ML20153H648

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Ascension Program
ML20153H648
Person / Time
Site: Pilgrim
Issue date: 08/31/1988
From:
BOSTON EDISON CO.
To:
Shared Package
ML20153H630 List:
References
PROC-880831, NUDOCS 8809090279
Download: ML20153H648 (41)
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f BOSTON EDISON COMPANY l l

l l PIIERIM NUCLEAR POWER STATION l

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l Power Anconsion Program August 31, 1988 Ck $fhf

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POWER ASCENSION PROGRAM ,

t Ta' ole of Contents Page Introduction 1 I.

f II. Power Ascension Logic Plan 2 A. Bases for Logic Plan 2 B. Summary Description I of Power Ascensicn 5 i III. Management Assessment Points and NRC Approval Points 9 A. Sources of Assessment Point and Approval Point Requirements 9  !

t B. Description of Power l Ascension Assessment Points 10 t C. Description of Approval Points 17 I

IV. dtartup Organization 19 A. Operations 'dection 19 f B. Post-Rofueling/Hodification f Outage Test Organization 20 l

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C. Nuclear Organization i Support for Operations 21 l D. Oversight and Assessment Team 21 f

V. Management Assessment Process 22 A. Readiness Assessment for f Initial Criticality 22 B. Oversight and Assessment l of Power Ascension 23 s 1  ?

l C. Performance Assessments I at Assessment Points 25 f

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D. Assessment During Normal Operation / Observation Periods 28 Glossary of Acronyms 29 Figure 1 Figure 2 Figure 3

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I. Introduction This document describes the Power Ascension Program for the restart of Pilgrim Nuclear Power Station (PNPS) from the current outage (RFO-7). The Power Ascension Program is the final phase of the PHPS Restart Plan and is the mechanism by which Boston Edison will demonstrate the effectiveness of its programs, plans and actions.

This program description should be read in conjunction with the Restart Plan, dated July 30, 1987 and the Readiness for Restart Self Assessment report dated May 26, 1988, to understand the scope of programs, plans and actions undertaken by Boston Edison to assure safe and reliable restart and continued operation.

The program description is organized to describe the Power Ascension Program in the following sequences o Logic Plan o Management Assessment Points and NRC Approval Points o Startup organization o Hanagement Assessment Process The management assessment description includes the mechanism for Boston Edison's process for confirming readiness for intial criticality and for oversight and assessment during power ascension.

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

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II. Power Ascension Logic Plan Boston Edison has developed a power ascension logic plan for the testing, restart and power ascension from RFO-7. The bases for this logic plan and the sequence of power ascension r,teps and associated tests are described in this section. The management assessment process, including the management Assessment Pointo, is integrated into the logic plan.

A. Bases for Ioolc Plan The power ascension logic plan is based on and complies with the PNPS Technical Specifications. In addition, the plan considers prior power ascension experience at PNPS, specific testing requirements for the work accomplished in RFO-7, personnel and equipment performance evaluatior. Nuclear Regulatory Commission (NRC) Approval Points and prior relevant nuclear industry experience.

Both testing and training will be conducted primarily at four test condition power levels. Three intermediate test condition power levels are nominL11y within plus or minus 5% of power level at 25, 50 and 75%. The fourth test condition power level is 95 to 100%.

power ascension experience from prior PHPS refueling outages is incorporated into the power ascension logic plan. The plan is sinilar to the sequence of power ascension that was proven successful in RFO-

6. In addition, checklists for plant operational condition changes, which were first used to track the completion of designated RFO-6 milestones leading to restart during the recirculation pipe 2

replacement work, have been expanded and refined for use during the approach to criticality and during RFO-7 power ascension.

Several specific hardware performance problems led directly to the plant shutdnwn 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 operating conditions.

These special tests are to confirms (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 portions of the Residual Heat Removal System; and (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 Reom which will be conducted after successful performance of the three special tests.

The power ascension program includes management assessment periods at each test condition power level. Each assessment period ends in an Assessment Point, during which management can systematically review earlier performance evaluation results, assure itself that corrective actions taken as a result of performance evaluations have been effective, and determine that the plant and its staff are randy to proceed with a period of normal operation / observation with the level of supervision and oversight more typical of that which will be in place during normal operations.

