ML091170441

Initial Exam 2009-301 Post Exam Comments

ML091170441
Person / Time
Site:	Harris
Issue date:	03/26/2009
From:	Toler T Progress Energy Carolinas
To:	Widmann M Division of Reactor Safety II
References
50-400/09-301
Download: ML091170441 (19)

Text

March 26, 2009 SERIAL: HNP-09-045 Mr. Malcolm Widmann, Region II United States Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303-8931 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REACTOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATIONS 05000400/2009301

Dear Mr. Widmann:

Enclosed is the post-examination package for the Reactor and Senior Reactor Operator Initial Examinations given at the Harris Nuclear Plant March 9,2009, through March 20,2009.

Included from the administration of the Written Examination are the student cover sheets, answer sheets, master examinations, an answer key, a log of applicant questions and answers, and the student seating chart. Also, pertaining to the SRO Written Examination are two post-examination comments (Question #83 and #87).

For the Operating Examination, there are two post-examination comments. Both comments are for Admin JPM corrections to approved material. The JPM comments are specifically for SROIRO Admin JPM A1-1 and RO Admin JPM A1-2.

If you have any questions regarding this submittal, please contact Mr. Archie Lucky at (919) 362-3386. .

Sincerely,

~7?X--

Terence T. Toler Superintendent - Operations Training Harris Nuclear Plant TTTlmgw Enclosures c: Mr. J. D. Austin (NRC Senior Resident Inspector, HNP) wlo Enclosures Mr. L. A. Reyes (NRC Regional Administrator, Region II) wlo Enclosures Ms. M. G. Vaaler (NRR Project Manager, HNP) wlo Enclosures Progress Energy Carolinas. Inc.

Harris Nuclear Plant POBox 165 New Hill. NC 27562

Harris Nuclear Plant 2009a NRC Written Exam Question Contention On March 23, 2009 the HNP Written Exam was reviewed with all participating candidates. During the review the SRO candidates identified two questions (#83 and #87) that were inconsistent with the answer key. Based on the review ofHarris Plant approved procedures the Harris Training Department supports post exam changes.

Contention: HNP SRO Written Exam (March, 2009) Question #83 has two possible correct answers Given the following plant conditions:

- The plant is operating at 100% power

- The crew has noted indications that an RCS leak is in progress and has entered AOP-016, Excessive Primary Plant Leakage The following alarms and indications are observed:

- Plant Vent Stack #1 WRGM Effluent is alarming at 4.8E4 uCiisec and rising

- Charging Pump IB Room Area Radiation monitor alarming at 1200 times normal and rising

- GFFD is in alarm and has increased by 80,000 CPM over the last 20 minutes

- lRM-ICR-3589-SA, CNMT HI Range Accident Monitor, is alarming at 14.7 Rlhr and rising

- lRM-ICR-3590-SB, CNMT HI Range Accident Monitor, is alarming at 18.4 Rlhr and rising Which ONE of the following is the EAL classification to be declared for this event?

(Reference provided)

A. EAL 2-1-1 B. EAL2-1-2 C. EAL 2-1-3 D. EAL 2-1-4 Plausibility and Answer Analysis A. Incorrect. Plausible since the conditions for this classification have been met by the increase in GFFD, but this is not the most limiting EAL.

B. Incorrect. Plausible since the conditions for this classification have been met due to the Table 2 area rad monitor reading> 1200 times normal, but this is not the most limiting EAL.

C. Correct. Multiple radiation alarms require evaluating Cnmt Hi Range Accident Monitors. With one above the setpoint the correct classification is to identify two fission product barriers breached D. Incorrect. Plausible since it is possible to reach a General Emergency based solely on Plant Vent Stack WRGM, but the thresholdfor this classification has not yet been reached KIA statement - ARM System Alarms - Knowledge of the emergency action level thresholds and classifications.

Importance Rating: 3.9 4.1 Technical

Reference:

Side 1 and Side 2 ofEAL Flow Path Rev. 06-1 References to be provided: Side 1 and Side 2 ofEAL Flow Path Rev. 06-1 1

Harris Nuclear Plant 2009a NRC Written Exam Question Contention Question #83 Basis/or Contention: Both Answers 'C' and 'D' are correct because insufficient information is provided in the stem of the question to adequately differentiate between the two answers.

