ML20235X246

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Power Ascension Program
ML20235X246
Person / Time
Site: Pilgrim
Issue date: 10/15/1987
From:
BOSTON EDISON CO.
To:
Shared Package
ML20235X235 List:
References
PROC-871015, NUDOCS 8710190267
Download: ML20235X246 (33)
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BOSTON EDISON COMPANY i

PILGRIM NUCLEAR POWER STATION' Power Ascension Prograa:

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W POWER ASCENSION PROGRAM T

' Table of Contents.

n Page I.

' Introduction-1 4

' II. -

Power Ascension Logic Plan

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Bases for Logic Plan 2

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Summary Description of Power. Ascension 4

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> - III. -

. Management l' Assessment Points

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-and NRC Approval Points A.

Sources of Assessment ~ Point and Approval Point' Requirements 8

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. Des:'ription of Power Ascension Assessment' Points 9

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Description of Approval Points 14

'IV.

'Startup Organization A.

Operations section 15 B.

Post-Refueling / Modification Outage Test Organization 16 C.

Nuclear Organization l

Support for Operations 17 l

D.

Oversight and Assessment Team 17 j

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Introduction This document describes the Power Ascension Program for the f

restart of Pilgrim Nuclear Power Station (PNPS)-from the current i

outage (RFO-7).- The Power Ascension Program is the final phase of the PNPS Restart Plan and.is the mechanism by which Boston Edison will demonstrate the effectiveness of its programs, plans i

and actions.

This program description should be read in conjunc-j tion with the Restart Plan, dated July 30, 1987, to understand J

the scope of programs, plans and actions undertaken by Boston Edison to assure safe and reliable restart and continued opera-i

' tion.

The program description is organized to describe the Power Ascension Program in the following sequence:

o Logic Plan o

Management Assessment Points and NRC Approval Points o

Startup Organization o

Management Assessment Process The management assessment description includes Boston Edison's process both for confirming readiness for initial criti-cality and for oversight and assessment during power ascension.

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This assessment process includes close monitoring and evaluation of personnel and plant performance by Boston Edison nuclear man-agers, with personal observation by senior nuclear managers.

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II.

Power-Ascension Logic Plan LBoston Edison has developed a power ascension logic plan fore j

theitesting;; restart'and power ascension-from RFO-7.-

The bases for this;1ogic' plan and the sequence of power. ascension steps and o

associated-tests are described in this section.

The management assessment process, including the management Assessment Points,

.isfintegrated into.the logic plan.

A. ;, Bases for Loaic Plan-The power ascension logic plan is based on and complies with

.the PNPS Technical Specifications.

In addition, the' plan con-siders prior' power ascension experience at.PNPS, specific testing I

requirements.for the work accomplished in RFO-7,' personnel and sequipment' performance evaluation, Nuclear Regulatory Commission

.(NRC) approval points and prior relevant nuclear industry ex-l perience.

Power ascension experience from prior PNPS refueling outages is incorporated into the power ascension logic plan.

The plan utilizes the sequence of power ascension that was proven success-ful in'RFO-6.

In addition, checklists for plant operational condition changes, which were first used to track the completion l

Hof designated RFO-6 milestones leading to restart during the

-recirculation' pipe replacement work, have been expanded and re-

' fined for use during RFO-7 power ascension.

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Several specific hardware performance problems led directly to the plant shutdown that resulted in RFO-7.

Therefore, in the course of power ascension, special tests will be conducted to verify proper operation of that hardware under certain plant L

operating conditions.

These special tests are to confirm:

l (1) the main steam isolation valves' ability to open with normal differential pressure across them; (2) the adequacy of the monitoring method and procedure in the event of leakage from the reactor to low pressure i

portions of the Residual Heat Removal System; and 1

(3) that main steam isolation valves remain open during reactor depressurization after the mode switch has been shifted from "Run" to "Startup".

An additional test unique to this startup is a shutdown-from-outside-the-Control Room which will be conducted after successful performance of the three special tests.

The power ascension program includes management assessment periods, each of which end in an Assessment Point, during which management can systematically review earlier performance evalua-tion results, assure itself that corrective actions taken as a result of performance evaluations have been effective, and deter-mine that the plant and its staff are ready to proceed beyond each designated Assessment Point in the power ascension process.

