ML20212C055

Trip Rept of 860710-11 Site Visit Re Concerns Arising from Desk Top Review of Util Procedures Generation Package & Operator Use of Emergency Operating Procedures on Simulators.Rev 2 to Procedure OMM-006 & Related Info Encl

ML20212C055
Person / Time
Site:	Harris
Issue date:	08/04/1986
From:	Beverly Clayton Office of Nuclear Reactor Regulation
To:	Buckley B Office of Nuclear Reactor Regulation
Shared Package
ML18004A404	List: ML20212C055 ML20212C061
References
NUDOCS 8608080121
Download: ML20212C055 (49)

Text

_-  ;

9 p arg 73 jog UNITED STATES g g j p, NUCLEAR REGULATORY COMMISSION O E WASHINGTON, D. C. 20555

, vY,:$

AUG 4 Docket No. 50-400 MEMORANDUM FOR: B. Buckley, Project Manager PWR Project Directorate #2 Division of PWR Licensing-A THRU: es . Rossi, Assistant Directer 7 Division of PWR Licensing-A V  !

1 Victor Benaroya, Chief w l Facilities Operations Branch gF/, I Division of PWR Licensing-A j 1

FROM: Brent Clayton, PAF0, DPLA George Lapinsky, PAF0, DPLA Frank Orr, PAF0, DPLA

SUBJECT:

TRIP REPORT - SHEAR 0N HARRIS NUCLEAR POWER PLANT EMERGENCY OPERATING PROCEDURES REVIEW MEETING JULY 10-11,1986 On July 10 and 11,1986, we met with Carolina Power & Light Company represent-atives to discuss concerns arising from a desk-top review of the applicant's procedures generation package (PGP) and to observe operators use the emergency operating procedures on the simulator. We decided on this approach because:

(1) Harris is the first Westinghouse plant we ' ave reviewed that has flow chart format E0Ps, (2) we had a large number of questions from our desk-top review, and (3) the licensing schedule did not allow time for a series of correspondence to resolve our concerns. We were accompanied and assisted by Anne Sutthoff of Battelle Human Affairs Research Center who performed the detailed desk-top  ;

review of the PGP, except for the plant-specific technical guideline which was  !

reviewed in-house.

]

Our meeting consisted of a presentation by applicant representatives on their E0P development process, observation of operators using the E0Ps to respond to several scenarios on the plant reference simulator, and a discussion of concerns arising from our desk-top review of the PGP and observation of the simulator exercise. Enclosure 1 is a list of meeting participants. A copy of the trans-parencies presented by the applicant is provided as Enclosure 2. During the meeting, the applicant provided a revised writer's guide which resolved some of the concerns from the review of the PGP. This revised writer's guide is provided as Enclosure 3. During our visit we also audited some of the applicant's E0Ps to determine if they were consistent with the instructions provided in the j writer's guide.  :

1 At the end of our visit, we still had a number of concerns which are summarized as follows: (1) The Harris E0Ps (both the flow chart procedures and the narrative procedures), while generally preserving the objectives and mitigation i i strategies of the Westinghouse guidelines, provide significantly less detail than i

Contact:

G. Lapinsky l x28166 _ _

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B. Buckley 4%

that provided in the staff-approved Westinghouse Emergency Response Guidelines <

. and-less than that typically observed in other licensees' E0Ps. Because this l 1

s tail is not provided in the E0Ps or other supplemental information available  !

in the control room, this places greater reliance on. operator knowledge than.

the typical . situation. ~ Because of expected degradation in human performance under stress, including memory, the training program on the Harris E0Ps is particularly important. Yet the applicant did not describe any systematic process for ensuring that this-information is included.in the training program.

~

4 (2) The applicant used several. techniques in producing.the flow chart procedures that na nnt 6:11y ennsistent with accepted human factors principles. (3) The writer's guide did.not address a number of the elements in SRP Section 13.5.2, Appendix .

A. - The E0Ps were written in a manner that would accomplish a number of the t objectives included in these elements, but the writer's guide should be

_ modified to provide guidance in these areas to provide assurance that future ,

i E0P revisions will be made in a consistent manner. (4) Our audit of the E0Ps '

disclosed that there were a number of items in the E0Ps that were not written

, in accordance with the writer's guide. These concerns are described in detail in Enclosure 4. Applicant representatives stated ~that these comments

would be formally addressed after receiving this trip report. The staff

reconsnends that the applicant address the resolution of the staffs' concerns

[ according to the following:

j I. Prior to fuel loading -

A. Certain plant-specific information which is called for in the

Westinghouse ERG's has not yet been provided in the Harris E0Ps.

l The applicant should perform a systematic review of training to.

I assure that the information that is missing has been included in the training program. Evidence that current operators have all of i

the required skills and knowledge necessary to implement the E0Ps j should be documented for NRC-review.

i I B. Develop or provide evidence of a training program that systematically l assures that information gaps in flowcharts and textual procedures

! are addressed specifically during future training; the program should

! include development of standards for the evaluation of task-level 1- performance so that the applicant can identify whether all

! operators possess the appropriate enabling skills and knowledge L to implement the E0Ps.

II. Prior to exceeding 5% power -

A. Provide a textual version of the E0P flowcharts in an easily accessible format in the control room. The text should contain i

detail equivalent to the level of detail provided in the WOG ERGS

! and include plant-specific information as called for in the WOG

ERGS.