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These normal operation and observation periods will include i

reactivity changes and plant evolutions as appropriate for now l '

operator required training, for establishing proficiency and l l  !

l familiarity with plant characteristics during steady state operations,  !

for additional confirmation of satisfactory equipment operation, and {

for self assessment of performance. 1 4

i The process for conducting performance evaluations of PNPS (

L personnel and equipment and the process for performing management

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l assessments of the results of those performance evaluations at each l 1

Assessment Point and subsequent normal cperation/ observation periods, I l I j are described in Section V. '

In response to the NRC request in the August 27, 1986 letter on the [

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! subject of Confirmatory Action Letter (CAL) 86-10, Boston Edison l l

proposes five NRC Approval Points, each of which require oral approval

] from NRC Region I for continuation of the power ascension. These ,

j Approval Points are described in Section III.

l Pinally, Boston Edison has continued to consider prior relevant l nuclear industry experience with restart and power ascension programs.

Boston Edison also has considered the specific plant circumstances (

1 t under which other restart and power ascinsion programs were developed i and conducted, to distinguish those features in other plants' programs which should apply to PNPS restart from those features which were [

l plant-specific and should not apply. l

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R. summary Descrintion 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, assessnent and power ascension stok A portable auxiliary boiler has been successi lly used to perform HPCI and T;CIC testing at 150 psig. HPCI and RCIC overspeed tests satisfactorily completed using the auxiliary boiler have been deleted from the initial power ascension sequence 'epicted in Figure 1.

Figure 2 is a plot of approximate power levels during the specified l tests, assessments, operator proficiency periods and training.

As illustrated in Figure 1, the PNPS reactor will be taken critical l

following Boston Edison and NRC approval of restart. As the plant is slowly heated and pressure is increasing, a number of routine startup l tests and checks of plant equipment and special operator training vill be conducted. Some of there tests, instrument calibrations, and 1

checks are indicated in Figure 1.

During initial reactor heatup, the main steam isolation valves will be tested to verify that they open with normal differential pressure across the valves. This test is designed to verify correction of one of the plant hardware problems addressed in CAL 86-10.

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

Thin action addresses a second hardware problem from CAL 06-10.

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l The reactor will be operated below 5% for plant system tightness and system operability verification under hot plant conditions and for portions of the Special Post Startup Training Program prior to requesting NRC approval to proceed to the next higher power test condition for programmed testing.

At approximately 25% reactor power, Boston Edison will initiate a normal shutdown, shift the mode switch to "Startup" and decresse reactor pressure to about 800 psig to confirm that the main steam isolation valves remain open during reactor depressurizution after the mode switch is shifted from "Run" to "Startup". This test addresses the third problem addressed in CA. 36-10.

Following successful completion of testing and after Managemen,t Assessment raint 1, Boston Edison will conduct approximately thirty days of normal operation for observation, for new operator required i training, for establishing proficiency end familiarity with plant characteristics during normal plant operations, and for additional self assessment. <

After completion of the normal operation / observation period, followed by NRC approval to raise power level above the 25% power test condition, the required shutdown-from-outside-the Control Room-test will be conducted.

Following recovery from the shutdown test, the scram setpoint will be raised to the 70% power level and reactor power will be gradually increased to approximately 50% as norr.al testing and calibration are l conducted. Boston Edison management will again assess performance of the plant and personnel at this point, followed by a second normal l

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l operation / observation period for nsw operator required training, for enhancing operator proficiency and familiarity with plant characteristics, and for self assessment.

Following NRC approval to go cbove the 50% power test condition, l l

the scram setpoint will be raised to the 95% power level to permit the reactor to be brought to approximately 75% power. During this time, l reactor engineering tests comparable to those performed at the 50%

power test condition, as well as turbine valve tests and main steam isolation valve tests, will be conducted. Boston Edison management will assess the performance of the plant and personnel at this point, followed by a third normal operation / observation period for new operator required training, for enhancing proficiency, and familiarity with plant characteristics and for self assessment, before permitting the power ascension to continua. Upon satisfactory completion of testing at the 75% power test condition, and when management confirms that operator training requirements have been met satisfactorily, operating crews may make the .ransition from a four to a six section watch rotation.