The first decision block of importance on the PEP-II 0 Emergency Action Level Flow Path Side 1 (Revision 06-1) is "EITHER CNMT HI RANGE ACCIDENT MON > 17.5 R/HR". Using information from the stem (IRM-ICR-3590-SB, CNMT HI Range Accident Monitor, is alarming at 18.4 RIhr and rising) this is given a YES response. This YES response leads to "INDICATE FUEL AND RCS BREACHED ON FPB STATUS BOARD". With the determination that both the Fuel and RCS FPB are breached, at a minimum a Site Area Emergency exists (EAL 2-1-3) and therefore, answers 'A' and 'B' are incorrect.

The second decision block of importance on the PEP-II 0 Emergency Action Level Flow Path Side 1 (Revision 06-1) is "BOTH FUEL AND RCS INTACT ON FPB STATUS BOARD". This decision block is given a NO response as result of the previous discussion. This NO response then requires evaluation of the "PATHWAY FOR FISSION PRODUCTS TO ESCAPE CNMT EXISTS OTHER THAN SECONDARY SYSTEMS (STEAMlFEED)" decision block. Given the detail provided in the stem, a YES or NO determination for this decision block becomes subject to interpretation.

The conditions given in the stem are a snapshot in time with no allowance for how long the trend existed or what the trend will be a time progresses. It is this short fall that results in both Answers 'C' and 'D' being correct.

Justification for a NO Response (Answer C, 2FPBs BREACHED/JEOPARDIZED): With Containment radiation at the levels indicated in the stem, it is inferred that a Containment Ventilation Isolation Signal has occurred. Because no indication of component failure is provided in the stem, it can be presumed that the valves are properly positioned and that a pathway does NOT exist for Fission Products to escape Containment. This would result in indicating Containment INTACT on the FPB Status Board and arriving at EAL 2-1-3, 2FPBs BREACHED/JEOPARDIZED (Keyed Answer 'C').

Justification for a YES Response (Answer D, 3FPBs BREACHED/JEOPARDIZED): With Containment radiation at the levels indicated in the stem it is inferred that a Containment Ventilation Isolation Signal has occurred. Given that the Plant Vent Stack # 1 WRGM Effluent is alarming at 4.8E4 uCiisec and is rising a reasonable interpretation can be made that a pathway does exist for Fission Products to escape Containment. This pathway could be through a mispositioned component or an RCS leak outside of Containment. Containment Normal Purge discharges to the Plant Vent Stack and with these levels still increasing, some sort of discharge is being direct to the Plant Vent Stack. The information provided in the question stem only gave one fuel breach area radiation monitor vice multiple monitors that would have been in alarm. This led at least one candidate to assume the other radiation monitors were normal and therefore a leak was likely in the Charging pump room. This would result in indicating Containment Breached on the FPB Status Board and arriving at EAL 2-1-4, 3FPBs BREACHED/JEOPARDIZED (Answer 'D').

The recommendation from Harris Nuclear Plant is to accept two answers ('C' and 'D') for this question based upon NUREG 1021 ES-403 D.1.b page 3 guidance. This question was written with an unclear stem that did not provide all the necessary information to distinguish between answers 'c' and 'D'.

2

Harris Nuclear Plant 2009a NRC Written Exam Question Contention Contention: HNP SRO Written Exam (March, 2009) Question #87 has NO correct answer Given the following plant conditions:

- The plant is operating at lOO% power

- Reactor Engineering is performing a flux map

- OWP-RP-02 is in place for PT-456, Pressurizer Pressure Channel II, due to a failed bistable Repair of PT-456 will not be completed for another 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> I&C reports the following:

- Due to errors in the MST during the last performance, the bistables for N-43 are set higher than the allowable values of Technical Specifications

- N-43 repairs will take 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Which ONE of the following describes the action that must be completed for these conditions in accordance with OWP-RP and Technical Specifications?