( l B. Review the "End Path Procedures" and the " Function Restoration l Procedures" to provide the plant-specific information 'as called- i for in the WOG ERGS.

q B. Buckley 4%

C. Specific deficiencies in E0Ps that were identified during'the NRC on-site visit will be resolved.

4 D. All E0Ps will be reviewed and revised ~to be consistent with the current Writer's Guide.

III. Prior to startup following the first refueling outage -

.A. Submit revised PGP including:

1. Revised Writer's Guide resolving NRC identified deficiencies.

, 2. Revised description of V&V program.

j 3. Revised description of training program on ~ E0Ps.

I B. Revise E0Ps consistent with revised Writer's Guide.

C. Validate the revised E0Ps.

D. Train operators on revised E0Ps and implement in control room.

. E. Provide technical basis for the plant-specific information that will be added to the procedures as a result of actions II.A. and i II.B. above.

The applicant should commit to a plan similar to that suggested above as soon

as possible so that our review can proceed expeditiously.

1 A separate supplemental safety evaluation report is being prepared to address the emergency operating procedures.

/s Brent Clayton, F0, DPLA u

l

! eorge ky AF0, DPL 2 d?av Frank Orr, PAF0, DPLA

Enclosures:

1. Meeting Participants

2. CP&L Presentation

3. Revised Writer's Guide i

Staff Comments

4.  !

Enclosure 1 EMERGENCY OPERATING PROCEDURES MEETING PARTICIPANTS July 10-11, 1986 CP&L Personnel Reuben Prichard - Ops. Eng.

Andrew Howe - Spec. Reg. Compl.

Dean Tibbitts - Acting Dir., Reg. Compl.

R. M. Sheppard - Consultant J. M. Collins - Ops. Manager Howard Smith - Ops. Support Supv.

Jim Thompson - Oper. Supv.

John Hudson - Proj. Spec., Lic. Op. Training John Eads - Senior Lic. Eng.

Carey Fleming - SRO, Ops.

Terry Toler - SRO, Ops.

Glen Blinde - HTU Wayne Powell - Dir. , HTU NRC Personnel Brent Clayton - Section Leader Frank Orr - Reactor Systems Engineer George Lapinsky - Engineering Psycholo Anne Sutthoff - Battelle (Consultant) gist 1

i

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9 Enclosure .2 MEETING TRANSPARENCIES l

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1

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• AGSNIH JULY 10 & 11, 1986 I. INTRODUCTION (10:00 am 10 July 1986) CP&L II. SWPP EOP DEVELOPMENT PROCESS BIES A. BASIC ASSUMPTIONS BRIS

1. DEFINITIONS & EXPLANATIONS

- DIRECT CONVERSION WOG 'IO SMPP PROCEDURES

- PATH PROCEDURES (PATH-1; PATH-2)

- PATH PROCEDURE GUIDE

- END PATH PROCEDURE (EPP-1 THRU EPP-26 )

- FUNCTIONAL RES'IORATION PROCEDURES (FRP-S.1 THRU FRP I.3)

CRITICAL SAFETY FUNCTION STATUS TREES.

2. ASSUMED USERS CP&L

^

3. INTEGRATED USE OF PROCEDURES Egg 8

4. USE OF EACH TYPE OF PROCEDURE OR GUIDE BRIS

5. nIODES OF USE EBES B. STEP DEVIATION DOCUMENT MS C. TASK ANALYSIS Ells D. VERIFICATION & VALIDATION (EOP) EMS

1. REVIEW OF PAST V & V PROGRAMS ,

BRIS

2. OLD SWPP SIMULA'IOR BRES

3. TABLE 'IOP EXERCISES Rads

4. SEABROOK SIMULA'IOR BRIS

5. NEW SWPP SIMULA'IOR BRIS E. DEVEIOPMENT OF EOP TRAINING MATERIALS BRIS F. CONTROL ROOM DESICN REVIEW (CRDR) EAIS (11:30 am 10 July 1986)

JULY 10 & 11, 1986 w .._..c. ,- . . . - - . . . _ - . . - - ,,_.,,_n n -- , , - - - , ~ . . - , -

3

-m G. WRITERS GUIDE (08:00 am 11 July 1986) ERIS

1. OMISSIONS CP&L/NBC

- DEFINITIONS,

- EXAMPLES,

- FORMAT GUIDANCE,

- LAYOUT, PHYSICAL DIMENSIONS, TYPE STYLE and SIZE.

2. INCONSISTENCIES BETWEEN TEXT GUIDANCE NBC AND FIGURES

3. OVER-ALL INCONSISTENCIES OR DEFICIENCIES NBC IN GUIDANCE

III. SIMULATOR EXERCISES (12

30 pm 10 July 1986) CP&L IV. ADDITIONAL 'IOPICS (11 July 1986) &&L/lGIC V. CLOSING REMARKS (12:30 pm 11 July 1986) CP&L/NBC r

l l

JULY 10 & 11, 1986 l

. 4 INI130 DUCTION 1

CP&L - RUBIN PRI'ICHARD i

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1

]

1 JULY 10 & 11, 1986

D I II 1P REVIEV V0G PERFORM PREPARE REV.1 V&V PRELIMINARY GUIDELINES (EOP) TRAINING i MODULES 1P PREPARE "

VRITER'S SIMULATOR  :

GUIDE EXERCISES BEGIN TRAINING 1

1P CONVERT EO, VALK "

E1,E E3 TO THROUGH  :

COMPLETE FLOVCHARTS EXERCISE TRAINING MODULE 1,

PREPARE ALL TABLE "

OTHER PROCEDURES TOP  :

BEGIN

, INTO EPP'S & FRP'S EXERCISE FINAL TRAINING 1P '

PREPARE EVALUATE "