Following NRC approval to go above the 75% power test condition, the scram setpoint will be raised to its normal 120% level and the reacter will be brought to approximately 100% power. Routine reactor engineering tests will be conducted at this power level to complete the power ascension process. Boston Edison management will assess the performance of the plant and personnel, confirming satisfactory completion of the Power Ascension Program and the offectivonoss of tho 7

i programs, plans and actions for continued operation. This assessment will be followed by the fourth period of normal operation / observation.

This sequence of restart tests for startup from RFO-7 is documented in PNPS Nuclear Operations Department Temporary Procedure 87-114.

Major elements of the procedure are the summary description, the cross-reference of the tests, and tho Restart Program Checklist. The summary description of the tests is intended for qeneral information.

The specific details or criteria for actually ce.c6ucting the listed tests will be incorporated in the individual PNPS operating procedures which are referenced in Temporary Procedure 87-114. The Restart Program Checklist will be used to focument acceptable completion of tests.

Figure 1, the Power Ascension Plan, will be used by the Startup Test Manager to develop the daily testing and power ascension schedules. The daily testing and power ascension schedulcs will be approved by the Operations Section Manager. The power ascension testing will be coordinated with the Master Surveillance Tracking Program using the Plan of the Day. The Plan of the Day is approved by the Plant Manager.

The startup test organization will function fully during the testing periods associated with each of the power level test conditions, and will be on standby during the normal operation / observation periods for operator training, self assessment and equipment observation, but will remain on-call to function as needed.

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III. Management Assessment Points and NRC Approval Points Boston Edison will assess personnel and equipment performance at several points during the power ascension. The process for assessment prior to initial criticality and resulting actions will have been completed prior to requesting restart and is discussed in Section V.A.

The sources of Boston Edison Assessment Point and NRC Approval Point requirements, the actual Assessment Points, and the proposed Approval Points for power ascension are described in this section.

A. Sources of Assessment Point and ADoroval Point Reauirements In the course of its self assessment, Boston Edison's senior nuclear management has identified a need for a number of predetermined Assessment Points for review of personnel and equipment operational performance. These Assessment Points occur at logical intervals in the power ascension sequence. Senior management approval will be obtained before powey ascension will be permitted to continue beyond each Boston Edison management Assessment 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 modo switch testing, and at specific milestones during ascension to full power." In response to this request, Boston Edison proposes five NRC Approval Points which would require oral authorization from NRC Region I before PNPS can continue power ascension.

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B. Descriction of Power Ascension Assessment Points Four Boston Edison Assessment Points are planned during the Power Ascension Program. The purpose of these Assessment Points is to confirm readiness to proce.a with normal operation /observat ion periods for operator training and self assessment and the next perj od of power ascension. The first assessment point using the process described in Section V will occur at the 25% power test condition. Examples of the types of activities that will be conducted during each of the assessment periods are described. At each Assessment Point, management will review results of observations, performance evaluations, and any corrective actions taken for personnel, equipment and procedures during the preceding period of power ascension.

Further, r.anagement will identify additional corrective actions as required.

A_stc s sment Point 1 The first Assessment Point will be after recovery from testing to confirm that the main steam isolation valves remain open during reactor depressurization after the reactor modo switch is shifted from "Run" to "Startup", and prior to a period of normal operation / observation for operator training, proficiency and self assessment. Assessment Toint 1 appears in Figure 1.

During the period between initial criticality and Assessment Point 1, operational training, personnel and equipment performance will be 10

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

o Reactor vessel heat-up, and the bringing of equipment on line to support increased power, including the conduct of operations, maintenance, technical and radiological control duties; o System tightness and operability tests under hot plant conditions; o HPCI and RCIC testing at 150 psig requirj.ng coordination of activities by the operations, maintenance and radiological controls personnel; o operator in sequence criticals; o Reactor water level instrumentation enecks; and o SRM/IRM overlap checks.