A. Bypass N-43 until repairs are completed on PT-456 B. Stabilize power at less than 75% within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. Trip the bistables for N-43 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> D. Place the plant in Mode 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> Plausibility and Answer Analysis A. Incorrect. This is plausible because Action 2.b. says the inoperable channel may be bypassed but this is only for surveillance testing and is only allowedfor up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

B. Incorrect. This is plausible because Action 2.c requires power to be reduced to 75% within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or perform QPTR (flux map) every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Flux map is in progress and can continue.

C. Incorrect. This is plausible because Action 2.a requires tripping bistables but precautions of OWP require checking bistables when taking instruments out of service to preclude a plant trip.

D. Correct. Because taking the instrument out of service will produce a plant trip, Action 2.a cannot be performed 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ofAction 2. a and 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of r.s. 3. 0.3 is a total of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

KIA statement - Reactor Protection - Ability to (a) predict the impacts ofthe following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Faulty bistable operation Importance Rating: 3.1 3.6 Technical

Reference:

OWP-RP Rev. 15, pages 96-99, Tech Spec 3.3.1 pg 3/4 3-2, 3/4 3-6 & 7 (pages 150, 154, and 155), Tech Spec 3.0.3 pg 3/40-1 (page 103)

References to be provided: None 3

Harris Nuclear Plant 2009a NRC Written Exam Question Contention Question 87 Basis/or Contention: The question stem states that "the bistables" for NI-43 are set too high. This would require the improperly set bistables to be declared inoperable. All Power Range NIS bistables are listed in Tech Spec Table 3.3-1 (page 3/4 3-2) Reactor Trip System Instrumentation, under functional units 2, 3, and 4. All of these bistables are covered by Action statement #2 (applicable in Modes 1 and 2).

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> In order to comply with this Tech Spec either the inoperable bistables must be tripped within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or the plant must be placed in a Mode that the spec is not applicable within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (Mode 3). Since action must be taken within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, answer D is incorrect because it would allow the plant to remain in Mode 1 for up to 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Answer C is still incorrect. Although it complies with the correct Tech Spec time for bistables to be tripped since the stem referred to "the bistables" and did not specify any specific bistable, it also requires the channel III OTLlT bistables to be tripped. This would result in a plant trip since the channel II OTLlT bistables were previously tripped. Precautions in the OWP require ensuring previously tripped bistables will not make up a Reactor trip coincidence prior to tripping the bistables for the current inoperable instrument channel.

If the actions on Answer D were taken then Tech Specs would be violated. If Answer C actions were taken then the OWP-RP would be violated and a resultant plant trip. Therefore, neither action could be done to comply with both Tech Specs and OWP-RP.

The recommendation from Harris Nuclear Plant is to remove the question from the exam due to no correct answer based upon NUREG 1021 ES-403 D.1.b page 3 guidance. There is technical information that supports a change in the answer key.

4

TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTI ONAl UN IT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. Manual Reactor Trip 2 1 2 1 2 1 2 1 2 31 ,4", 5" 9 4 2 3 4 2 3 5.

• *lIux e

Intermediate Range, Neutron Flux 4

4 2

2 2

1 3

3 2

.B 1###,

. 2

./

3

6. Source Range, Neutron Flux 8.

a. Startup

b. Shutdown

~~

Overpower ~T 2

2 3

3 1

1 2

2 2

2 2

2 2##

3, 4, 5 111'1.

1, 2

.. 4 5

6

9. Pressurizer Pressure--Low (Above P-7) 3 2 2 1 6(1)

10. Pressurizer Pressure--High 3 2 2 1, 2 6

11. Pressurizer Water Level--High 3 2 2 1 6 (Above P-7)

SHEARON HARRIS - UNIT 1 3/4 3-2 Amendment No. 84

TABLE 3.3-1 (Continued)

TABLE NOTATIONS

'When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.

"Whenever Reactor Trip Breakers are to be tested.

1. 1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. 1. Below the P-IO (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(l)The applicable MODES for these channels noted in Table 3.3-3 are more restrictive and, therefore, applicable.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

{~tl~~~JfIl~~;r - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

b. The Minimum Channels OPERABLE requirement is met:

however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1, and

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s: or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.