STEP V&V -

EVALUATE DEVIATION RESULTS TRAINING DOCUMENT COMMENTS I

,, ,i, 1

PREPARE

• - FINAL EOP SET ,

4 4 BEGIN BEGIN TASK CRDR  : REVIEV ANALYSIS UPDATE HED'S I

4

CRDR PREPARE  ;

SUMMARY

PGP u

II.A.1 EOP DEVEIDPMENT PROCESS WOG 'IO PLANT SPECIFIC PMNNRES WOG

@&L SIIIELINES TITLE EPP-001 ECA-0.0 IDSS OF AC POWER 'IO 1A-SA & IB-SB BUSSES EPP-002 ECA-0.1 IDSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED EPP-003 ECA-0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED h EPP-004 ES-0.1 REAC'IOR TRIP RESPONSE

} EPP-005 ES-0.2 NATURAL CIRCULATION 000LDOWN j EPP-006 ES-0.3 NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL - WITH RVLIS

! EPP-007 ES-0.4 NATURAL CIRCULATION 000LDOWN WITH STEAM j VOID IN VESSEL WITHOUT RVLIS.

i EPP-008 ES-1.1 SI TERMINATION EPP-009 ES-1.2 POST-IOCA 000LDOWN AND DEPRESSURIZATION EPP-010 ES-1.3 TRANSFER 'IU OOLD LEG RECIRCULATION EPP-011 ES-1.4 . TRANSFER 'ID IKyr LEG RECIRCULATION EPP-012 ECA-1.1 IDSS OF EMERGENCY COOLANT RECIRCULATION i EPP-013 ECA-1.2 IOCA OUTSIDE CONTAINMENT 1

i i

I JULY 10 & 11, 1986 i

I.__-..._.-__ _ - . - - _ _ - - . .- _.- .__ __ _ _ _ _ -.- _ -._.. - -- .__ _ _ - - - _ _ - - _ _ _ _ _ _

H*

i II.A.1

, EOP DEVELOPMENT PROCESS WOG 10 PLANT SPECIFIC PanrmIERES WDG Q&L W II E L IliE S TITLE

, EPP-014 E-2 FAULTED STEAM GENERATOR ISOLATION i EPP-015 ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERA 10RS ,

i EPP-016 E-3 SGTR ISOLATION l EPP-017 ES-3.1 POST-SGTR 000LDOWN USING BACKFILL EPP-018 ES-3.2 POST-STGR 000LDOWN USING BIOWDOWN EPP-019 ES-3.3 POST-STGR 000LDOWN USING STEAM DUMP EPP-020 ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT:

SUB000 LED RECOVERY

} EPP-021 ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT:

j SATURATED RECOVERY EPP-022 ECA-3.3 SGTR WITHOUT PRESSURIZER PRESSURE i

CONTROL PATH-1 E-O & E-1 REACTOR TRIP AND SAFETY INJECTION 4

PATH-2 E-3 STEAM GENRA10R TUBE RUPTURE i

}

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JULY 10 & 11, 1986

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II.A.1 EOP DEVEIOPMENT PROCESS 500 W PLANT SPECIFIC FmmanS NOG CF4L GIIIELINES TITLE PRP-S.1 FR-S.1 RESPONSE M NUCLEAR POWER GENERATION /A1WS

,. FRP-S.2 FR-8.2 RESPONSE M IOSS OF CORE SHUTDOWN FRP-C.1 FR-C.1 RESPONSE M INADEQUATE CORE COOLING

FRP-C.2 FR-C.2 RESPONSE M DEGRADED CORE COOLING i

i FRP-C.3 FR-C.3 RESPONSE TO SATURATED CORE COOLING 00NDITIONS l

FRP-H.1 FR-H.1 RESPONSE M IDSS OF SECONDARY HEAT SINK i, FRP-H.2 FR-H.2 RESPONSE M STEAM GENERATOR OVERPRESSURE i PRP-H.3 FR-H.3 RESPONSE 10 IDSS OF NORMAL STEAM RELEASE 4

CAPABILITY FRP-H.4 FR-H.4 RESPONSE M STEAM GENERA 10R HIGi LEVEL j FRP-H.5 FR-H.5 RESPONSE 10 STEAM GENERA 10R IDW LEVEL i'

FRP-P.1 FR-P.1 RESPONSE 10 IAAGINENT PRESSURIZED THERMAL i

SHOCK 00NDITIONS I FRP-P.2 FR-P.2 RESPONSE TO ANTICIPATED PRESSURIZED l THERMAL SHOCK 00NDITIONS l

FRP-J.1 FR-Z.1 RESPONSE 10 HIGH CONTAINMENT PRESSURE l .

{ PRP-J.2 FR-Z.2 RESPONSE 10 00NTAINMENT FIDODING 1

FRP-J.3 FR-Z.3 RESPONSE TO HIGH CONTAINMENT RADIATION j LEVEL FRP-I.1 FR-I.1 RESPONSE 10 HIGH PRESSURIZER LEVEL l FRP-I.2 FR-I.2 RESPONSE TO IDW PRESSURIZER LEVEL FRP-I.3 FR-I.3 RESPONSE TO VOID IN REAC10R YESSEL l JULY 10 & 11, 1986

l; 6 - i i

II.A.1 EOP DEVEI4PMENT PROCESS PA'11I Funnutzutus i

o UTILIZE A STANDARD SET OF SYMBOLS .

o CONVERT MAJOR PROCEDURES 'IO PATH FORMAT l o CONTAINS ALL EOP ACTIONS REQUIRED OF THE MAJOR PROCEDURES l o EXTENDED ACTIONS ARE PERPORMED UTILIZING EPP'S AND FRP'S j AS WELL AS.CSFST'S 1

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! JULY 10 & 11, 1986 e

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, II.A.1 EOP DEVEIDPMENT PROCESS IDGIC SYMBOLS AND PORMAT DECISIN Svamru. - THIS SYMBOL WILL CONTAIN A QUESTION WHICH THE OPERA'IOR IS M ANSWER YES OR MD. THE QUESTION SHALL PERTAIN 'IO A PLANT PARAMETER, SETPOINT,

, SWITCH POSITION OR SYSTEM CONDITION.