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 formal assessment and determine readiness to proceed with operator training, establishing proficiency and additional self assessment with power level at the 25% power test condition. This range was selected for calibration of the nuclear instrumentation. The "Management Assessment" period of 8 to 12 days is depicted in Figure 1 and in Figure 2. Subsequent to this assessment period, newly licensed lteactor operators (individuals receiving licenses after May 1987) on each operating crew are scheduled to recejve approximately thirty days of normal operation / observation to gain operating experience to satisfy new license requirements and enhance their proficiency. This operating l 11

experience will include reactivity changes for training and other planned evolutions such as equipment startup and shutdown.

Assessment Point 2 The second Assessment Point will be after the reactor engineering tests at the 50% power test condition prior to a period of normal operation / observation for operator training, proficiency enhancement and additional self assessment, and moving the scram setpoint above the 70% power level. Assessment Point 2 appears in Figure 1.

Between Assessment Pcints 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 i undertaken during this period include the following' l o Shutdown-from-outside-the Control Room test, requiring shutdown of the reactor from the dedicated Alternate Shutdown Panels in the Process Buildings while maintaining a qualified crew of operators in the Control Room.

o Assessment of plant operation between 25% and 50% power which will place the plant in an increasingly stable configuration by virtue of the following conditions:

(1) Condensate system will be fully in service; (2) Both feedwater regulator valvos will be in automatic; (3) RPV level control will bo in three element control; (4) Power level will still be within bypass valve capability between 25% and 30% power levels; (5) 4KV busses will be transferred to the unit auxiliary transformer with the startup transformer as backup; (6) APRM's will be on scale providing total core coverage; 12

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(7) Power level will be high enough for a heat balance; (8) Drywell will be inerted and differential pressures' established; (9) Electrica:L pressure regulator will be in service providing tighter automatic pressure control with the mechanical pressure regulator in backup; and (10) Chemistry controls in place will be much tighter than during startup.

The "Management Assessment" period immediately prior to Assessment Point 2 is shown in Figure 1 and in Figure 2. The duration of this assessment period will be adjusted based on performance observed.

Similarly the duration of the following period of normal operation / observation for operator training, proficiency enhancement ,

and additional self assessment will be determined during the "Management Assessment" and will be adjusted based on the results of self assessment during the training period. ,

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1 Assessment Point 3 Boston Edison has selected a third Assessment Point after completion of the reactor engineering tests at the 75% power test condition prior to the third period of normal operation / observation for operator training, proficiency enhancement and additional self assessment and movement of the scram setpoint above 95% power.

Assessment Point 3 is depicted in Figure 1.

Many of the plant activities between Assessment Points 2 and 3 are virtually identical to those between Points 1 and 2 because the reactor engineering tests conducted at the 75% awer test condition are largely a repetition of those conducted at the 50% power test condition. During this period, additional plant equipment will be placed in service as necessary to support the higher power levels.

The types of activities that will be conducted during this period include the following:

o Placing the additional condensate domineralizer units in service; o operation of the Augmented Offgas Systom; o Placing the third reactor feedwater pump in service; o Routine surveillancos and proventivo maintenance, chemistry analyses and radiological surveys, and o condenser thermal backwash.

The "Management Assessment" period immediately prior to Assessment Point 3 is depicted in Figure 1 and in Figure 2. The duration of this 14

assessment period will be adjusted based on performance observed.

Training requirements for new operators are planned to be completed by this time. A period of normal operation / observation at around 75%

power will follow Assessment Point 3. The purpose of this period is to gain operator experience and proficiency with the plant in its full power configuration and for additional self assessment. When operator training requirements are confirmed to have been met, and with management concurrence, this period may also be used to make the transition from a four to a six section operator watch rotation. The duration of this period will be determined during the "Management Assessment" and will be adjusted based on the results of self assessment during the training period.

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l Assessment Point 4 At nominal 100% power, the final series of reactor engineering tests and calibrations in the Power Ascension Program will be performed. Evaluation conducted between Assessment Points 3 and 4 will largely focus on reutine operating activities such as coordination of surveillances, anticipation and correction of problems, and the conduct of routine and preventive maintenance. In addition, operating activities such as recirculation flow adjustments and control rod manipulations to counterace xenon buildup and achieve 100% power provide an opportunity to evaluate the coordination between operations personnel and reactor engineers.

