ML20081J936

Procedure GP-18, Scram Review Procedure

ML20081J936
Person / Time
Site:	Peach Bottom
Issue date:	10/14/1983
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20081J933	List: ML20081J928 ML20081J936
References
GL-83-28, GP-18, NUDOCS 8311090211
Download: ML20081J936 (38)

Text

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JIc81jm AA M//YO3 Bumtr 1 ADELPHIA ELECTRIC COMPANY t

DEACH BOITG1 UNITS 2 AND 3 GP SCRAM REVIEW PBOCEDURE ,

PURPOSE:

The purpose of this procedure is to ensure that all reactor scrams

- are analyzed and that a determination is made that the plant can be safely restarted. (

REFERENCES:

1. NRC Generic letter 83-28

2. Prints listed in individual sections of GP-18 C.O.L. l

3. Letter on Upset Report Guidance, J. E. Winzenried to STA's,1/8/81.

PREREQUISI'IES:

1. Scram condition, automatic or manual.

PROCEDURE:

1. As soon as the plant conditions permit, Shif t Suoervision shall r initiate GP-18 C.O.L. This C.O.L. is to be filed out by a member of Shif t Supervision or the STA.

2. The STA shall review the ccrnpleted C.O.L. and using the information contained therein, and through interviews with involved personnel shall compile an Upset Report. This report should contain applicable recorder traces and copies of the Sequence Event Im and Post Trip Io3s from the process ccrnputer. See letter from J. E. Winzenried to STA's, January 8, 1981, for further details.

3. The Upset Report shall be written and reviewed by the Engineer-Technical in an expiditious manner and a copy of the report filed in the station files. Other copies of the recort will be distributed to licensed and other personnel as felt aoplicable by station management.

4. The Operations Engineer or alternate shall review the GP-18 C.O.L. .

for completeness and content to ensure there are no unresolved or  !

unexplained conditions. He shall sign the reviewed bv line at the end of the C.O.L. and indicate if POPC review is required. PORC review shall be required if any of the beim conditions exist.

8311090211 831104 PDR ADOCK 0500027]

P

• ' GP-18 Fage 2 of 4, Rev. 2 I

a. Undetermined cause & scram k b. Unexplained or unidentified action of events

c. Failure of ECCS to properly ooerate

d. Failure of all control rods to fully insert

e. Failure of RPS, PCIS or other systems subject to LSSS to operate as required

f. Any other significant event as determined by the Operations Engineer

5. If the Operations Engineer indicates no PORC review required, his signature en GP-18 completes the C.O.L. for ourposes of GP-2.

(GP-2 requires GP-18 to be completed and plant superintendent permission to start up).

6. If PORC review is indicated, the PORC shall review the event to determine if O&SR review is required or to determine what actions must be taken prior to start up. O&SR shall review the event prior to start up if the event was different from those evaluated in the S.A.R. or as required by the PORC.

7. If no O&SR review is required, indication of PORC review in the C.O.L. and completion of actions required by PORC cmstitutes completion of GP-18 C.O.L.

8. If O&SR review is required, indication of O&SR review in the C.O.L. and completion of O&SR and PORC items must be completed 4 to constitute a completed C.O.L. for start up.

l

" GP-18 Paqa 3 of 4, Rev. 2 i

COMPtJIER AIDS TO TRANSIENT ANALYSIS

(

To assist in transient analysis, the computer provides two programs which can help in rebuilding the transient. These programs are: 1) Sequence of Events Log and 2) Demand Log - Post Trip (Data Recall) Ing.

SEGENCE OF EVENTS LOG The Sequence of Events Log logs the digital occurrances during the transient, i.e., Trip signals, breakers open/close, etc. This log is broken down into two separate parts, the NSSS coints and the BOP points.

The NSSS portion will record the first 80 changes of state from the NSSS points accurately; whereas the BOP portion will only record the first 30 changes of state from the BOP points accurately. After the 80 points for NSSS and the 30 points for BOP the computer will re-scan all the sequence of events points, up to 17( , once the comouter has cleared its memory. On this re-scan, the cmputer will note which sequence of events points changed state from the last scan and print these coints with the corresponding re-scan time, not the actual change of state time.

'Ihis log is not demandable from the operators or engineers console but is i autmatically initiated under certain trip conditions.

DD4AND IDG - POST TRIP (DATA RECALL) IDG The Post Trip Log trends up to 40 analog points once a minute over a 40 minute period. At any given mment, the ccraputer holds the previous 20 minute values in memory. Once the Post Trip Iog is initiated, it retains the past 20 minutes of memory in a special output table and continues to store the next 20 minutes of data. At the end of this 20 minute ceriod, (20 minutes after Post Trip Log initiated) the 40 minutes of data will be printed on the CD typer. A list of the current Post Trip Data Points is attached.

The Post Trip Iog is initiated following certain designated plant trips or on demand from the operators console. It is demanded by number 55 option 11 from the operators console and will print out acoroximately 20 minutes later on the CD typer. The Post Trip Iog will be lost in the event the computer goes down before the Post Trip Iog is printed.

It could be advantageous to demand the Post Trip Log from the ooerators console under certain plant condition to help in evaluating the event. An example of this would be the resin injection on Aaril 7,1981, under this condition the automatic initiation of the Post Trio tog does not occur.

_.y. ,.- .. . ,. ..

• GP-18

, .'. Paga 4 of 4, Rev. 2 POST TRIP DATA LOG B000 APRM Ch A Pwr B001 APRM Ch C Pwr B025 Rtr Water Level "H2O B013 Rtr Press PSIG B014 Rtr Core Diff Press Psi B015 Jet Punp Flw M#/Hr B029 W Inlet to Rtr Al Degf B031 W Inlet to Rtr B1 Degf B018 PEP Disch A M#/Hr B019 IFP Disch B M#/Hr B020 RFP Disch C M#/Hr B026 Rtr Out Steam Flw M#/Hr B033 Recirc Al Drive Fl w M#/Hr E046 500 KV Bus Voltage G009 Gen Voltage KV G029 Gross Generator MW G032 Gen Reactive Pwer Mvar G030 Field Current Amps G000 Gen H2 Press Psig G001 Stator Clg Outlet Degf T051 Turb Hyd Fluid Press Psig F082 N Disch A2 GPM P083 W Disch B2 GPM F084 W Disch C2 GPM F119 Cond Pp Disch Hdr Press Psig t B035 Recirc A2 Drive Flw M9/Hr 14 Spares O

. i e

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- - Page 1 of lu, nuv. J .