These periods will also be used to conduct required training of recently licensed Reactor Operators.

The process for conducting performance evaluations of PNPS personnel and equipment through-out each period between the Assessment Points and the process for performing management assessments of the results of those perfor-3

V mance evaluations ~at each Assessment Point are described in Sec-tion.V.

i In response to the NRC request in the August 27, 1986 letter on the _ subject of Confirmatory Action Letter (CAL) 86-10, Boston l

Edison has proposed three NRC approval points, each of which

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require oral approval'from NRC Region I for continuation of-the power ascension.

These approval points are described in Section III.

Finally, Boston Edison has considered prior relevant nuclear industry. experience with restart and power ascension programs.

Boston Edison has considered the specific plant circumstances I

under which other restart and power ascension programs were de-veloped and conducted to distinguish those features in other plants' programs which should apply to PNPS restart from those features which were plant-specific and'should not apply.

B.

Summary Description of Power Ascension A sequence of power ascension steps and associated tests brings the plant from approach-to-criticality to 100% power.

This sequence is depicted in Figures 1 and 2.

Figure 1 is a diagram of the testing, training, assessment and power ascension steps.

A portable auxiliary boiler is being used to perform HPCI 2 -

and RCIC testing at 150 psig prior to beginning power ascension.

Tests satisfactorily completed using the auxiliary boiler will be i

deleted from the initial power ascension sequence depicted on 4

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page 1 of Figure 1.

Figure 2 is a plot of approximate power levels-during the specified tests, training and assessments.

As illustrated in Figure 1, the PNPS reactor will be taken critical following Boston Edison and NRC approval of restart.

As the plant is slowly heated and pressure is increasing, a number of routine startup tests and checks of plant equipment are con-ducted.

Some of these tests, instrument calibrations, and checks are indicated on Figure 1.

n During initial reactor heatup, the main steam isolation valves will be tested to verify that they open with normal dif-ferential pressure across the valves.

This test is designed to verify correction of one of the plant hardware problems addressed in' CAL 86-10.

Beginning with initial reactor heatup and continuing throughout the power ascension, Boston Edison will monitor the low pressure portions of the Residual Heat Removal system for in-leakage from the reactor.

This action addresses a second hard-ware problem from CAL 86-10.

At approximately 27% reactor power, Boston Edison will ini-tiate a normal shutdown, shift the mode switch to startup and decrease reactor pressure to about 800 psig to confirm that the main steam isolation valves remain open during reactor depres-surization after the mode switch is shifted from "Run" to " Start-up".

This test addresses the third problem addressed in CAL 86-10.

Following successful completion of the above testing, Boston 5

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Licient decay heat to conductfthe required shutdown-from-outside :

B Jthe-Control'. Room' test.'

This period of operation Will.also be l'

used1for: operator. training:and management assessment of perfor-manceLpriorotoJconducting the required shutdown-from-outside-the-e

' Control Room test ~.

Following recovery from the shutdown. test, the scram set-y

. point'will.be raised to the.70% power level and~ reactor powers L

will'be graduallyfincreased to approximately 50% as normal test-ing:and' calibration are. conducted.

Boston Edison management will assess performance of the plant and personnel at'this. point be-fore' permitting the power ascension to continue above'the 50%

power level.

.The scram setpoint will then be raised'to'95%' power to.per-

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mit,the, reactor to be brought to approximately 75% power.

During this time, reactor engineering tests comparable to those per-l I

formed at'50% power, as well as turbine valve tests and main j

steam isolation: valve' tests, will b'e conducted.

Boston Edison q

management will assess the performance of the plant and personnel

,.at:this point ~before permitting the power ascension to continue above the 75% power level.'

The scram setpoint will then be raised to its normal 120%

level and'the reactor will be brought to 100% power.

Routine reactor engineering tests will be conducted at this power level

'E ltofcomplete the power ascension process.

Boston Edison manage-ment will assess the performance of the plant and personnel con-6

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' firming satisfactory completion of the Power Ascension Program and,the: effectiveness L of the programs, plans and actions for con-u tinuedfoperation..