SHEARON HARRIS - UNIT 1 3/4 3-6 Amendment No. 101

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

-=

ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and

b. Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10%-of RAT~D THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.

ACTION 5 - a. With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inopet~

able channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor Trip SYltem breakers, and verify compliance with the shutdown margin requirements of Specification 3.1.1.2 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

b. With no channels OPERABLE, open the Reactor Trip System breakers within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and suspend all operations involving positive reactivity changes: Verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.2 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

- With the number of OPERABLE chann'els one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 - With less than the Minimum Humber of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

SHEARON HARRIS - UNIT 1 3/4 3-7 Amendment No. 15

OWP-RP-02 Sheet 1 of 7 EIR Number:

W/O Number:

1. OWP - ::.:R:.::P_-..=0.=2_ _ __ Clearance Number:

2. System: Reactor Protection

3. Component: PRESSURIZER PRESSURE

4. Scope: LCO action required due to inoperable Pressurizer Pressure protection channel I (PI-01RC-0455), II (PI-01RC-0456),

or III (PI-01RC-0457)

5. Applicable Requirements: 3.3.1 (Modes 1 and 2)/ 3.3.2 (Modes 1, 2 and 3) and 3.3.3.S.a (Modes 1, 2, and 3) 6.

existing plant conditions permissive annunciator window.

7. Component lineups completed per attached /

sheet{s) . Signature Date

8. Testing required on redundant equipment while the component is inoperable. N_o_n_e_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___

9. Testing/Action required to restore operability. (N/A if tracked on EIR)

MST-IOl19 for Chan I /

MST-I0120 for Chan II /

MST-I0121 for Chan III /

Channel Check /

Signature Date

10. Component lineups restored per attached /

sheet{s) . Signature Date

11. Remarks:

_ _ _ _ _ _ _ _ _--'-'.;;c._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

12. Reviewed By:

Superintendent - Shift Operations Date After receiving the fim~l review signature, *this OWP becomes a QA RECORD and should be submitted to Document Sf~i::vices.

Rev. 15 Page 12 of 1041 I

OWP-RP-02 Sheet 2 of 7 Bistable/Status Light Lineup position for Restored Component ID Inoperability position or Number Initial/Verified Initial/Verified PRESSURIZER PRESS CHANNEL I (PI-455)

NOTE: Master Test Switches may be positioned to TEST for troubleshooting. They are not required to be in TEST to meet Tech Specs:.: Operating these switches before operating the bistable switches aids in troubleshooting by maintaining system conditions the same as they were when the trouble occurred.

Concurrent verification is preferred while tripping bistables.

In PIC 17 on Card C17-836:

SW5 (PS/455H) Master Test Switch for PS/455F TEST _ _ / _ _ NORMAL /

In PIC 17 on Card C17-844:

BS1 (PS/455F1) Master Test Switch for PS/455 TEST / NORMAL -_/_-

In PIC 1 on Card Cl-844:

BSl (PB/455D PRZ Low Press SI) TEST / NORMAL /

BS2 lPB/455B PRZ Press Intlk P-11) TEST / NORMAL /

BS3 (PB/455A PRZ High Press RX Trip) TEST / NORMAL /

BS4 (PB/455C PRZ Low Press RX Trip) TEST / NORMAL /

In PIC 1 on Card Cl-822:

TEST _ _ / _ _ NORMAL -_/_-

TEST / NORMAL /

On Recorder Panel:

TS-412Z TR-412 Selector LOOP A, Switch (circle position LOOP B, OR LOOP B, OR selected) LOOP C / LOOP C -_/_-

IOWP-RP Rev. 15 Page 13 of 104 I

OWP-RP-02 Sheet 3 of 7 Bistable/Status Light Lineup position for Restored Component ID Inoperability position or Number Initial/Verified Initial/Verified PRESSURIZER PRESS CHANNEL I (PI-455) (continued)

On TSLB-3:

(Check the following)

TRIP PRZ HI PRESS PB455A (Window 14-1) ENERGIZED _____ / _____ DE-ENERGIZED /

• Circle appropriate status. Should be energized if > P-11, DE-ENERGIZED if < P-11.