JLCselc

/ 3 ILADELPilIA ELICfRIC cot 4PANY BBERIT 2 EACH IDP1U4 UNITS 2 AND 3 l

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'6.'O .E.Gis218 SC1tNTTEVIIM PlOCEDUIE UNIT DATE .

TIME INITIAPING EVENT SIDRT DIECRIPTION OF INITIATING EVENP Manual (

Automatic INITIAL CDNDITIONS Ibc Pwr  %

Gen Load Mde Recirc Speed A %B  %

RFP's On A B C Cond Pps On A B C

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Circ Pps On A B C NOTES

1) This C.O.L. is divided into several sections to alloa verification of proper operation of RPS, PCIS, DCCS, and 4KV and 13KV electrical systems.

2) When this procedure is in use, the following may also be required.

A) Notification of Plant Staff (Name)

B) A-31 Notification to NRC Yes No C) EP-101 Classification Notification Made Unusual Event

.. Alert .

Site Emergency

. General Emergency None of the Above D) Trip Procedures

3) obtain the post trip data log, which is printed out

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C.O.L. GP-18 Page 2 of 16, Rev. 3 ,

20 minutes af ter the event (on O.D. typer) for use in anC.yzing the event. The post trip data log records selected parameters each minute for 20 minutes before

{ and 20 minutes after a reactor scram or turbine trip.

4)' If any discrepancies are noted from expected auto actions, indicate these in Section VIII.

PART I RPS

1) From the computer printout and annunciators, verify the following:

COMP NNUNCIA'IOR A) Manual Scram A Trip B) Manual Scram B Trip C) Mode Switch in S/D D) CRD Vol Hi Level A Channel B Channel C Channel D Channel

2) Verify the following:

A) All rods full in B) All 8 RPS rod GPS white lights out C) Scram disch vol isolated Inboard Outboard

3) Was the scram initiated manually?

Yes , verify no auto scram signals occurred j before the manual scram signal. Go to Part II.

No , (auto scram) continue with Step 4 of this section.

4). From the computer printout and annunciators, verify the following:

024P MNUNCIA'IOR A) Auto Scram A Trip B) Auto Scram B Trip

__. 5) From the computer printout, determine the scram ,

initiating signal.

Scram Initiated By A) Channel A B) Channel B C) Channel C

C.O.L. GP-18 Page 3 of 16, Rev. 3 -

D) Channel D

6) List other scram signals that occurred (use reverse

( side if more room is needed).

A) C)

Channel A Channel A B B C C D D B)

Channel A B

C D

7) Briefly describe the cause of the scram.

8) Proceed to Part II.

REFERET.ES RPS Logic M-1-5-54 l

l PART II PCIS GP I

-1) Shoold a GP I isolation have occurred?

Yes Go to Step 2 l No Go to Part III

2) Check for the following alarms and computer ,

printouts (all not required):

A) System I Main Steam Line Lo Pressure Alarm B) System II Main Steam Line Lo Pressure C) System I Main Steam Line Hi Radiation i D) System II Main Steam Line Hi Radiation

'A' E) System I Rx Vessel Lo Lo Water Level Computer L:

, , ,_ ; . ~ . . - - .s .

C.O.L. GP-18 Page 4 of 16, Rev. 3 ,

Computer'C' F) System II Rx Vessel In Lo Water Level Computer 'B'  !

C mputer'D' l

(- G) System I Steam Line Hi Temp Comouter 'A' Computer 'C' H) System II Steam Line Hi Temp Computer 'B' Computer 'D' I) System I Main Steam Hi Flow Alarm Computer ' A'

'C' J) System II Main Steam Hi Flow 'B'

'D' K) GP I Isolation Relays Not Reset Ch. A Alarm L) GP I Isolation Relays Not Reset Ch. B Alarm

3) Did a GP I isolation occur?

Yes Go to Step 4 No Indicate discrepancies in Part VIII and go to Step 4.

4) Check that the following-occurred:

A) All MSIV's close B) MSL sample valves close C) MSL drains close D) Recirc sample valves close E) RHR sample valves close F) Mech. vac. Pp trips (on high rad) 5)' Were any RHR sample valve isolations bypassed?

Yes Go to Step 6 No Go to Step 7

6) List RdR sample valves bypassed.

(' 7) Conments.

l

8) Go to Part III.

RTERENCES

1) PCIS Logic M-1-S-23 i

. . C.O.L. GP-18 Page 5 of 16, Rev. 3 .

PARr III PCIS GP II/GP III

1) Should a GP II or GP III isolation have occurred?

Yes Go to Step 2 No Go to Part IV

2) Check for the fo? _.741ng alarms (not all required):

A) GP II/III inboard isol. relays not reset alarm B) GP II/III outboard isol. relays not reset alarm C) Reactor vessel lo water level trip alarm D) D/W hi press trip alarm E) Reactor bldg. or refueling floor vent exh. hi rad trip alarm F) Clean up recirc pump suct, line break alarm G) System I hi Rx pressure S/D cooling blocked H) System II hi Rx pressure S/D cooling blocked

3) Did any GP II or GP III isolations occur?

Yes Go to Step 4.

No Go to Part IV and list discrepancies in Part VIII.

4) Check which groups of valves' isolated:

GP II A Inboard Outboard GP II B i GP II C GP II D GP III

! Verify all valves in the above checked groups are in the isolated condition. List any discrepancies in Part VIII of this C.O.L. (see GP-8 for list of valves).

- 5) Did SDGr operate?

Yes Go to Step 6 No Go to Step 7 6). Check which SBGT components operated.

l Filter train A B Fan A B C

7) Did secondary containment isolate?

Yes Go to Step 8 ,

No Go to Step 9 l 8) Indicate which valves closed.

I l A0 20452 AD 30452 l AO 20453 AD 30453 A0 20457 AD 30457 i

, C.O.L. GP-18 Page 6 of 16, Rev. 3 .

AO 20458 AD 30458 AO 20459 AD 30459 g

AO 20460 AD 30460 AO 20461 AD 30461 AO 20462 AO 30462 AO 20463 AO 30463 AO 20464 AO 30464 AO 20467 AO 30467 AD 20468 AO 30468

9) Were any GP II or GP III isolations bypassed?