9-ThisEsequencenofirestart: tests for.startup from RFO-7.is documented in PNPS:. Nuclear Operations Department Temporary Proce-

. dure 487-114. ! Major' elements.of the procedure are the summary description,-the cross-reference of the tests,'and the Power-

Ascension' Test Checklist.

The summary description of the tests

.is intended for general:information.

The specific details or criteria for actually conducting the. listed tests will be incor-l

.porated-in the individual PNPS operating procedures which are referenced-in Temporary Procedure 87-114.

The Power Ascension i

' Test checklist will'be used to document acceptable completion.of-I i

a' test.

Figure.1,.the Power Ascension Plan, will be used tiy the Startup Test Manager ~to develop daily testing and power ascension schedules, which will be approved by the operations Section Man-ager.. In addition, a plan of the day will be approved by the Station Manager that will co-ordinate the power ascension testing with theitesting. required by the Master Surveillance Tracking Program.=

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? Management Assessment Points ih, J

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and NRC ApprovalLPoints-jg

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BostonlEdison'will assess" personnel and equipment perfor--

4mancela't;several points-during the: power' ascension.

The process

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'for assessment prior.to' initial criticality will.have been.com-K A

'pleted prior to requesting-; restart-and'is discussed in Section.

I LV.Ai LThe sources'ofyBoston Edison Assessment, Point and NRC ap-proval point' requirements,;the actual Assessment Points, and the 1

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proposed Approval 1 Points for power ascension are described in' t

Im this'~~section..

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' Sources of' Assessment Point and Acoroval Point Requirements

.'In the course-of'its.self-assessment,. Boston' Edison's senior q

s-nuclear'managementihas. identified a need for a number of pre-

' determined' Assessment Points for review of personnel and equip-

.menttoperational' performance.

These Assessment Points occur at logical intervalsEin'the. power. ascension sequence.. Senior man-

.agement' approval willLbe obtained before power ascension will be

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permitted'to. continue.beyond each Boston Edison management as-sessment' point.

The.NRC, in-its' August 27, 1986 letter, requested that the

'PNPS power ascension program include " hold points at appropriate stages such~as. criticality, completion of mode switch testing, land'at. specific milestones during ascension to full power."

In response to this request, Boston Edison has proposed three NRC l

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. approval. points which would require oral authorization from NRC' Region 1I before PNPS.can' continue power ascension.

BE Description.of Power Ascension Assessment Points Four Boston Edison Assessment Points are planned during the

, Power Ascension Program.

Examples of the types of activities that willLbe' conducted'during each of the evaluation periods are described.. At each Assessment Point, management will review results of observations, performance evaluations, and any correc-tive actions taken for personnel, equipment and procedures during the preceding period of. power ascension.

Further, management will' identify additional corrective actions as required, and will

confirm readiness to proceed with the next period of power ascen-sion.

Assessment Point 1

.The first Assessment Point will be after recovery from test-1 ing to confirm that the main steam isolation valves remain open during reactor depressurization after the reactor mode switch is shifted from "Run" to "Startup" and with the plant conditions established for commencing the shutdown-from-outside-the-Control Room test.

Assessment Point 1 appears on page 2 of Figure 1.

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e During the period between' initial' criticality and Assessment

.Po ni t'1, personnel and equipment performance will be evaluated.

TheLtypes of activities and tests that will be undertaken during this period include the following:

o HPCI and RCIC testing at 150 psig and at rated pres-sure,. requiring coordination of activities by the oper-ations, maintenance and radiological controls person-nel; and o

. Reactor vessel heat-up, and the bringing of equipment on line.to support increased power, including the con-

. duct of operations, maintenance, technical and radiolo-gical control duties.

1 Evaluations of activities such as those described above will enable management to assess the performance of personnel in a variety of disciplines, as well as the working interface and coordination between the. disciplines.

Management will conduct this assessment and determine.readi-ness to proceed with power ascension while at a power level I

between 20% and 35%.

This range was selected for calibration of j

i the nuclear instrumentation and to build up sufficient decay heat j

to properly perform the shutdown-from-outside-the-Control Room f

test. 'The " Management Assessment" period is depicted on page 2 of Figure 1.