Results from these reactor engineering tests, as well as the additional performance evaluations, will be assessed by Boston Edison senior management at the fourth Assessment Point, which will be followed by the fourth period of normal operation / observation for additional self assessment. Boston Edison management will assess the performance of the plant and personnel, confirming satisfactory completion of the Power Ascension Program and the effectiveness of the programs, plans and actions for continued operation. The results of this final assessment will be formally provided to the NRC to support close-out of Confirmatory Action Letter 86-10.

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C. Dancriotion of Accroval Points As shown in Figure 2, Boston Edison proposes five NRC Approval Points.

In accordance with CAL 86-10, dated April 12, 1986, the first NRC Approval Point is immediately prior to criticality.

The second NRC Approval Point is proposed where the plant has been brought to criticality and is being held to power levels below 5% in order to conduct testing, conduct portions of the Special Post Restart Training Program, and verify plant system tightness and operability under hot plant conditions.

NRC Approval Points two through five will be preceded by a recommendation from PNPS line management, with the concurrence of the oversight and assessment team, that it is ready for the NRC to consider approval of continuation of power ascension to the next programmed test condition.

The third NRC Approval Point is proposed after recovery from testing to verify that the main steam isolation valves remain open during reactor depressurization after the reactor mode switch is shifted from "Run" to "Startup," after the normal operation / observation period for training and proficiency enhancement and prior to commencement of the shutdown-from-outside-the-control Room test. NRC letter dated August 27, 1986 on the subject of Confirmatory Action Letter 86-10 suggested one NRC Approval Point after mode switch testing. The third NRC Approval Point is proposed 17

to also include the opportunity to observe the subsequent normal

, operation / observation period before granting approval.

The fourth NRC Approval Point is proposed after completion of reactor engineering tests, the normal operation / observation period for operator training and proficiency enhancement at the 50% power test condition and before the scram setpoinc 1c adjusted above the 70%

level.

The fifth NRC Approval Point prior to full power operation is proposed after completion of the reactor engineering tests and the normal operation / observation period for operator training and proficiency enhancement at the 75% power test condition and prior to movement of the scram setpoint above the 95% level. At this point, results from the reactor engineering tests and operator training can be reviewed to confirm readiness to complete power ascension.

At 100% power after completion of engineering tests and calibrations and concurrent with normal operations / observation Boston Edison management will assess the performance of the plant and personnel, confirming satisfactory completion of the Power Ascension Program and the effectiveness of the programs, plans and actions for continued operation. The results of this final assessment will be formally provided to the NRC to support close-out of Confirmatory Action Letter 86-10.

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IV. Startup Organization The PNPS startup organization for return to operation from RFO-7 is comprised of four elements as follows:

(1) the Operations Section; (2) the post-refueling / modification outage test organization; (3) the Nuclear Organization support for operations; and (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 Boston Edison's management oversight processes to increase observation and evaluation of major evolutions during power ascension, to conduct periodic management assessments of evaluations performed throughout this period, and to confirm readiness to proceed.

A. Ooerations Section The Operations Section is the normal line organization for restart from an outage such as RFO-7. Plant startup from any protracted and complex outage requires that additional poople be available on shift to properly execute both the routino and outage-specific tests, as well as to respond to operational problems that may occur after a long shutoown. In recognition of those factors, Boston Edison has elected to utilize a four-shift rotation for the operators. The four-shift rotation will enable assignment of the necessary number of operators, without incurring excessivo and unscheduled overtimo. The four-shift 19

rotation will also enable assignment of an experienced SRO, designated as the "Assistant Watch Engineer" to provide field oversight and on-the-job training for the equipment operators.

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 shift, and the shift operating crews. They report to the Plant Manager.

At the completion of Assessment Point 3 and when a sufficient number of Reactor Operators are fully qualified, a transition to a six section watchbill may be implemented. Thic six section watchbill 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 each operating crew and address watchstanding, training and extended absenco Coverage.

B. Post-Refuelina/ Modification Outaae Test Oraanization 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 Figurt 3 show this organization. Boston Edison's experience is that this test organization's support to the oporations section has contributed to the successful control of startup from an extended and complex outage.