Yes Go to Step 10 No Go to Step 11

10) Check any GP II/GP III isolation that was bypassed:

A) Inst. N2 to drywell AD 2969 A&B B) Inboard D/W 2" vent AD 2509 C) Outboard D/N 2" vent AO 2510 & AO 2523 D) Inboard torus 2" vent AO 2513 E) Outboard torus 2" vent AO 2514 F) Inboard cad sample valves SV 5966A-D G) Outboard cad sample valve SV 910A H) 02 analyzer inboard isol. vivs SV 2671 I) 02 analyzer outboard isol. vivs SV 2978

11) Coments, s

12) Go to Part IV.

MtnKENCES PCIS logic M-1-S-23 i

PARP IV BJCS - 104 PRESSURE ,

1) Should any lw pressure EOCS systems have initiated?

Yes Go to Step 2 No Go to Part V

2) Check for the follw ing alarms (not all required):

i i

I _ . _ . _ _ . _ . . . _ _ - . - . - - . - - - , -

. C.O.L. GP-18 Page 6 of 16, Rev. 3 ,

AO 20458 AO 30458 AO 20459 AO 30459

AO 20460 AO 30460 AO 20461 AO 30461 AO 20462 AD 30462 AO 20463 AD 30463 AO 20464 AO 30464 AO 20467 AD 30467 AO 20468 AO 30468

9) Were any GP II or GP III isolations bypassed?

Yes Go to Step 10 No Go to Step 11

10) Check any GP II/GP III isolation that was bypassed:

A) Inst. N2 to drywell AO 2969 A&B B) Inboard D/R 2" vent AD 2509 C) Outboard D/W 2" vent AO 2510 & AO 2523 D) Inboard torus 2" vent AD 2513 E) Outboard torus 2" vent AO 2514 F) Inboard cad sample valves SV 5966A-D G) Outboard cad sample valve SV 910A H) 02 analyzer inboard isol. Vlvs SV 2671 I) 02 analyzer outboard isol. vivs SV 2978

11) Coments.

12) Go to Part IV.

REFER N PCIS logic M-1-S-23 PARP IV 10CS - IDd PRESSURE

1) Should any lw pressure ETS systems have initiated?

Yes Go to Step 2 No Go to Part V

2) Check for the following alarms (not all required):

Page 7 of 16, Rev. 3 -

A) System I reactor lo pressure is alarmed B) System II reactor low pressure is alarmed C) Hi drywell press. signal sealed in alarmed

( D) System I reactor vessel water lo lo lo.

level is alarmed E) Syste.n II reactor vessel water lo lo lo level is alarmed

3) Did any mm pumps initiate?

Yes Go to Step 4 No Go to Step 5

4) Check which of the following occurred:

A) A R9R Pp start B) B m m Pp start C) C RIR Pp start D) D RHR Pp start E) MO-10-25A opened F) ML)-10-25B opened G) Mo-10-154A opened H) MD-10-154B opened I) Mm relays not reset ' A' logic alarmed J) RIE relays not reset 'B' ~ logic alarmed

5) Did any core spray pump start?

( Yes Go to Step 6 No Go to Step 7

6) Check which of the follcuing occur:

A) A core spray Pp start B) B core spray Pp start C) C core spray Pp start D) D core spray Pp start E) bD-14-llA opened F) MO-14-12A opened G) bD-14-lla opened H) bD-14-128 opened J) Core spray relays not reset logic ' A' alarmed K) Core spray relays not reset logic 'B' alarmcd

7) Comments on IUIR/ core spray operation:

8) Go to Part V.

REFERENCES Low Press EOCS,

. C.O.L. GP-18 Page 8 of 16, Rev. 3 .

4

1) Im logic M-1-S-65 4

2) Core spray lo3ic M-1-5-40 <

PARP V IOCS SYSTQ4S - HI PRESSURE

1) Should any hign pressure DDCS systems have initiated?

Yes Go to Step 2 No Go to Part VI

2) Check wnich of the foll wing occur:

A) Rx lo level alarm on C204B  ;

B) D/W hi press alarm C) D/W press sealed in alarm i D) ADS timer initiated alarm E) Rx lo lo level alarm

3) Did HPCI initiate?

Yes Go to Step 4 No Go to Step 5

4) Check the follwing actions.

A) Aux oil pump started B) MO-23-14 opened C) MD 23-19 opened D) Turb. gov. & stop valves open E) HPCI relays not reset alarm

5) Did HPCI isolate?

Yes Go to Step 6 No Go to Step 7

6) Check for the foll w ing (not all required):

A) HPCI steam line hi fim alarm B) HPCI relays not reset alarm C) HPCI valves isolate per GP 8 1 7) Did HPCI trip?

Yes Go to Step 7 ,

No Go to Step 8

8) Check the follwing (not all required):

A) Turb, trip alarm B) Turb. SV & CV close C) HPCI Pp suct. l w press alarm

. . , C.O.L. GP-18

.Page 9 of 16, Rev. 3 ,

D) lioCI turb, exh. line disch. press alarm E) Turbine overspeed F) Manual trip I G) 11PCI isolation H) Hi Rx water level

9) Comnents on HPCI operation.

10) Did RCIC initiate?

Yes Go to Step 10 No Go to Step 11 ll) Check the follwing (not all required):

A) RCIC relays not reset alarm B) RCIC turb. gov. & SV open C) MD-13-31 opened D) Mo-13-21 opened

12) Did RCIC isolate?

Yes Go to Step 12 No Go to Step 13

13) Check the follwing (not all required):

A) RCIC steam line hi flow alarm B) HCIC relays not reset alarm C) RCIC valves isolate per GP-8

14) Did RCIC trip or shut down?

Yes Go to Step 14 No Go to Step 15 l

15) Check the following conditions and alarms (not all required):

A) RCIC turb. trip alarm B) HCIC pump suct. lo pressure alarm C) RCIC turb. exh. line disch. high D) RCIC turb. SV & CV close

.. E) Turb, overspeed ,

F) Manual trip G) Isolation H) Hi reactor water level

16) Comnents on RCIC operation.

l l

. . C.O.L. GP-18 Page 10 of 16, Rev. 3 .

1 i (

17) Did ADS timers initiate?

Yes Go to Step 17 No Go to Part VI

18) Did ADS timers go to completion?

Yes No

19) List those ADS RV's that indicate open:

A B

C G

K

20) Comnents on ADS.

1

21) Go to Part VI.