During this assessment period, newly licensed Reac-tor Operators (individuals receiving licenses after May 1987) on each operating crew are scheduled to receive 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of operat-j ing experience.

Depending on the shift rotation schedule, this i

.i assessment period is scheduled to be 8 to 12 days in duration.

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d' AssesEment Point 2 The second Assessment Point will be after the reactor en-gineering tests at nominal 50% reactor power and prior to moving the scram setpoint above the 70% power level.

Assessment Point 2 appears on page 3 of Figure 1.

Between Assessment Points 1 and 2, a number of tests and plant activities, such as bringing equipment on line to support increasing power, will provide an opportunity for evaluation of equipment and personnel performance.

The types of activities and tests that will be undertaken during this period include the following:

o Shutdown-from-outside-the-Control Room test, requiring shutdown of the reactor from the dedicated alternate shutdown panels in the Process Buildings while main-taining a qualified crew of operators in the Control n

Room.

o Condensate domineralizer operation, as necessary, which requires:

(1) plant chemistry personnel to sample, analyze and provide water conductivity status; and (2) placing the additional condensate demineralized units in service.

The " Management Assessment" period immediately prior to Assessment Point 2 is shown on Page 3 of Figure 1.

This assess-ment period is scheduled to be 8 to 12 days in duration to permit newly licensed Reactor Operators on each operating crew to re-ceive 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of operating experience.

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Assessment Point 3 y

1 Boston Edison.has selected a third Assessment Point after completion of the reactor engineering tests at no inal 75% power levelandpriortomovement.ofthes}cramsetpointabove95%

power.

Assessment Point 3 is depicted on page 3 of Figure'1.

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'Many of the plant activities between Assessment Points 2 and~

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3 are virtually. identical to those between Points 1 and>2 because j

the reactor engineering tests conducted at the 75% power level are largely a repetition of those conducted at the 50% power level.

During this period, additional plant equipment will be placed in service as necessary to support the higher power lev-els.

The types of activities that will be conducted during,this I

period include the following:

o Placing the additional condensate demineralized units

'in service;

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o operation of the Augmented offgas System; o

Placing the third reactor feedwater pump in servich; j

and Routine sur.v'elllances and preventive maintenance, chem-o istry analyses, and radiological surveys.

The " Management Assessment" period immediately prior to Assessment Point 3 is depicted on page 3 of Figure 2.

During i

this period, newly lic 41 sed Reactor Operators on each operating crew are scheduled to receive 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of operating experience.

Depending on the shift rotation.uchedule, t?? s assessment period i

is scheduled to be 8 to 12 days in' dura, tion,

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Assessment Point 4 l

J At' nominal 100% p-ower, the' final series of reactor engineer-

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i ing tests.and calibrations'in the power ascension program will be performed.. Evaluations conducted between Assessment Points 3 and 4 will largely focus on routine operating activities such as coordination of surveillance, anticipation and correction of j

l problems, and the conduct of routine and preventive maintenance.

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In addition, operating activities such as recirculation flow adjustments and control rod manipulations to counteract xenon

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buildup and achieve 100% power provide an opportunity to evaluate the coordination between operations personnel and reactor en-gineers.

I Results from these reactor engineering tests, as well as the additional performance evaluations, will be assessed by Boston l

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1 Edison senior management at the fourth and final Assessment

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l Point.

Boston Edison management.will assess the performance of

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the plant and personnel confirming satisfactory completion of the Power Ascension Program and'the effectiveness of the programs, plans and actions for continued operation.

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Description of Acoroval Points I

i As shown'on Figure 2, Boston' Edison proposes three NRC Ap-l proval Points.

The first NRC Approval Point is immediately prior to criti-cality.

In accordance with CAL 86-10,. dated April 12, 1986, NRC Region I authorization is required for PNPS restart.

The second NRC Approval Point is proposed after recovery from testing to verify that the main steam isolation valves re-main open during reactor depressurization after the reactor mode switch is shifted from "Run" to "Startup" and with the plant conditions' established for commencing the shutdown-from-outside-the-Control Room test.