1 i

ACTIN SDBOL -

THIS SYMBOL WILL CONTAIN SPECIFIC ACTION OR l VERIFICATION 'IO BE PERFORMED BY THE OPERA'IOR. l

) INFORMATIN & -

THIS SYMBOL WILL CONTAIN INFORMATION 'IO ASSIST

. CAUTIN Sunrw- THE OPERA'IORS IN DIAG 40 SING PLANT CONDITIONS. j 4

1 ABEDW 8maru a -

ARROWS WILL BE USED 'IO DIRECT THE OPERA'IOR FROM ONE PATH PROCEDURE 'IO ANOTHER OR FROM A PATH PROCEDURE 'IO EITHER A END PATH PROCEDURE OR A FUNCTIONAL RES*IORATION PROCEDURE.

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JULY 10 & 11, 1986 .

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b 8 II.A.1 EOP DEVEIDPMENT PROCESS IDGIC SYMBOLS sacasensvusot a vas Acfm afar svusot l 1

- T-0 _

i m PATM-f PATM-TO-GMDPATM AMOW FATWTO-PATM PATM ENTRY SMIT'Afl810W Peerf AfutOW i PRP =

ILS PATM=TS-fuel 47104 RESTORAfteel Afut0W JULY 10 & 11, 1986 l

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wry asse PATH PROCEDURE EXAMPLE

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> ECP-1P- 44 l MV- 2 FM 800:

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TitAftef00 U E SILY I

II.A.1 .

EOP DEVEIDPMENT PROCySS PATH PHIID80PHY EN WY Ilf!O PA W8:

o E-0 AND E-1 INTO PAW-1 o E-3 IN'IO PA111-2 ,

f o E-2 INTO EPP-11 WHEN: ,

o REAC1DR TRIP AND/OR o SAFETY INJECTION, OR o THE CONDITIONS REQUIRING THE ABOVE.

l ADVANTAS8:

o NO MEMORIZATION REQUIRED 'IO ENTER & USE NEWORK o TIES EOP NEWORK 'IOGETHER o EOP NEWORK EASY 'IO SEE EXITS:

o 'ID ANOTHER PATH 1

o TO AN EPP o TO A FRP 0

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I JULY 10 & 11, 1986 i i

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- . = _.. __ ._ _ _ _ . - _ __ _ ._ __. , , . _ . . - . , - _ . _ . _ - .

s .

II.A.1 EOP DEVELOPMENT PROCESS PAlli WIIBS o PAlli WIIES ARE WRITTEN 'IO SUPPORT THE PATH PROCEDURES i

~

c rori FA1TI WIIES ARE THE WRITTEN BASIS FOR THE PATH PROCEDURES AND

, ARE WRITTEN IN 'IDO-COLINN FORMAT o PAlli WIIX8 ARE INTENDED 'IO BE USED DURING OPERNIOR TRAINING ON PATH-1 AND PATH-2 PROCEDURES; 1

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, JULY 10 & 11, 1986 l

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II.A.1 EOP DEVEIDPMENT PROCESS WRITTEN ParinnrunenS l

i o 'IWO-COLUMN FORMAT

o NO ITALICS l o CAUTIONS & NOTES CLEARLY DELINEATED o ALL WRITTEN PROCEDURES ASSOCIATED WITH THE E-0 THROUGH E-3 GUIDELINES HAVE THE EPP OR END PATH PROCEDURE CATEGORY (I.E.

EPP-4 WAS ES-0.1) i o ALL WRITTEN PROCEDURES ASSOCIATED WITH THE FUNCTIONAL RES'IORATION GUIDELINES HAVE THE NAME FUNCTIONAL RESTORATION 1

PROCEDURES AND THE SAME LETTER DESIWATION IS UTILIZED I .E.

FRG-S.1 = PRP-S.1 j (EXCEPT POR THE "Z" SERIES THAT HAS BEEN CHANGED 'IO "J" DUE 'IO i

CONFUSION IN THE CONTROL ROOM (Z & C SOUND MUCH THE SAME) r  !

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. JULY 10 & 11, 1988 4

- - , , , , , . - - . . . - - . ,,n - - - - - - . , . - . , ~ . . , , - - , - - . - , . . -- - . - - , - - - -,,-.-.,n.- . . , - - - , - . - . - - . - - . . - - -

i.- -

j RESPONSE TO NUCLEAR POWER GENERATION /ATWS h STRUCTIONS CONT 4GEhCY ACTIONS

1. VERIFY REACTOR TRIP: MANUALLY TRIP REACTOR. E <

• ROD BOTTOM LIGHTS - LIT REACTOR WLL E TRIP, THEN

• REACTOR TRIP AND BYPASS RUN BACK TURBINE. E BREAKERS - OPEN TURBINE CAN E BE RUN

• ROD POSITION BACK, THEN CLOSE MSIVs AND INDICATORS - ZERO BYPASS VALVES.

• NEUTRON FLUX

- DECREASING l

2.  !