High pressure ECCS reference prints:

1) HPCI M-1-S-42

2) RCIC M-1-S-36

3) ADS M-1-S-52

4) Core spray M-1-S-40

5) WIR M-1-S-65 PART VI 4KV & D/G OPERUION f

1) Should any diesel generators have started?

Yes Go to Step 2 -

, ,, No Go to Step 2 ,

2) Should a 4KV fast transfer have occurred?

Yes Go to Step 3 NO Go to Part VII

+

3) Did a loss of power occur?

l

C.O.L. GP-18 L' age L1 of 16, llev. 3 Yen Go to Step 4 4

No Go to Step 6

! I.

4) Did a 4KV fast transfer occur?

, Yec Go to Step 5 No Go to Step 6 & list discrepancies in Part VIII.

5) List final 4KV breaker positions.

212 Open Close 313 Open Close 222 323 ~

232 333 242 343

6) Did any diesel generators start?

Yes Go to Step 7 No Go to Step 10

7) Check which D/G started.

A C

] B D

, 8) Did any D/G load?

i Yes Go to Step 9 l

No Go to Step 10 3 9) Which D/G bkrs. closed?

12 13-22 23 4

32 33 42 43

10) Comnents on D/G and 4KV operation.

ll) Go to Part VII.

i I

PART VII 13KV AND IRIN TURB. GENERATOR

1) Was the .nain turbine on?

Yes Go to Step 2 l

1

C.O.L. GP-18 Page 12 of 16, Rev. 3 No _ Go to Part VIII

2) Turb. trip waa:

Manual Autonatic ~

~~

3) Should a 13iW transfer have occurred?

Yes Go to Step 4 No Go to Step 6

4) 13KV transfer was:

Automatic Go to Step 5 Manual Go to Step 6 Did not occur Go to Step 6 and list discrepancy in Part VIII.

5) Verify the following:

A) A recirc Pp trip B) B recirc Pp trip C) Fact transfer was to bkr and bkr

6) Verify tne following actions:

A) Stop valve not open trip. Annunciator _ _ _

Channel A Conputer B

C D

B) Turb. CV close trip. Annunciator Cnannel A Conputer B

C i

D I C) Gen, protective lockout 386B trip D) Gen. protective Bk. 386F trip E) Gen output bkrs. trips i F) Gen. fld. bkr. trip

7) List other gen. lockout relays that are flagged.

f m =~ o o s

. . C.O.L. GP-18 Page 13 of 16, R v. 3 -

Co:nnents:

(

REFERDCES Turb. trip E-119 Gen, lockout E-92 PART VIII 1)- To allow for future reconstruction of the event, list the names of the following individuals.

Snif t Superintendent Shif t Supervisor Chief Operator U/2 ACO U/3 ACO STA P0 APO A0 Helper List any other personnel involved and their work groups.

f f

_ _ . . . - . _ . . _ _ .. . - , . , , . . _ _ - . . - . . - . , . - _ - _, -.-m.. - .. - - , , , . , , , .

F

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• C.O.L. GP-18 Page 14 of 16, Rev. 3 PARf IX

( 1) List any unresolved or unexplained conditions noted  :

in this procedure.

P C.O.L. Completed By SfA Review By NOTE: THE FOLLOETING STEPS ARE 'IO BE COMPLBTED BY THE OPERATIONS ENGINECR OR ALTERNATS AS APPLICABLE.

2) Porc Review Required Due To i

I A) Undetermined cause of scram.

l l B) Unexplained or unidentified actions or events.

C) Failure of ETS to properly op2 rate.

D) Failure of all control rods to fully insert.

E) Failure of RPS, PCIS or other systems subject to LSSS to operate as required.

l l F) Other significant event as determined by Operations Engineer.

.. G) No Porc review required. ,

l Reviewed By l (Operations Engineer or Alt.)

f. ,

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• C.O.L. GP-18

, Page 15 of 16, Rev. 3 '

3) List Items Requiring Porc Review

(

4) List Actions Required By Porc Review

5) Porc Review Complete and all Actions Required by Porc Completed t

/

PORC MIG. NO. INITIAL

6) Was an O&SR Review Required Yes Go To Step 7 No End i

1

7) Describe Conditions Warranting O&SR Review l

i l

l l

T

• C.O.L. GP-18 Page 16 of 16, Rev. 3 ,

8) Describe Actions Required by O&SR Review

(

9) All Actions Required by O&SR Review Are Completed INITIAL

.e ,

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Page1u[1, . .. S.

SAS:tth if7/D \

EERBtr 3 ILADELPHIA ELE 0rRIC COMPANY PEACH B0 RIOM UNITS 2 AND 3 REACIOR STARIUP ORDER

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UNIT NtNBER STEPS IDENTIFIED BY + ARE Nor REQUIRED ON A SCRAM RECOVERY. STEPS IDENTIFIED BY + MAY BE WAIVED BY ONE PORC MENBER ON A FAST PLANT REXXNERY (SHUIDOM4 48 HRS.) IF MAINTENANCE DID Nor AFFIIT. THE SYSTEM INVOLVED.

C.O.L. G.P. 2A Initial and Time (

A. PRIOR TO REACIOR START-UP

1. Maintenance or other operations which effect reactor safety complete. Work on tech. spec.

equipnent or instement. /

1.a Isc Group verify all required surveillance tests are complete. /

1.b I&C Group verified that RT 8.0

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has been successfully empleted. /

1.c I&C Group verified that SF-13.38-2 or ST-13.38-3 has been completed (only

?

required following a refueling outage) . /

Step 1.b is to be done at the option of the operations engineer.

1.d If a Safety Relief Valve (s) failed to function as designed as a cause of or daring the shutdown prior to this startup, verify that the valve was replaced with a new or reconditioned valve, or that the failed valve itself was renoved from service, disassembled, inspected, adjusted and pressure set-point tested with steam (NIC IE Bulletin No. 80-25). /

2. All open permits reviewed to determine their effect on plant operation. (Work on tech, spec.

equignant or instruments) . /

3. Jumper log reviewed and no jumpers installed which affect safe operation of the plant. /

4. Locked valve log reviewed and valve positions

C.O.L. GP-2A

,' Paga 2 of 14, Rev. 54 satisfactory for plant start-up. /

I Water tight doors for interior flooding

+5.

protection below elev. 116 checked closed per procedure S.15.1. /

+6. Floor drains in all ECCS rooms plugged.