The August 27, 1986 NRC letter referen-cing CAL 86-10 indicates that completion of this testing is an appropriate stage for NRC approval to continue power ascension.

Accordingly, Boston Edison proposes this as the second NRC Ap-

' proval' Point.

The third NRC Approval Point prior to full power operation

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is proposed after completion of the reactor engineering tests at nominal 75% power level and prior to movement of the scram set-point above the 95% level.

At this point, results from the reac-q l

tor engineering tests and operator training at the 50% and 75%

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power levels can be reviewed to confirm readiness to complete power ascension.

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l-IV..Startup Organization j

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1 The PNPS stat..p~ organization.forireturn to operation from'

.j R RFO-7tishcomprised of-.~four elements as follows:

(1); the' Operations Section;.

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'(2) lthe post-refueling / modification.

Ab outage. test organization; (3): the. Nuclear Organization support'for operations;fand (4) the-oversight and assessment team.

-The.first'three elements are the normal line organizations that

.would support restart =from any complex and extended PNPS outage.

The fourth element'is.an expansion of Boston Edison's management oversight processes-to increase observation and evaluation of major evolu'tions during power ascension, to conduct periodic management assessments of evaluations performed throughout this period, and to' confirm readiness to proceed.

A.

-Operations Section

.The Operations Section is the normal line organization for restart from-an outage such as RFO-7.

Plant startup from any l

protracted and complex outage requires that additional people be available on shift to properly execute both the routine and out-l

. age-specific tests, as well as respond to operational problems

.that may occur after a long shutdown.

In recognition of these factors, Boston Edison has elected to utilize a four-shift rota-15

tion.for the operators.' The four-shift rotation will' enable assignment-of the necessary number of operators, without incur-a

' ring excessive and unscheduled overtime.

The four-shift rotation twill also enable assignment of an~experiencedLSRO, designated'as the " Assistant Watch-Engineer" to provide field oversight and on-the-job training for the equipment operators.

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'The actual operating organization ~as depicted in Figure 3

consists of:the operations Section Manager and, in descending order, his chief Operating Engineer, the Watch Engineers for each-

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shift, and'the shift operating crews.- They. report to the Station LManager.

At the completion of the power ascension program and when a sufficient number of Reactor Operators are fully qualified, a transition to a six section watchbill will occur.

This six sec-tiontwatchbill is intended to provide a nominal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week for ebchioperating crew and address watchstanding, training and extended absence coverage.

B.

Post-Refueling / Modification Outace Test Organization

. Boston Edison is following its normal practice to use a

,, post-refueling / modification outage test organization for restart from a complex outage.

The shaded boxes on the chart in Figure 3 show this organization.

Boston Edison's experience is that this

. test organization's support to the Operations section has con-tributed to the successful control of startup from an extended 16 l

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and complex outage.

The Technical Section Manager is the Startup Test Manager during restart and power ascension.

As such, he is responsible for. directing and coordinating the efforts of the Shift-Test Coordinators, Reactor Engineers, Computer Engineers, Test Engineers, Turbine Test Engineers, and Test and Turnover personnel, for preparation of daily power ascension test sched-

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i ules, and for independent review of test results.

C.

Nuclear Organization Support for Operations The restart from RFO-7 will be achieved with the normal plant support functions, e.g.,

Nuclear Engineering, Quality Assurance / Quality Control, Security, Fire Protection, Planning / Scheduling and Cost Control, Technical Support, and other nuclear organization groups.

Due to the complexity of this outage, there will be a Shift Maintenance Representative, as j

shown on Figure 3, assigned to provide 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage for main-tenance coordination.

1 D.

Oversicht and Assessment Team During restart and power ascension from RFO-7, an additional organization will provide oversight of power ascension.

A de-scription of the oversight and assessment team is provided in Section V.

B.

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.VL Managemebt Assessment Process W 8 b

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' iThe: management assessment process ldurihg: rest' art and.powerE m

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TasbensionTwillifocusjon?managementkoperational,. plant and: equip-w h ;.

ment'l performance. - Senior. Boston 1 Edison. Nuclear. organization-g

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managers'will.personall'y?observefmajor. evolutions during restart.

