, 13 March 2020

Text

====="==================================================================

=======================================================================

References:

=======================================================================

=======================================================================

References:

=================================================================

Response

4.0 REFERENCES

SUMMARY

=======================================================================

=======================================================================

References:

=================================================================

2.0 REFERENCES

1.0 INTRODUCTION

2.0 REFERENCES

1.0 INTRODUCTION

2.0 REFERENCES

2.0 REFERENCES

=======================================================================

========.===============================================================

References:

.===========================================================================

1.0 INTRODUCTION

2.0 REFERENCES

1.0 INTRODUCTION

2.0 REFERENCES

========================================================================

========================================================================

References:

=======================================================================

=======================================================================

References:

====================="============================================

1.0 INTRODUCTION

1.0 INTRODUCTION

2.0 REFERENCES

=======================================================================

============.===========================================================

References:

5.0 REFERENCES

Navigation menu

Search