HPCI B&D RHR j RCIC A&C Core Spray A&C RHR B&D Core Spray

'Ihis step is a good idea, but is not a requirement. /

7. Perform ST 2.4.11 A/C/F (ST 2.9.11 A/C/F) and Sr 2.4.11 B/D/E (ST 2.9.11 B/D/E) Functional Test of scram discharge volume instrumentation after every scram prior to startup. /

8. Outstanding MRFs reviewed to determine their impact on plant operation. /

9. GP 1 coupleted if required by Engineer-Operations or alternate and filed with startup package. (If not required, mark this step N/A). /

10. Was shutdown due to a scram? Yes No .

( If yes, verify that C.O.L. GP-18 has been completed prior to startup. /

11. Sr 6.15 Recirc Pump Disch. Valve operability must be completed if it has not been performed in the last

?

31 days. /,

12. CHECK LIQUID NITIOGEN INVINIORIES. ORDER m 2 AS NH2SSARY 'IO ENSURE SUFFICIINE QUANTITY 'IO INERP CONIAINMENr. CONTAINMENT INERFING MJST BB3IN AS I

EARLY AS POSSIBLE PER S.3.9.1.A & H. /

+13. Perform and sign-off one of the following (a or b):

1 l

a. Verify by reviewing the door access history (available from the Sergeant of the Guard) that no entries have been made through door No.194 (Unit 3, No. 250) into the Unit 2 (Unit 3) MSIV room during the just coupleted outage. Alternately, a review of RWP's may be performed to make this determination. /

b. Verify by visual inspection that there are no, transient combustibles present in the MSIV room.

l Immediately remove any which are found and re-inspect. /

+14. Perform and sign-off one of the following (a or b):

C.O.L. GP-2A Pag 2 3 of 14, Rev. 54

a. Verify by reviewing the door access history (available from the Sergeant of the. Guard) that no entries have been made through door No. 59 (Unit 3, No. 60) into the Unit 2 (Unit 3) off-gas pipe tunnel. Alternately, a review of IMP's may be performed to make thi? determination. /

b. Verify by visual inspection that there are no transient combustibles present in the Unit T (Unit 3) offgas line pipe tunnel. Imediately

)

renove any which are found and re-inspect. /

15. If a drywell entry has been made, verify open position for the following locked valves by verifying open indi-caticn in the ccntrol room:

10-81A ' A' loop RHR Injection Block Valve (Panel C03)10-81B 'B' loop RHR Injection Block Valve (Panel C03) /

14-14A 'A' Loop CS Injection Block Valve (Panel C04)14-14B 'B' Loop CS Injection Block Valve (Panel C03) 11-18 SBL Injection (Panel COSA)

16. If a drywell entry has been made:

A. Verify that the shutdowT1 cooling manual block valve is open. /

t 10-88 B. Perform non-automatic containment isolation valve C.O.L. S.3.9.3.A (Unit 2) or C.O.L. S.3.9.3.B (Unit 3) . /

17. SRM - Drawer Functional Test cmpleted (Sr 3.1.3) . /

10. SRM - Channels bypassed, if any i

A B C /

D NONE

19. SRM - Recorder Count Rates - All count rates must be equal to or greater than 3 cps. Record the count rate.

A B C D /

20. SRM Detectors fully inserted. /

21. IBM - drawer functional test completed (Sr 3.2.3) .

! Must be performed once/ week if startup exceeds one week. /

22. IRM - channels bypassed, if any

. . C.O.L. GP-2A Paga 4 of 14, Rev. 54 l

A B C D E F G H NONE /

23. All Im range switches in range 1. /

24. All Im detectors fully inserted. /

25. APM functional test completed. (Sr 3.3.6) /

l 26. Each AP M has at least 2 LP m inputs per level and at least 14 total LPM inputs. /

27. APM bypassed, if any.

A B C D i E F NONE /

l i 28. Reactor protection system in service. /  ;

29. Rod worth minimizer in service per procedures S.S.S.A, S.5.5.B and tested by SP 10.5. /  ;

30. RSCS system in service and tested by Sr 10.6.

(Steps 1 thru 9) /

31. All operable control rods fully inserted and positions known from rod position information system. /

32. All control rods and m =31ators fully operable. / l

33. No Rod Sequence Control System keyswitches are in use,  ?

except rods with a failed " Full In" or " Full Out" position l switd1 where the actual rod position is known. /

34. Two LICENSED OPERATORS in control room. /

NMES: AND l

35. ELECTRICAL SYSTm:

A. Both off-site sources and the startup ,

transformers and emergency transformers are available and capable of automatically '

l supplying power to the 4KV ernrgency buses. /

l B. The four diesel generators are operable and ,

l there is a minimum of 104,000 gal. of diesel  ;

fuel on site. / I l

C. The 4KV emergency buses and the 480V l emergency load centers are energized. / l I

D. The four unit 125V batteries and their l

C.O.L. GP-2A Page 5 of 14, R:v. 54 chargers are operable. /

I 36. ADS system operable. /

37. Main steam relief valve system operable. /

38. Relief valve discharge line vacuum breakers indicate closed and all red pushbuttons in the

" Button Out" position. POS-8096A thru L. / _

, 39. Main steam safety valves operable. /

40. Control rod remrwal bridge locked in pmitita with the deck plates removed. /

\

41. CBD housing support is in place & has been inspected after any disassembly. /

42. Primary ocntainment integrity established, PCIS is operable, and Torus and Drywell Vacuum Breakers operable. (Not required for open vessel testing.) /

43. Ventilation set up for inerting the containment via SBGIS (Procedure S.3.9.1.A) /

44. Perform C.O.L. S.3.9.1.A. Purge valves may be left open at this time. /

45. Drywell cleared of personnel and outer air lock door locked or reason why not.

1

/

46. Secondary Containment integrity in effect. /

47. Standby Gas Treatment System operable. /

48. Reactor Water Iodine Concentration is less than 2.0 microcuries/ gram of dose equivalent I-131. /

49. Reactor coolant and feedwater chemistry.

i

! A. Reactor coolant chloride concentration is less than 0.2 ppm and conductivity is less than 5.0 umho/an, and startup chemistry ST 7.2.3.B has been started. /

l +B. The heat cycle shall be cleaned with long path recirculation on every startup from cold conditions when condenser vacuum

, has been lost (< 20 inches) for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the heat cycle (waterside) is breached. This step may be deleted by the station superintendent or alternate. This step need i -_ _ _ _ _