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'and?po.wardascensioniand willLassess-personne11and: equipment per-1,

. form'ancelat:each of the fouridesignate'd'. Assessment Points'to et confirm. readiness;for continued operation.

AsLusedLihfthisiprogram, the-following terms are defined:.

evaluation

' processes.used-by! peer evaluators, line management-cc ' '

=andlindividual'membersjof the oversight and as-sessmentLteam throughout the Power Ascension Pro-

- t up gramfto observe. specific. activities and evaluate the-performance.

. assessment" processes used by the line management or oversight i

and-assessment team during the designated assess--

ment period prior to each Assessment Point to review.the,results of prior PNPS activities, in-cluding prior performance evaluations-and to de-cide whether the personnel'and plant are ready for continued operation.

l A.

Readiness ~ Assessment for Initial-Criticality i

The readiness assessment process for initial criticality

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l will consist of five major elements.

First, the prerequisites

.for. criticality.and the responsible individual for each prerequi-

' site will be identified.

As the second step, the responsible i

-individuals and their line management will certify that the re-start prerequisites are closed.

Then senior management will t

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'reviewsprerequisite closure to assure that the actions taken-

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i fully. address the identified issues and-that the items are pro-perly. closed.

Fourth, senior management will conduct an assess-mentLof the effectiveness of the' programs, plans and. actions for

- restart.

' Senior management will then. decide whether to recommend restart to the Boston Edison Board of Directors.. Finally,= after Boston Edison Board approval, NRC approval to restart will be i

. requested.

l Restart prerequisites'for criticality include the following:

(1) the Restart Plan, including:

(a) the Restart Plan Appendix 10 Restart Regulatory Responses;-

(b) the restart actions in the Material Condition Improvement Action Plan (MCIAP);

(c) the restart actions in the Radiological Action

' Plan (RAP); and (2) the Plant Operating Condition Change Checklist Number 6 j

for pre-critical tests and plant startup, including a review of plant systems status by the Systems Group and approval of the checklist by Boston Edison's Operations Review Committee.

The seven bases for the Boston Edison management assessment of readiness for criticality and restart as described in the 4

Restart Plan, Chapter V, are as follows:

(1)

Management will have executed its plans for RFO-7 work.

(2)

Staffing levels will be adequate to support safe and reliable restart and continued operation, and a plan for orderly transition from the restart organization to l

a long term organization will be established.

l (3)

Pertinent performance indicator trends for RFO-7 work, including backlog work, will show that management con-I trol has been established.

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J' (4)- Self-assessments will have been performed and action plans 1 established, includingicomprehensive action plans

. addressing-materia 1' condition-(including maint'enance l

and. radiological' controls), to. assure that' management.

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. control:will. continue, j

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Regulatory 11ssues will have'been addressed.

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Systems group reviews will have.beentcompleted and j

restart: actions identified from those reviews will-have f

e been closed.or specifically scheduled in the approach to startup.

-(7).

The1RFO-7. Power Ascension' Program,. including NRC holdT,

points, will have been' established.

The readiness assessment: process has been structured tnrough the i use of the: restart prerequisites and bases for assessment to assure the integrity of the-results.

B.

Oversight and Assessment of' Power Ascension Six senior level managers in the Nuclear. Organization will serve as-the oversight and assessment team during power ascen-sion.' These senior managers will observe personnel'and equipment performance during the Power Ascension Program and will perform 1

. assessments.at each of the Assessment Points to confirm readiness for continued operation.

The team members are:

(1) the Senior Vice President - Nuclear;

]

(2) the Vice President - Nuclear Engineering and Quality Assurance; (3) the' Executive Assistant to the Senior Vice President - Nuclear; I

(4) the Director of Planning and Restart; 1

i l

20 l'_-

L.

(5) the Nuclear Engineering Manager; and (6) the Quality Assurance Manager.

Direct support to the oversight and assessment team in per-forming assessments of plant and personnel performance will be provided by peer evaluators.

In the area of operations, for ex-ample, individuals assigned as peer evaluators will have current or previous BWR Senior Reactor Operator licenses or certifica-tions.

These individuals will be' assigned to shift rotation to act as operations observers and report the results of their ob-servations and evaluations to the oversight and assessment team.