The Technical Section Manager is the Startup Test Manager during restart and power ascension. As such, he is responsible for directing Phd coordinating the efforts of the Shift Test Coordinators, Reactor Engineers, Computer Engincors, Test Engincors and Turbine Test 20

Engineers, for preparation of daily power ascension test schedules, and for independent review of test results.

The test organization will be fully functional during the periods of testing, and will be in a standby but on-call status during post Assessment Point normal operation / observation and training periods.

C. Nuclear Oraanization Suncort 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, Radiological Protection, Planning / Scheduling, Technical Support and other nuclear organization functions. Due to the complexity of this outage, there will be a shift Maintenance Representativo, as shown on Figure 3, ass.'?ned to provido 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage for maintenanco coordination.

D. Overslaht and Assessment Team During restart and power asconsion from RFO-7, an additional organization will provido oversight of power ascension. A description of the oversight and assessment team is provided in Section V.B.

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V. Management Assessment Process The management assessment process during restart and power ascension will focus on management, operational, plant and equipment I

performance. Senior Boston Edison Nuclear organization managers will personally observe major evolutions during restart and power ascension and will assess personnel and equipment performance at each of the four designated Assessment Points to confirm readiness for continued i operations. The team will also oversee PHPS line management functions

! during post Assessment Point periods of normal operation / observation.

As used in this program, the following terms are defined:

, evaluation processes used by peer evaluators, line management and individual members of the oversight and assessment team throughout the Power Ascension Program to observe specific activities and evaluate the performance.

assessment processes used by the line management or oversight and

assessment team during the designated assessment periods prior to each Assessment Point to review the results of prior PNPS activities, including prior performance i evaluations, and to decide whether the personnel and plant are ready for continued operation.

I A. Readiness Assessment for Initial criticalit_y i

The RRSA has been completed. Based upon the status of actions l arising from this assessment, senior management will decide when to recommend restart to the Boston Edison Board of Directors. Finally, after Board of Directors approval, Boston Edison will submit a request for restart to the NRC.

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B. Oversicht and Assessment of Power Ascension Seven senior level managers in the Nuclear organization will serve as the oversight and assessment team during power ascension. These senior managers will observ' personnel and equipment performance during the Power Ascension Program and will perform assessments at each of the Assessment Points to confirm readiness for continued operations. The team members are:

(1) the Senior Vice President-Nuclear; (2) the Vice President-Nuclear Engineering; (3) the Director, Special Projects; (4) the Nuclear Engineering Manager; (5) the Quality Assurance Manager; (6) the Station Director; and (7) the Special Assistant to the Senior Vice President-Nuclear.

Direct support to the oversight and assessment team in performing assessments of plant and personnel performance will be provided by peer evaluators. In the area of operations, for example, individuals assigned as peer evaluators have current or previous BWR Senior Reactor Operator licenses or certifications. Those individuals will be assigned to shift rotation to act as operations observers, team leaders for other peer evaluators assigned to that shift, and report the results of their observations and evaluations to the line organization and to the oversight and assessment team.

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Other peer evaluators will be assigned to support observations in areas such as radiological controls (health physics), chemistry, technical support, security, fire protection 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 results of their observations and evaluations to the line management through the peer evaluator team leader, and 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.

Senior management assessment during the Power Ascension Program, and evaluation of plant and operator activities by peer evaluators will be comprehensive during the assessment periods preceding defined Assessment Points during power level test conditions. Senior management assesament and evaluation during the normal operations / observation periods for new operator required training, operator proficiency enhancement and additional self assessment subsequent to each of the formal Assessment Points will continue, but will be done on an audit basis to confirm the validity of conclusions drawn during the more intense testing and assessment periods, and will provide a unique opportunity for observing line management and crew performance in an environment more typical of normal operating conditions.

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. o C. Performance Assessments at Assessment Points The process for 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:

(1) performance standards to guide the evaluations; (2) guidelines for follow-up and feedback of lessons learned; (3) training on the standards and guidelines for follow-up and feedback; (4) performance evaluations and assessments by line management; and (5) performance evaluations by the oversight and assessment team including peer evaluations.