C.O.L. GP-2A Pag 3 6 of 14, Rev. 54 not be ccupleted prior to startup but it must be cmpleted prior to exceeding 212 degrees F if required. Establish long 4

path recirculation with one condensate pump running through the heat cycle with the F/W stop valves closed and the manual feed pump bypass valve (12") open. Long path recirculation shall be through one feedwater heater string at a time with the appropriate 2 out of 3 feedwater heater string outlet valves (MO-2132 A, B, or C) closed. Long path recirculation shall continue on each string until the 5th heater effluent chemistry is satisfactory (Turbidity less than or equal to 0.2 FIU and conductivity less than or equal to 1.0 umho/m at 25 degrees C). It will take about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to flush each feedwater string. Notify chemistry to start RF 7.8 to record this flush data. Once satisfactory effluent is obtained open the heater string outlet valve (MO-2132 A, B, or C) for the next string to be flushed and close the outlet valve for the string just flushed. Flush the next string until its effluent chemistry is satisfactory. Repeat the above for the last string. When satisfactory chemistry is obtained in all three strings, open all the heater string outlet valves and cantinue with startup operations. The manual feed pump bypass valve (12") may be closed at this time.

'A' string flushed satisfactory /

'B' string flushed satisfactory /

'C' string flushed satisfactory /

IF NO HEAT CYCLE FLUSH IS REQUIRED (HOT STARIUP, RECOVERY FROM SCRAM WITHIN 24 HOURS OR NO MAINTEN-ANCE W HEATERS) MARK THE ABOVE BLANKS WI'IH A "NA" AND INITIALS.

l C. MO 29A & B open and mousetrapped. /

l 50. Both Core Spray Subsystems and Initiating Instrmentation are operable and discharge piping to last block valve is filled. /

51. A, C, and D core spray pump room unit coolers appropriately arranged in RUN arxl AUIO. One B core spray pump rom unit cooler shall be in operation at all times (due to cabling problems). /

52. The LPCI Subsystems and Initiating Instr mentation are operable and discharge piping from the pumps to the last block valve is filled.

53. A, C, and D RHR pump room unit coolers appropriately arranged in RUN and AUID. One B RHR pump rom unit cool shall be in operation at all times (due to cabling problems). /

54. The Standby Liquid Control System is eperable and the tank volume, temperature and concentration are within

__ _ _ _ _ _ ._ ~ ___. ___

C.O.L. GP-2A Page 7 of 14, Rev. 54 tolerance. /

55. A H twenty jet pumps are operable. Verified by observing flow indication on the meters in the cable spreading room. /

56. The HPSW system is operable and a n containment cooling loops available. /

57. The HPCI system is operable. If pump suction is from the torus, ensure water flow frczn pump discharge high point vent. /

58. One HPCI room unit cooler shall be in operation at au times, the other in AUIO. /

59. The RCIC system is operable. If pump suction is from the torus, ensure water flow from pump discharge high point vent. /

60. One RCIC room unit cooler in 10N, other in AUIO. /

61. Refueling deck exhaust radiation monitors not known to be iroperable. /

62. Reactor building exhaust radiation monitors not known to be inoperable. /

63. Air ejector off-gas radiation monitors checked for operability by performing S.ll.2.BB Part A. /

l l

64. Roof vent radiation monitors not known  ?

to be inoperable. /

65. Main off-gas stack radiation monitors I

not known to be inoperable. /

l 66. Main steam line radiation monitors not l known to be inoperable. /

l 67. Off-gas line isolation sw. in auto position. /

68. Perform C.O.L. S.ll.2.A.17, off-gas system l hydrogen analyzer normal line-up to ensure l

H2 analyzers are in service. /

i

69. Drywen sumps and integrators operable. /

l 70. Dryw2H air sampling system for gas, I iodine and particulate not known to be l

inoperable. /

l 71. No safety related hydraulic snubbers L e to be inoperable. /

1

C.O.L. GP-2A Pag 3 8 of 14, Rev. 54

72. Both instrument air backup valves to I the drywen in AITIO. /

73. All four FT-110's, recirculation system drive flow, valved in service. These are normally valved out of service when the plant is on shutdown cooling. ,

/

74. Containment atmospheric dilution system operable. /

75. CAD system H2 and 02 analyzer on drywell not known to be inoperable. /

76. CAD system H2 and 02 analyzer on torus not known to be inoperable. /

77. 2000 gallons of liquid nitrogen in CAD tank. /

78. Reactor vessel water level normal. /

4 79. Check all annunciators for conditions which could affect plant safety. /

80. Drywen strongbacks instaHed. (Optional at this

, time.) /

81. Inerting of containment may begin. The primary containment butterfly valves cannot be assured of closing from the fun open position during a design basis IDCA. Therefore, the primary containment  ?

! butterfly valves must be limited to less than 37 degrees opening (snap rings installed) unless the reactor coolant temperature is less than 212 degrees AND the reactor node switd1 is in SHUrD09N or REFUEL.

When reactor pressure is >105 psig AND the reactor is critical AND the mode switch is in startup or run, start the 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> clock if the containment vent values are stin required to be open. (See Sr 9.16)

a. Verify snap-rings are instaued on au containment butterfly valves as listed in S.3-9.1.H (Valves set at 30 degrees) prior to placing the mode switch in STARr-UP. / _

(Operate valves per Procedure S.3.9.1.H)

6. After containment is inerted, verify that the boot seals on an 18" butterfly valves have been inflated, by verifying that the red valve position indicating lights are '

extinguished and that the green lights

C.O.L. GP-2A Pag 2 9 of 14, Rev. 54 are lit. Also, verify that the 4 alarms that annunciate valves open are clear -

Panel C203B windows 1,2 & 3 and panel C203C window 21 (See Page 14). /

82. Inspection by shift supervision inside drywell completed. Inspection nust verify:

1. All insulation in place

2. Cleanliness

3. All scaffolding removed

4. No foreign material in drywell l

5. Temporary shielding removed /

83. EHC system is not known to be contaminated l with water. /

84. This step is not necessary to be completed prior to startup. Clear the TIP machine block if it was applied and install signs of 4 torus area access doors, the ladder to the TIP room and the door to the TIP room which read "Before entering this area, sign the TIP and torus area access log book located on the desk mounted on the shield wall outside the Ccntrol Room (North-Unit 3 & South-Unit 2) . /

I'IEMS 1 THRU 85 t

REVIEWED BY IRTE BRING ALL NCN-CCNFORMANCES WIDI THIS CHEK-OFF LISP TO THE ATTENTION OF BIE OPERATICNS ENGINEER FOR CONCURRENCE OR CORRECTIVE ACTION.