Other peer evaluators will be assigned to support observa-l tions in areas such as radiological controls (health physics) and maintenance to support the oversight and assessment team as necessary.

These peer evaluators will observe specific plant evolutions or support activities of interest and report the re-sults of their observations and evaluations to the oversight and assessment team.

This performance evaluation process is designed to retain the flexibility to respond to changing conditions.

The number and experience of the peer evaluators will be adjusted by the oversight and assessment team based on the evolution to be observed and the trend in observations.

21

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Performance-Assessments'

{

at Assessment Points g

I LThe processifor' performance' assessment by the oversight and

assessment-team at each of.the four Assessment ~ Points during-power. ascension'will. consist of.the following five elements

)

I (1), performance' standards to guide the evaluations;

.(2)'Jguidelines for follow-up.and' feedback of lessons

. learned;,

(3) t' raining on the standards'and guidelines for follow-up

-and' feedback; 1

(4). performance evaluations and assessments by line manage-

ment; and:

(5). performance evaluations by the oversight and' assessment team including peer evaluations.

Performance ~ standards are under' development for each of the

disciplines; that will be~ evaluated.

These standards will be used by the evaluators as a basis for comparison of actual performance 3

to predetermined goals to ensure consistency throughout the eval-uat!>n.and agsessment process. ' Guidelines for-follow-up and feedbackof.lessonslearnedwillbedeveloped, and will cover the criteria for determining the immediacy of feedback as well as the lines of, communication for feedback.

The standards now being developed address the following Lhypes of' concerns:

(1)

Is plant equipment operating safely and reliably?

(_ 2)

Are assessment and feedback of lessons learned effec-tive?

(3)

Is the organization functioning as a team?

22

(4)

Is management oversight effective and is management knowledgeable about current plant and organizational conditions?

(5)- Are' problems identified, addressed and resolved in a timely and appropriate manner?

(6)

Has the. staff-provided proper oversight of operations activities to ensure safe and reliable operation?

f (7). Do the operators receive adequate and timely technical support?

(8)

Is the. interface between the maintenance, radiological controls, and operations personnel working properly to

.I ensure adequate maintenance support for plant evolu-t tions?

(9)

Have the management tools such as procedures, computer programs, etc., provided the guidance and information necessary to support plant evolutions?

(10). Are off-normal conditions anticipated, recognized and j

resolved in a timely and appropriate manner?

These standards and guidelines, as well as the results of the evaluations, will be available at the PNPS site.

The pre-restart training of the individuals involved in this evaluabion and assessment process will include a combination of selected activities that will be dependent upon the individual's assignment / area of expertise.

These activities will include the following:

Formal Classroom Instruction Simulator Familiarization / Lab Exercises On-site Field Activities (e.g. Surveillance Testing, Equipment Maintenance / Testing, System Walkthroughs, etc.)

This training and critique process will familiarize these individuals with the applicable standards and guidelines to as-23

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sure:a consistent basis for the' evaluations.

The specific plant

^

' evaluations generated during;this. training _ program, will provide Boston Edison senior management with~an. additional mechanism for assessing the readiness of plant personnel for initial critical-

ity andLpower< ascension.

During power ascension, any new in-dividuals. assigned toLthis~ evaluation process will also' receive training on'these stanStrds and guidelines.

Performance evaluations duric.g restart and power ascension

'will be conducted on two parallel tracks.

Line tan:gement will evaluate' performance as part of their. normal management func-

.tions,. including expansion of the recently implemented PNPS

' Management Monitoring Program.

The oversight and assesisent team Ewill perform independent evaluations with input from peer evalu-ators.

During the assessment period immediately prior to each As-sessment Point, the oversight and assessment team will review the results of the evaluations performed thus far.

These assessments are designed to confirm satisfactory personnel and equipment

-performance to that point in the Power Ascension Program and the readiness of the personnel and plant for continued safe and reli-able operation.

1 24 R

GLOSSARY OF ACRONYMS ASP ALTERNATE SHUTD0HN PANEL ACC ACCESS AHE ASSISTANT HATCH ENGINEER APRM AVERAGE P0HER RANGE MONITOR CAL CALIBRATION CALC CALCULATION i

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