VERIFY TURBINE TRIP - ALL MANUALLY TRIP TURBINE. E STOP VALVES CLOSED l

' TURBINE WLL E TRIP,THEN l RUN BACK TURBINE. E l TURBINE CAN E BE RUN l BACK, .ItBL CLOSE MSIVs AND l BYPASS VALVES. '

h

3. CHECK AFW PUMPS RUNNING:

l

o. MOTOR DRIVEN o. MANUALLY START PUMPS i PUMPS - RUNNING

b. TURBINE DRIVEN b. MANUALLY OPEN STEAM PUMP - RUNNING, IF SUPPLY VALVES.

NECESSARY TWO-COLUMN FORMAT EXAMPLE top-1P-m I arv-2 ru non IEF DWOi are. onir fameNo usE oNLY

DIFFERENCES BETWEEN FR3s AND EPPs FRP EEE i  ;

1 I GUIDANCE FOR CRITICAL SAFETY i

PLANT CHALLENGE TO FUNCTIONS

ORIENTATION SYMPTOM SPECIFIC EVENT 1

PRIMARY ENTRY STATUS TREE PATHS WAY

SUMMARY

- OBJECTIVE 14 j

E0P-1P-73 l E/= 2 ru nor APP. DAW TRMNING M G4.Y

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E0FHP3 I488 0F ALL AC POWER WITHOUT SI REQUIRED

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his procedure provides actions to use normal operational

! systems to stabilise plant conditions following restorstion of I i

AC emergency power.

his procedure along with all the procedures making up the SB(PP E0Ps contain items used to satisfy regulatory commitments j in the FSAR sad Tech Specs.

2.0 OPERA'ttR ACTIONS j

. 1 cat 7FION l 2 i

o Critical Safety Tuction status trees should be monitored for I information only. Function Restoration Procedures should NOT

• 1

• be implemented prior to completion of Step 10. . l o h e loads placed on the. energized AC emergency bus should not

. exceed the capacity of the power source. __

i E: For trended values called out in this procedure, the computer  !

will be the primary indication and the recorder panel shall  ;

be a backup source.

i

! Instructions Resoonse Not Obtained 7

~

, 1. Check RCP Seal Isolation ' .

i Status: . ,

s. RCP seal injection a. E valves open g :

outside.CIGfr position not known, THEN isolation valves - check CSIP status:

, SEUr 1CS-341 1CS-382

1) E CSIP running, THEN 1CS-423 '

go to Step 2.

2) E CSIP NCfr running,

~

THEN close valves before starting CSIP.

. b. RCP thermal barrier b. g valve open g position CCW return CNtff not known, THEN check CCW isolation valve - pump status:

SHUT

1) R pump running, THEN 1CC-251 So to 8t*p 2.

OR II:C-249 2) R pump NOT running, -

THEN close either valve.

9

, , ROP-RPP-002 Rev. 1 Page 3 of 12

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II.A.1 EOP bEVELOPMENT PROCESS WRITTEN PitOCEDURES END PAlli PBOCEDURES:

DESICNATED AS "END" OF PATH ACTION (S)

CONTAIN ALL ES'S, ECA'S AND E-2 PINICTI(MEAL RESTORATIN PEANMRRS3 CONTAIN ALL FUNCTIONAL RES'IORATION GUIDELINES SAME UTILIZATION AS THE WOG "Z" CHANGED 'ID "J" FOR SOUND IDENTIFICATION r

JULY 10 & 11, 1986

\

II.A.1 EOP DEVEIDPMENT PROCESS WITICAL SAFETY FUNCTIN STATUS 11 TEES o SAME IDGIC AS WOG. .

o SIMILAR COLOR SCHEME AS WOG (MAGENTA INSTEAD OF ORANGE) o TREES AND IDGIC ARE MAJOR PORTION OF SPDS o SAME UTILIZATION AS WITH WOG.

J JULY 10 & 11, 1986 I

e -- .- I

,o .

II.A.2 i

! EOP DEVELOPMENT PROCESS ASSIERRn USERS o ALL LICENSED OPERATORS o ALL SROs i

o ALL STAS o ALL SHIFT FOREMEN o OPERATIONS MANAGER & STAFF ALL ABOVE ARE T1tAINED IN M CLAsstanrus AS -WELL AS M SIMULATUEL W W NEW BOP NET 1REK.

JULY 10 & 11, 1986 .

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, l EMERGENCY OPERATIONS CONCEPTS

. ; Normal Operation 4 No

_ . , =

3 M

Yes o Atmormal Operation e,

4 Diagneele i Repair -

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[Yee _ Emergency Operation c

g 5-

,a 1 r l i f O 5 o No 84 , CSF No ,,

Required? Satisfied? :c 8

Optimal h Recovery C  : Yes , , ,

Concept CSF Eve \ntNo Restoration nos Em l ,

meence Concept l

Yes y

l 4 .

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. i

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a 8

EOP NETWORK

SUMMARY

E0P-TP-08 l REV- 2 m.E wo:

NET DWO:

APP. DATE TRAMNO U E ONLY A

II.A.4 .

EOP DEVELOPMENT PROCESS USE OF PROCEDURES PA111 PBOCEDURES:

- PATH-1 ENTERED FIRST

- PATH-1 ONLY ENTRY IN'IO NETWORK DURING NORMAL OPERATIONS.