P11 PRZ HI PRESS PB455B

• ENERGIZED/

(Window 14-2) ENERGIZED _____ / _____ DE-ENERGIZED /

TRIP PRZ LO PRESS PB455C (Window 14-3) ENERGIZED / DE-ENERGIZED /

SI PRZ LO PRESS PB455D (Window 14-4) ENERGIZED / DE-ENERGIZED /

A TRIP O/TEMP ~T TB412C1 (Window 7 -1) ENERGIZED _____ / _____ DE-ENERGIZED - _ / _ -

A RUNBK O/TEMP ~T TB412C2 (Window 7-3) ENERGIZED _____ / _____ DE-ENERGIZED /

~~P-RP Rev. 15 Page 14 of 1041

OWP-RP-02 Sheet 4 of 7 Bistable/Status Light Lineup position for Restored Component ID Inoperabili ty position or Number Initial/Verified Initial/Verified PRESSURIZER PRESS CHANNEL II (PI-456)

NOTE: The Master Test Switch may be positioned to TEST for troubleshooting. It is not required to be in TEST to meet Tech Specs. Operating this switch before operating the bistable switches aids in troubleshooting by maintaining system conditions the same as they were when the trouble occurred.

Concurrent verification is preferred while tripping bistables.

In PIC 2 on Card C2-862:

SW7 (PS/456F) Master Test Switch for PS/456 TEST _ _ / _ _ NORMAL /

In PIC 2 on Card C2-844:

BSl (PB/456D PRZ Low Press SI) TEST / NORMAL /

BS2 (PB/456B PRZ Press Intlk P-11) TEST / NORMAL /

BS3 (PB/456A PRZ High Press RX Trip) TEST I NORMAL /

BS4 (PB/456C PRZLow Press RX Trip) TEST / NORMAL /

In PIC 2 on Card C2-822:

BS3 (TB/422C1 OT~T RX Trip) TEST _____ / _____ NORMAL -_/_-

BS4 (TB/422C2 OT~T C-3) TEST / NORMAL /

On Recorder Panel:

TS-412Z TR-412 Selector LOOP A, Switch (circle position LOOP A, OR LOOP B, OR selected) LOOP C _ _ / _ _ LOOP C -_/_-

IOWP-RP Rev. 15 Page 15 of 1041 1

OWP-RP-02 Sheet 5 of 7 Bistable/Status Light Lineup position for Restored Component ID Inoperability position or Number Initial/Verified Initial/Verified PRESSURIZER PRESS CHANNEL II (PI-456) (continued)

On TSLB-3:

(Check the following)

TRIP PRZ HI PRESS PB45~~

(Window 15-1) ENERGIZED / DE-ENERGIZED /

• Circle appropriate status. Should be energized if > P-ll, DE-ENERGIZED if < P-l1.

Pll PRZ HI PRESS PB456B

• ENERGIZED/

(Window 15-2) ENERGIZED / DE-ENERGIZED /

TRIP PRZ LO PRESS PB456C (Window 15-3) ENERGIZED _____ / _____ DE-ENERGIZED /

SI PRZ LO PRESS PB456D (Window 15-4) ENERGIZED / DE-ENERGIZED - _ / _ -

B TRIP O/TEMP ~T TB422Cl (Window 8-1) ENERGIZED / DE-ENERGIZED /

B Rl~TBK O/TEMP ~T TB422:2 (Window 8 - 3 ) ENERGIZED _____ / _____ DE-ENERGIZED /

" (

[OWP-RP Rev. 15 Page 16 of 1041

OWP-RP-02 Sheet 6 of 7 Bistable/Status Light Lineup position for Restored Component ID Inoperability position or Number Initial/Verified Initial/Verified PRESSURIZER PRESS CHANNEL III (PI-457)

NOTE: The Master Test Switch may be positioned to TEST for troubleshooting. It is not required to be in TEST to meet Tech Specs. Operating this switch before operating the bistable switches aids in troubleshooting by maintaining system conditions the same as they were when the trouble occurred.