ACEEPTABIE NON-CONFORMANCES WSr BE INITIALED BY THE SHIPr SUPERINTENDEM

, AND CNE PORC MEMBER.

1 THIS CHEK-OEF LISP IS NOP CDNSIDERED COMPIETE UNTIL REVIEWED AND SIGNED BY SHIPr SUPERVISION.

CAUTION!!

EXTREMELY SiORT REACIOR PERIODS HAVE BEEN EXPERIENCED DURING REACIOR STPRIUPS AT OTHER FACILITIES DUE TO RIGH 100 NOIGI WORIHS. WIDIDRAWAL OF THE FIRSr RCD (S) IN A NEW ROD GROUP, ESPEIALLY GROUPS 3 AND 4, WILL USUAILY EXHIBIT HIGI ICD N0101 WORIH. ALSO DURING STARIUPS WITH XEDNON PEAK CONDITIONS AND NO VOIDS IN THE CORE WI'INDRAHAL OF ALL BODS AND ESPECIAILY EDGE HCDS MAY EXHIBIT HIGH 10D NOICH %ORIUS. THEREEORE, EXTREME CAUPION WST BE EXERCISED DURING STARIUPS UNDER DIESE CONDITIONS. IF i UNUSUAILY HIGH IG N0101 WORIHS ARE OBSERVED, NOTIFY A REACIOR ENGINEER.  :

85. Approval obtained to start Reactor.

l APPBOVED: Station Superintendent PER: __

~ ' C.O.L. GP-2A Paga 10 of 14, Rev. 54 DATE: TIME:

I

86. Startup performed by:

SID:

DATE:

TIME:

87. Emergency Rod In switch tested on rod location.

88. Criticality achieved at:

DATE: REACIOR WATER TEMP.

TIME: PERIOD:

100: SEQUENCE:

IOSITION: OUT OF SEQUENCE BODS COUNr RATE:

ABOVE CRITICALITY DATA REVIEMED.

SS/SSV

89. Shutdown Margin Test Sr 3.8-2 (Sr 3.8-3) performed for initial startup following a refueling outage. If not required, mark N/A.

l Verified By/Date

?

B. PRIOR 'IO EXtyRnING 212 DEGREES F

1. Section A completed. /

2. Control Room Ventilation System in normal service and radiation monitor operable. /

3. Emergency S&vice Water System is operable. /

3

4. 'Ibrus water voltane 122,900 - 127,300 ft.

and temperature 90 degrees F or less.

i (14.5 to 14.9 feet) /

5. Vessel Temperature 100 degrees F or higher (must be higher than 185 degrees F to pressurize above 250 psig). /

6. Unidentified reactor coolant leakages is less than 5 gpn; total leakage is less than 25 gpn. /

7. Verify recirculation pump seal purge valve (s)

l C.O.L. GP-2A Paga 11 of 14, Rev. 54 l MD 8029 (9029) A&B, open and 1-3 gpm on FI 8029 (9029) A&B for recirc. pump (s) operating i

FI 8029 (9029) A&B on 135' Elev. Reactor Bldg.

in CBD Flow Control area. /

8. Turbine on turning gear, vacuum established, bypass valves operable. / l

9. Main steam line drains open. /

10. Reactor temperature above Tech. Spec.

Figure 3.6.3. /

11. Prior to placing air ejector in service:

a. Verify that lights in off gas tunnel are turned off. /

b. Verify that any other portable equipment which is plugged in the tunnel has been disconnected. /

c. Verify that all combustible material has been removed fran the tunnel area. /

d. Fill all loop seals listed in Appendix A. /

, REVIEHED BY IRTE SHIFT SUPERVISION BRING ALL NOMXNPOIV%NCES WI'1H THIS CHECK-OFF LIST 'IO 'IHE ATTENTION OF THE OPERATICNS ENGINEER FOR CONCURRENCE OR CORREXM'IVE ACTION.

ACCEPIABLE NCN-CONFORMANCE 14JSP BE INITIALED BY THE SHIFT SUPERINTENDENT ?  !

AND CNE PORC MEMBER. l l

THIS CHEEK-OEF LISP IS NOT CJNSIDERED OCMPIETE UNTIL REVIEWED AND SIGNED BY SHIFT SUPERVISION.

C. PRIOR '1D EXCEEDING 600 PSIG

1. Verify condenser vacuum and MSIV closure scram annunciators have reset. /

2. Verify offgas radiation monitor sample flow per S 11.2 BB. /

i

3. Verify at least one reactor feed pump is in  !

service ready to deliver feedwater to the  ;

reactor. /

BRING ALL N(N-CONPORMANCES WI'1H THIS CHECK-OFF LISP 'IO '1HE ATTENTION l OF '1HE OPERATIONS ENGINEER FOR CONCURRENCE OR CORRECTIVE ACTION.

ACCEPIABIE NON-CONPORMANCE 14JST BE INITIALED BY '1HE SHIFT SUPERINTENDENT AND CNE PORC MEMBER.

. . C.O.L. GP-2A

,, Pag 2 12 of 14, Rev. 54

'IHIS CHECK-OET LIST IS NOT CENSIDE3ED 00MPTIE UNTIL RENIEWED AND SIGNED I BY SHIFT SUPERVISION.

D. REACIOR M PRESSURE

1. Tura off the drywell lights Unit 2 - Panel 25-L 1

Unit 3 - Panel 35-L /

2. Leak test the airlotL Initial when results are reported. /

3. Chain and lock the outer drywell door. /

4. With recombiner in service, return off gas line isolation sw. to the open position.

Perform final off-gas radiaticm monitor adjustments per S.ll.2.BB Part B. /

5. Conplete C.O.L. S.3.9.1.A that was started in step 41. /

t

C.O.L. GP-2A

,* - Page 13 of 14, Rev. 54 REVIEWED BY DATE SHIFr SUPERVISIN BRING ALL NC2HJ0tFCRMANCES WITH THIS CHECK-Of7 LIST TO THE ATTENTION OF THE OPERATICNS ENGINEER FOR CCNCIIRRENCE OR CORRECTIVE ACTION.

ACEEPEABIE N0tHXNFORMANCES MIST BE INITIALED BY 'lHE SHIFr SUPERINPENDENT AND ONE PWC MEMBER.