END PAlli PanrmmnuS (EPP'S)

- ENTERED FROM PATH PROCEDURES, OTHER END PATH PROCEDURES, OR FUNCTIONAL RES10 RATION PROCEDURES. t l

l PIE 8CTIGIAL RESTGRATIGI Pannurunran (PBPs)

- ENTERED FROM PATH PROCEDURES, SPDS, END PATH PROCEDURES AND l OTHER FUNCTIONAL RESPONSE PROCEDURES.

i l

l l

JULY 10 & 11, 1986 1 1

USAGE OF THE "OTAL NETWORK

1. ENTER THE NETWORK AT PATH-1.

l

2. MOVE THROUGH PATH-1 AND-  !

• MONITOR STATUS TREES, OR

• MOVE TO PATH-2, OR 1 1

MOVE TO AN EPP, OR

• MOVE TO A FRP.

i

3. MONITOR STATUS TREES.

I USAGE OF THE TOTAL NETWORK EOP-TP-57 I REV- 2 FILE NO:

RET DWG:

APP. DATE TRAIMNC USE ONLY

USAGE Or T"E TOTAL N ETWORK (CONTNUEDS . .

i

- 4.

~ '

SUSPEND PATH OR EPP ACTIONS IF A HIGHER '

PRIORITY EXISTS. l l

5. VARIOUS ROUTINES AVAILABLE At it.M '

RESTORATION OF A CRITICAL SAFETY FUNCTION FROM RED OR ORANGE. ,

l

6. SOME ADJUSTMENTS MAY BE NEEDED UPON  ;

CONTINUATION OF RECOVERY ACTIONS. '

r l

7. CERTAIN EPPs TAKE PRECEDENCE OVER FRPs.

4 1

TWORK CON EoP-1P-68 l REV- 2 Fu.E por REF 000:  !

APP. DAW TRMNING U E (N.Y j l

_ _ - - . -__ . .. - .. \

II.A.5 l EOP DEVEIDPMENT PROCESS MODES OF USE

l i ONLY PATH-1 IS ENTERED BY ANYONE USING THE NETWORK. THIS IS BY TRAINING AND BY THE FACT THAT THERE IS NO NATURAL OR OTHERWISE i ENTRY POINT INTO THE NETWORK OTHER THAN PATH-1 DURING NORMAL l OPERATION. ,

J THE EOP NE'IMORK IS STRUCTURED SUCH AS 'IO ALIDW THE INTEGRATION OF l SUPPORTING PROCEDURES AND DIRECTS THE USE OF OTHER NE'IWORK PRO-  !

CEDURES. IN ADDITION, ONLY ONE NETWORK PROCEDURE IS IN EFFECT AT  !

ANY ONE TIME. l i

IN ACTUAL PRACTICE THE SRO USES THE PATH PROCEDURES / NETWORK PROCEDURES AND REQUESTS INFORMATION FROM THE REAC'IOR OPERATORS.

THE STA MONITORS THE CRITICAL SAFETY FUNCTION STATUS TREES.

ALL OF THE NE'IWORK PROCEDURES AND BACKGROUND INFORMATION ARE S'IORED IN THE CONTROL ROOM.

ASSUMPTIONS ABOUT STAFF STARTED WITH THE NORMAL CP&L STAFF COMPLIMENT. THE EOP NETWORK HAS BEEN TESTED WITH ONLY TWO PERSONNEL IN THE CONTROL ROOM WITH SATISFACTORY RESULTS.

JULY 10 & 11, 1986

-- -,- - . ~ . . - . . . , . . . - , . , . , _ _ _, ,_. -- . , _ , - _.

II.B EOP DEVEIOPMENT PROCESS .

STRP IEVIATICM DOCEMENT o COMPARES THE ACTUAL WOG WORDING 'IO SHNPP WORDING o 03MPARES THE REQUIRED ACTION o COMPARES THE INSTRUMENTATION REQUIRED o PROVIDES A JUSTIFICATION FOR AHX DEVIATION o ANY DEVIATION WITH A SAFETY SIGNIFICANCE WILL BE BROUGHT

'IO THE ATTENTION OF SIMPP MANAGEMENT' o PROVIDES BENCHWARK POR ANY FITTURE PROCEDURE CHANGES JULY 10 & 11, 1986 I

a SBtfPA00G.EXP Stec Deviation pggtment Rev. O, 28 MAR 85 SHIPP Procedure 9/ Step EPP-5 / 19 Rev. O NOG Procedure #/ Step ES-0. 2 / 19 Rev. HP-REV.1 FINFL

1. SHtPP step 19

19. Continue BCS Cooldown To Cold Shutdown

a. When at least one BCS cold

~

leg temperature is less than 2500F, M rack out all but one CSIP breaker.

2. WDG step 19

19. Continue R3 Cooldoest To Cold Shutdoun 3a. Justification of Differences step I-19: Plant-specific SI pump lockout included.

f

36. Explanation of Footnote Values None Page 95

me@PMY: IKP Steo Dmriation Mmt Ber. O, 28 MAR 85 l

4. SHt@P Instrumentatior/ Control Requirenents Instrumentation:

RCSI12 o RCS cold leg wide range temperature indication:

[RCS TEMPERATURE]

A 0%D LBG TEMP TI 410.1 SB

[RCS TEMPERATURE]

B 00LD LEG TEMP TI 420.1 SB

[BCS TEMPERATURE]

C 02D LBG TEMP TI 430 SB

[RCS TEMP]

TR 410 RCSIll

o RCS hot leg temperature indication

[RCS TEMPERATURE]

A IDT IAG TEMP TI 413.1 SA

[RCS TEMPERATURE]

a aar IaG TEMP TI 423.1 m

[RCS TEMP / PRESS]

ta 413 I

[ICS T9tPERATURE]

C IDT LEG TEMP TI 433 SA RHRI2 .

o Instrumentation for RHR systen operation:

[RCS PRESSURE]

WIDE RANGE PRESS PI 402.1 SA

[RCS PP N RE]

- WIDE RANGE PRESS PI 403.1 SB

[03EONENT 002ING MTER]

RER HX A OUT FI 688A1

[03tPOtENT CDCLING RTER]

RHR HX B OUT FI 68R1

[RCS PRESSURE] 1 WIDE RANGE PRESS PI 440 '

Page 96

onep/lhatr. EMP st>=n Deviation hirat Rev. O, 28 MAR 85

^

[RCS PRESSURE]

WIDE PAN 2 PRESS PI 441 .