Concurrent verification is preferred while tripping bistables.

In PIC 3 on Card C3-863:

SW2 (PS/457E) Master Test Switch for PS/457 TEST / NORMAL /

In PIC 3 on Card C3-834:

BSI (PB/457D PRZ Low Press SI) TEST / NORMAL -_/_-

BS2 (PB/457B PRZ Press Intlk P-ll) TEST _ _ / _ _ NORMAL /

BS3 (PB/457A PRZ High Press RX Trip) TEST / NORMAL -_/_-

BS4 (PB/457C PRZ Low Press RX Trip) TEST / NORMAL -_/_-

In PIC 3 on Card C3-822:

BS3 (TB/432Cl OT~T RX Trip) TEST _ _ / _ _ NORMAL -_/_-

BS4 (TB/432C2 OT~T C-3) TEST / NORMAL /

On Recorder Panel:

TS-412Z TR-412 Selecto~ LOOP AI Switch (circle position LOOP AI OR LOOP BI OR selected) LOOP B / LOOP C /

IOWP-RP Rev. 15 Page 17 of 1041

OWP-RP-02 Sheet 7 of 7 Bistable/Status Light Lineup position for Restored Component ID Inoperability position or Number Initial/Verified Initial/Verified PRESSURIZER PRESS CHANNEL III (PI-457) (continued)

On TSLB-3:

(Check the following)

TRIP PRZ HI PRESS PB457A (Window 16-1) ENERGIZED / DE-ENERGIZED /

• Circle appropriate status. Should be energized if > P-11, DE-ENERGIZED if < P-11.

P11 PRZ HI PRESS PB457B

• ENERGIZED/

(Window 16-2) ENERGIZED _____ / _____ DE-ENERGIZED _____ / _____

TRIP PRZ LO PRESS PB457C (Window 16-3) ENERGIZED / DE-ENERGIZED /

SI PRZ LO PRESS PB457D (Window 16-4) ENERGIZED / DE-ENERGIZED /

C TRIP O/TEMP ~T TB432Cl (Window 9-1) ENERGIZED _____ / _____ DE-ENERGIZED - _ / _ -

C RUNBK O/TEMP ~T TB432C2 (Window 9 - 3) ENERGIZED _____ / _____ DE-ENERGIZED - _ / _ -

IOWP-RP Rev. 15 Page 18 of 1041

OWP-RP-2S Sheet 1 of 4 EIR Number:

W/O Number:

1. OWP - ~R~P_-~2~S_______ Clearance Number:

2. System: Nuclear Instrumentation

3. Component: POWER RANGE N-43

4. Scope: LCO action required due to inoperable Channel 3 Power Range Nuclear Instrumentation

5. Applicable Requirements: 3.3.1 (Modes 1 and 2), 4.2.1.1 and 4.2.4.2 (Mode 1 above 50% RATED THERMAL POWER)

6. Precautions: 1) EnsU:rce Qnlyo:p.e chann~l 01lt o*f lServ:i,ce at Cj. t:i,me. <

2) This procedure does not alter the input to the :£:>-8 or P-10 permissives.

7. Component lineups** completed per attached /

sheet (s) . Signature Date

8. Testing required on redundant equipment while the component is inoperable. Perform EST-91S once per 12 hrs if Rx power is greater than 75% with one Channel inoperable. Perform OST-1039 once per 12 hrs if Rx power is greater than 50%.

9. Testing/Action required to restore operability. (N/A if tracked on EIR)

OST-1021, 1022 or 1033 /

OST-1004 /

OST-1039 (above 50% RTP) /

MST-I0046 /

Signature Date

10. Component lineups restored per attached /

sheet (s) . Signature Date

11. Remarks:

12. Reviewed By:

Superintendent - Shift Operations Date After receiving the final review signature, this OWP becomes a QA RECORD and should be submitted to Document Services.

OVVP-RP Rev. 15 Page 96 of 1041

OWP-RP-25 Sheet 2 of 4 Bistable/Status Light Lineup position for Restored Inoperabili ty position Component ID or Number Initial/Verified Initial/Verified NOTE: This OWP must be performed in order to prevent possible spurious rod motion or level control swings.