THIS CHECK-OE7 LIST IS NOT CONSIDERED CCNPIETE UNTIL REVIEWED AND SIGNED BY SHIFT SUPERVISION.

O i

. \ EIHIBIT 4 A-7 APPENDIX 3 Pago 1 of 4, Rov. I gA s .

SilIFT TECHNICAL ADVISOR // 5'/

- DUTIES AND RESPONSIBILITIES 4 ,,,

The shift technical advisor shall serve in advisory capacity to shift supervision. He shall not assume a command or control function. .He shall always be able to report to the control room within 10 minutos during his shift.

Rosponsibilitios during Routine Plant Operations and Outages. .

Primary duty is to maintain and improve nucioar safoty in the oporation of tho plant under accident, ttansient and normal operating conditions.  !!is primary means of accomplishing this task is by observ.ing operations and making recommendations to the shift super-vision and the plant staff. Whilo on shift he shall report directly to the Shift S up o r i n t. o n d e n t . For administrative and other purposos he is under the supervision of the Engineer-Technical. The STA shall not allow any assigned duties to detract from his dodicated

• concern for sufoty of the plant. ,

OPERATIONS ASSESSMENT A. During Normal Operations l

l

1. Ilo shall rcs? and review the below listed logs to ensuro operational problems are corrected, or correctivo action ordered (MRF'd) and properly closed out.

l LOGS:

a. Shift Technical Advisor

b. Shift Supervision I c. Control Oporator

d. Assistant Control Operator Unit 243

e. Radwasto

2. Roviow Jumpor Status Shoots for each Unit ACO and the C0 post. Initial entries not previously initialed.

3. Survey systems which are governed by the Specifications i to ensure Operability Requirements are met. .

4. Survey systems wh n are not governed by the Technical Specifications for proper operation.

S. Survey systems for performance in accordance with design.

. " Survey" moans to check valve lineups, flows, prossures, temperatures, etc., to ensuro the system porformanco or lino up for automatic oporation is in accordanco with design, m

I

A-7 APPENDIX 3 Paga 2 of 4, Rev.

r

• S. Following transionts, review system design and performance for proper operation under upset conditions, and suggest modifications as appropriate.

Following transients, review ' applicable procedures for completeness

• 6

• and suggest revisions if desirable. .

Maintain knowledge of modifications to plant equipment and holp 7*

instruct shif t porconnel in this area.

• B. During refueling or maintenance outages, review outage unit conditions to ensure compliance with Tech. Spec's.

NOTE: T!!C STA IS NOT an "on shif t" outage co-ordinator" . Ilis dutics are safety oriented and are especially directed to the Opera-ting Unit. ,

• 9.

Obtain information, road and instruct shift personnel regarding significant operating problem that have occurred at PB and other sites.

• 10. Advise SS/SSV of any problem areas identified.

• 11. Physically verify j un.por installation and rostoration, in accordanco with A.42, at the roquest of Shift Supervision, at locations from which he can report to the Control Room

- within 10 minutes.

12. Maintain a log'of the activitios porformed and problom areas idontified. Sign log at the end of his shift.

Turn over of job responsibility occurs after his roliof initials your log.

• 13. When duties 1 through 4 and 12 have been performed and astorisked (*) items, as required, are completod, the STA may porform his regular work assignnents as long as they do not impare his ability to respond to the control room.

B. During Transient or Emergency Conditions

1. Report to the Control Poom and observe plant instrumentation.

Make a determination that the transient is proceding in accordance with plant design and that the significant parameters are within acceptable limits for that transient.

2. Observe operation of applicable ECCS and availability of ECCS components which wore not activated by the transient.

^ 3. Observe other control room instrumentation not necessarily directly associated with the transient. Make a determination that these values are within normal limits.

• Theseidemsneednotbeperformedoneachshiftandare l optional at the discretion of the STA.

i

. . s, A-/

APPENillX 3 Page 3 of 4, Rev.17

4. Hoport any adverse findings to the Shif t Superintendent, Shif t -

Supervisor or Control Room Operaturu.

5. Continue to observe plant instrumentation and computer out-put until the plant is in a stabic condition.

6. Af ter a stable condition has been achieved, aid shif t personnel in analysis of the transient to determine cause and Tech Spec implication. Report transients and plant condition to individuals specified by Shift Superintendent and serve as a liaison between Technical support personnel (in technical support center) and ,

shift supervision.

7. Observe the overall progrouu of the plant throughout the event.

p Ixt Not become involved in detai,ls , Lu the degrou that the overall picture is lost.

8. , Investigate and write upset reports for plant upsets which foccur on his shift. Ile shall make up at least a preliminary report of the upset and discuss it (via phone if necessary) *

'with plant management prior to leaving the site. The order '

for calling is:

Operations Engineer Technical Engineer Ass't. Station Superintendent Station Superintendent

9. Investigate and write LURs and unusual events (as defined in Tech Spec) which occur on his shift. He shall make a preliminary report of the LER or Unusual Event prior to 1 caving the site.

Ile shall discuss (by phone if necessary) the preliminary report with plant management prior to leaving the site. The order is same as 8 above.

OPERATING EXPERIENCE ASSESSMENT The Operating Experience Assessment Function shall be directed at evaluating the adequacy of the three P's.

1. PLANT: Is the equipment, as installed and maintained adequate?

If not, suggest means for improvement.

2.. PROCEDURES: Are the procedures, as written and performed adequate?

If not, suggest means for improvement.

3. PEOPLE: Is the perf'ormance of the people, as trained and qualified, adequate? If not, suggest means for improving performance.

Once per month a meeting shall be held with offsite participants from other sectione of Electric Production and Engineering Dent.'n. The following subjects shall be discussod:

1. Noted inadequacies in the three P's.

2. Plant transients, upsets, accidents or other off normal conditions experienced.

3. LER's during the past week.

4. Plant upset reports.

Reports.

. . , s A-7 APPENDIX 3 Pags 4 of 4, Rsv

-l' d

The purpose of these meetings is ti assess operating experience to identify weak areas in the 3 P's by af xing the question "What if . . . . . . ."

(conditions or responso has been slightly different) . Recommendations ,

shall be made to correct weak areas.

lictween these monthly meetings, S.T. A personnel should convey outstanding concerns in these areas to the Operations lingineer either verhally or vip the. STA log.

d t.

• s

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