[RMP A)

RHR REP A DISCH PRESS PI 600A

[RMP A]

HK A ER FLOW FI 605Al

[RMP B]

RER RMP B DISCH PRESS PI 60G5

[RMP B]

i HX B HDR FLOW FI 6051B1

[RHR]

IAN HEAD SI TBhIN A TO CCED LEG ISI-340 SA (888&)

[RHR]

IIM HEAD SI TRhIN B TO CCED LEG ISI-341 SB (8882)

[RHR]

I4W HEAD SI TRKINS A & B TO HOT IBG VLV 18I-359 SA (8889) j [RER]

I4N HEAD SI TRIN A 3D BDT IAG QIOSEKNER 3SI-326 SA (8887A)

[RER]

4 I4M HEAD SI TRIN B TO IE7f IAG CROSS 0ER 3SI-377 B (8887B)

EER RMP A-SA 4

EBR RMP FSB CUCI54 l o CSIP breakers status indicaticm QIhRGDEVSI RMP NtEARER JVC-SA {

CHARGINWSI RMP HREAKER WC-NB C RBGIN WSI RMP A-SA

- cmRGINWSI RMP B-SB 4

, smWPAry: ECP stao Deviation h=nt Rev. 0, 28 MAR 85 Control RERCl o RHR system control switchets:

.- RHR LETDOWN HCV-142 RHR HEAT EXQ9HER A OUEET FIOi 00tE'RCL 1R&30 (BCV 603h)

RER IEAT EKQUNER B 00HET FIDf (DemL 1R&46 (BCV 6038) 4 RER HEAT EKOUNER A NPASS FIDi 00tML FCV-605A RHR IEAT EKQUEER B NPASS FIDW (Dt@BCL FCV-605B 3

RER RMP A-Sh RER REP B-SB CCN RMP A-Sh COf RMP B-SB IOf HEAD SI TRIN A 'to GID IBG 1-SI-340 sh (888th)

IOf IEAD SI TRAIN B 'to GID IAG 1-SI-341 m (8881B) 3 IOf HEAD SI TRIN A 'E0 IDF LBG CROSS 0UER 1-SI-326 m (8887A) '

i i IOf IEAD SI TahIN B 'to IDF IBG OCSS0WER 1-SI-327 m (8887B) '

M:S IOCP A TO RER RMP A-R IIIIF1JB -

i M3B IGN A TO RER RMP A-4R 1RII-2Sh RCS IOCP C TO RER RMP FSB 1R8-396B R3 IDOP C TO RER RMP IHB IRB-40Sh CYCC34 .

l o CSIPs breaker controls:  !

l

, - IOCAL

?

5. WOG InstrumentatiorVControl Requirements Instrumentation: o RCS cold leg tagerature indication o -RCS hot leg tangerature indiation o Plant-specific instrumentation to monitor RCS cooldoun

. using the RHR System Page 98

- - - _ _ _ - - w - r - , - . c -,, , e , , -- , e--e

SEWPA10G BCP steo Deviation Doctanent Rev. 0, 28 8UR 85 l

Controls o Plant-specific controls to cool down the BCS using RHR Systemi

6. Justification of InstrumentatiorVControl Diffierences Plant-specific step tran control of CSIP breakers frcan WOG Step 15 Plant-specific step using CSIP breakers indication was transferred frcut M)G Step 15.

t l

l

II.C 1

EOP DEVEIOPMENT PROCESS TASK ANALYSIS

- WOG SRTA CONVERTED 'IO REY.1

~ ~ ELEMENT TABLES AND SEQUENCE MATRIX CONVERTED 'IO "SHNPP SFTA"

- BREAK ELEMENTS INTO DOWN IN'IO BEHAVIOR ELEMENTS = (ACTION &

INFORMATION REQUIREMENTS - DETAILS)

- SUMMARIZE ACTION AND INFORMATION REQUIREMENTS

- VERIFICATION OF TASK PERFORMANCE CAPABILITIES

- VERIFICATION OF AVAILABILITY

- VERIFICATION OF SUITABILITY

- VALIDATION OF CONTROL ROOM PUNCTIONS CP&L ME1mnIDGY ArinmPTED AT ALL T15tBE SITES BY NBC.

1 JULY 10 & 11, 1986

II.D EOP DEVEIDPMENT PROCESS V & V PROGRAM

1. REVIEW OF PAST WOG V & V ACTIVITIES REVIEWED CALLAWAY VIDEO TAPES REVIEWED SEABROOK RESULTS DOCUMENT INCORPORATED AREAS OF CONCERN AS THEY APPLIED 'IU CP&L o USE OF PROCEDURES o "J" VS "Z" o VARIOUS DISOONTINUITIES 1

-t l-JULY 10 & 11, 1986 1

e O II.D EOP DEVELOPMENT PROCESS V & V PBOGRAM

2. OLD SERIPP SIMULATOR o PERFORMED OVER 50. HOURS FOR EOP TEAM TO GET DIRECT EXPERIENCE o PERFORMED OVER 120 HOURS WITH 'I1YO TEAMS h