On MAIN CONTROL BOARD:

ROD BANK SELECTOR Switch MANUAL _____1_____ MANUAL _ _1 _ -

FW Reg Byp Valve Controllers:

FK-479.1 MANUAL _ _I _ - MANUAL _ _1 _ -

FK-489.1 MANUAL _ _I _ - MANUAL _ _I _ -

- - - - -I - - - - I FK-499.1 MANUAL MANUAL In PIC 3 on Card C3-822:

NOTE: Concurrent verification is preferred while tripping bistables.

TEST I NORMAL _ _1 _ -

TEST I NORMAL _ _1_-

On DETECTOR CURRENT COMPARATOR Drawer:

UPPER SECTION Switch PRN43 I NORMAL _ _I _ -

LOWER SECTION Switch PRN43 I NORMAL I On MISCELLANEOUS CONTROL AND INDICATION PANEL:

ROD STOP BYPASS Switch BYPASS PR N43

---

I - - - - - OPERATE _ _1 _ -

PONER MISMATCH BYPASS BYPASS Switch PR N43 I OPERATE I On COMPARATOR AND RATE Drawer:

CO~IPARATOR CHANNEL DEFEAT Switch N43 _ _1__ NORMAL _ _1 _ -

On Power Range Drawer N43A NOTE: The purpose of the sign installed below is to alert personnel of tripped bistables that may not be obvious at the NI drawer. The wording in quotations is the recommended wording, but similar words may also be used.

Sign stating "Bistables Tripped - OWP-RP in Affect" Installed I Removed _ _1 _ -

IOWP-RP Rev. 15 Page 97 of 104/

OWP-RP-25 Sheet 3 of 4 Bistable/Status Light Lineup position for Restored Inoperabi l i ty position Component ID or Number Initial/Verified Initial/Verified In POWER RANGE N43:

NOTE: Concurrent .verification is preferred in the following Step.

DISCONNECTED / CONNECTED -_/_-

(On completion of the above lineup, check the following.)

On TSLB-3:

C TRIP O/TEMP ~T ENERGIZED / DE-ENERGIZED /

TB432C1 (Window 9-1)

C RUN BK O/TEMP ~T ENERGIZED / DE-ENERGIZED _____ / _____

TB432C2 (Window 9-3)

On TSLB-4:

• Circle required state as determined by present plant conditions.

PR LO PWR HI FLUX NC 43P *ENERGIZED OR (Window 5-3) ENERGIZED / DE-ENERGIZED _____ / _____

PR HI PWR HI FLUX NC 43R (Window 6-3) ENERGIZED -_/_- DE-ENERGIZED /

• • May require manual reset of rate trips locally at drawer.

PR HI FLUX RATE NC 43U/K **

(Window 7-3) ENERGIZED / DE-ENERGIZED _ _ / _ _

On BYPASS PERMISSIVE LIGHTS Panel:

PR OVERPWR ROD WTHDRWL BLK BYPASS CHAN III (Window 3-7) ENERGIZED -_/_- DE-ENERGIZED /

OWP-RP Rev. 15 Page 98 of 1041

OWP-RP-25 Sheet 4 of 4 Bistable/Status Light Lineup position for Restored Inoperability position Component ID or Number Initial/Verified Initial/Verified On ERFIS Computer:

(After status lights have been checked, perform the following using the DR function. )

ANM0122M - PWR RNG DELETED FROM RESTORED TO CHANNEL N43 QI I-MIN AVG PROCESSING / PROCESSING /

On MAIN CONTROL BOARD:

+ Circle appropriate position as determined by plant conditions.

ROD BANK SELECTOR Switch MAN/AUTO + / MAN/AUTO + /

FW Reg Byp Valve Controllers:

+ Circle appropriate position as determined by plant conditions.

FK-479.I MAN/AUTO + / MAN/AUTO + /

FK-489.I MAN/AUTO + / MAN/AUTO + /

FK-499.I MAN/AUTO + / MAN/AUTO + /

OVVP-RP Rev. 15 Page 99 of 1041