- EACH TEAM HAD AN EOP SESSION FOLIDWED BY A " TAPED" VERBAL DEBRIEFING ,

- SECOND WEEK OF TRAINING WAS VIDEOTAPED o OPERATION CX)hMENTS WERE CATALOGUED AND ACTED UPON o OPERATOR PROBLEMS WERE ACTED UPON JULY 10 & 11, 1986

. s O II.D EOP DEVEIOPMENT PROCESS V & V PROGRAM

3. TABLE 'IOP EXERCISES

- APPROXIMATELY 20 HOURS PER CREW WAS SPENT PERFORMING IN-CLASS EXERCISES

- ALL CATEGORIES OF EVENTS ARE PERFORMED

- PROBLEMS ARE HANDLED AS THEY OOCUR 1

i I

JULY 10 & 11, 1986

i

< . o l l

II.D EOP DEVELOPMENT PROCESS Y & V PBOGRAM l

4. SIMULATOR - SEABROOK o PERFORMED 40 HOURS WITH ONE TEAM EVALUATED EOP/ PLANT RESPONSE EVALUATEb EOP/EAL INTERFACES o RESULTS FROM EVALUATION RESPONSES WERE WITHIN EXPECTED RANGES EOP/EAL INTERFACES WERE SLIGHTLY MODIFIED 'IO ADJUST FOR ACTUAL USAGE e

JULY 10 & 11, 1986 1

II.D EOP DEVEIOPMENT PROCESS V & V PROGRAM

5. NEW SE9EPP SIMULA'IOR

^ -

-PERPORMED EXTENSIVE EOP CHECKOUT DURING ACCEPTANCE PROGRAM

- SIMULATOR CONTROL ROOM IS ESSENTIALLY THE SAME AS SIBIPP; SAME CONTROL BOARD LAYOUT

- OPERATOR TRAINING USING NEW EOPs IS BEGINNING

)

JULY 10 & 11, 1986 1

II.D EOP DEVELOPMENT PROCESS -

V & V PROGRAM

6. CONTROL ROOM WALK THROUGH DONE DURING CRDR PHYSICAL PROCEDURE WALK THROUGH IN THE ACTUAL CONTROL

, ROOM MOST PROCEDURES UTILIZED; ALL CONTROLS UTILIZED SCENARIOS SELECTED SO AS TO INSURE COMPATIBILITY (EOP/ OPERA'IOR/00NTROL ROOM) 1 i

f l

JULY 10 & 11, 1986

, ~ <

II.E TRAINING PROWAM POR 81tMP1tBIATIC EMERGENCY OPERATING PROCEDURES PHASE I PHASE II NEW EOP PHASE III SPECIPIC BOP 8 SPECIPIC EOPS DEVEIDPMENT (CLASSROOM) ( SIMULA10R)

PROCESS

_1

, I I MODULE I MODULE IA i . I MODULE II ISODULE III IIODULE IV MODULE V l EOP PRE NUREG RIODULE VI WESTINGHOUSE NEW BOP DE8mIPTION USING NEW BACKGtOUND 0899 USING NEW OWNERS GROUP APPROAct OF NEW EOPS EOPS EOPS (EXERCISES) (EXERCISES)

USED AS BACKGIOtmlD POR SIMULA10R TEAMS. USEB POR COLD AND IM LICENSE CLASSES MOST OPERATORS WERE PREVIOUSLY LIG NSED OPERATORS. .

4 o TRAINING MATERIAL - AS PREPARED BY EOP DEVII4PIENT TEARI o SHNPP TRAINING CONVERTS INPITT 11tAINING IIATERIAL INTO IX81 RED PORM/PORMAT o SHNPP TRAINING MAINTAINS & UPIMTES LJP 11AINING IIATERIAL o EACH LICENSEE RECEIVES A 9 WEEK CERTIFICATHal TEMI o ADDITIONAL SIMULA10R TRAINING FOR BAOI LICEll8EE OVER AND ABOVE THE 9 WEEK TERid.

JULY 10 & 11, 1988 8

• ll

e 9 II.F EOP DEVEIDPMENT PROCESS '

O(XfTBOL BOOM IESIN REVIEW (CRIR) l

- CRDR UPDATED 'IO NUREG-0700 i

- CONTROL ROOM SURVEYS UPDATED 'IO NUREG-0700 i

- SFTA CONDUCTED

- VERIFICATION OF TASK PERFORMANCE CAPABILITIES CONDUCTED

- VALIDATION OF CONTROL ROOM FUNCTIONS CONDUCTED 1

- HEDS DISPOSITIONED/OORRECTED

- FINAL

SUMMARY

REPORT SUBMI'ITED 'IO NRC - SEPTEMBER 1985

- AUDIT WITH NRC ON CRDR - APRIL 1988

- SER 'IO BE UPDATED BY NRC IN NEAR FUTURE 1

e 1

JULY 10 & 11, 1986

- - ~ - , - - - . - - , - - - - + - - - - - - - - - , - ,a-, ,

e

II.G EdP DEVELOPMENT PROCESS WRITERS EJIDE o STAND ALONE DOCUMENT o DELINEATES THE FORMAT & CONTENT OF WRITTEN PROCEDURES PATH PROCEDURES o GUIDANCE ON WRITING o GUIDANCE ON REVISING o USES AS MUCH PLANT NORMAL PROCEDURE WRITING INFORMATION AS

! POSSIBLE o ONLY DOCUMENT 10 EMBRACE THE TWO-COLUMN FORMAT AT CP&L.

e v

l JULY 10 & 11, 1986 l

l l

1 l

i i

Enclosure 3 REVISED WRITER'S GUIDE 9

i d

e