Performance standards have been developed for each of the disciplines that will be evaluated. These standards will ce used by the evaluators as a basis for comparison cf actual performance to predetermined goals to ensure consistency throughout the eveluation and assessment process. Guidelines for follow-up and feedback of lessons learned have been developed, and these cover the criteria for determining the immediacy of feedback as well as the lines of communication for feedback.

The standards developed address the following types of concerns:

(1) Is plant equipment operating safely and reliably?

(2) Are assessment and feedback of lessons learned effective?

(3) Is the organization functioning as a team?

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(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?

(7) Do the operators receive adequate and timely techniccl support?

(8) Is the interface between the maintenance, radiological controls, and operations personnel working properly to ensure adequate maintenance support for plant evolutions?

(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 resolved in a timely and appropriate manner?

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

The pre-restart training of the peer evaluators involved in this evaluation and assessment process included a combination of selected activities that are dependent upon the individual's assignment / area of expertise. These activities included the following:

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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 has familiarized these individuals with th9 applicable standards and guidelines to assure a consistent basis for the evaluations. The specific plant evaluations generated during this training program, provided Boston Edison senior i

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management with an additional mechanism for assessing the readiness of plant personnel for initial criticality and power ascension. During power ascension, any new individuals assigned to this evaluation process will also receive training on these standards and guidelines.

Performance evaluations during restart and poner ascension will be conducted on two parallel tracks. Line management will evaluate performance as part of their normal management functions, including use of the PNPS Management Monitoring Program. The oversight and assessment team will perform independent e. valuations with input from peer evaluators and monitor line management functions.

During the assessment period immediately prior to each Assessment 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 reliable operation.

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l D. Assessment Durina Normal l Operation / Observation Periodt l During the post Assessment Point periods of normal operation / observation, station line management will continue operation and assess station and personnel performance, directing corrective actions as necessary, and carrying out other normal line management functions typical of a normal operating environment. The oversight and asseusment team will continue to monitor line management and station performance during these periods, but at a frequency more typical of a normal operating environment.

The Boston Edison recommendation to proceed witn the next stage of power ascension (a prerequisite for NRC approval P.t each of the i

, proposed NRC Approval Points), will be made by line management and will be monitored and concurred with by the oversight and assessment team.

J l

i

/

28 l

GIDSSARY OF ACRONYMS ADS

S/D SHUTDOWN S/U STARTUP SDOCR SHUTDOWN OUTSIDE CONTROL ROOM SJAE STEAM JET AIR EJECTOR SRM STARTUP RANGE MONITOR STM STEAM SV STOP VALVE TP TEMPORARY PROCEDURE TEMP TEMPERATURE TIP TRAVERSING INCORE PROBE TSY TURBINE SUPERVISORY INSTRUMENTATION TURB TURBINE i

i l

r e >

l l

i 30 l

l

O 4

POWER ASCENSION PLAN -

SHEET 1 OF 6

/ / / *'^""*/

MC U P4SEO FCH N S SD MARGPg 8.5.5.378.5.5.6 HESTART SRWidA 1RM RGR7 INSEO RX WATER CALC 9.16.1 RAISE PRESSURE TESTRCCAT OVERL/p CORRELAilON CRITICALS LEVEL CHECK TO 150 PSIG n 150 PSIG h: U / 3 4

V ?6 U 48 8 4 6

l HELIUM TEST' s 1-4 WATER a

BOXES RX WATER LEVEL CHW C l SEE NOTE 3

, umDweERSACC a HATcHPRORTOCRIT o

l tour s.: RAM SETPONT HEATUP TO 1000 PSIG TO 45*/.PROR TO SU TIME IN HOURS O

NOre-

1. HPCI & RCC TESTPG SATISFACTORILY CCAFLETED WITH AUXILIARY BOLER MAY BE DELETED
2. THS IS A PLAN FROM WHK:H DAILY SCEDIRES WiLL BE. MOPED THESE DALY SCHEDULES Wit TAKE NTO CCr4SOERATL1. PLANT APO EOUFENTSTATUS.
3. MONITOR FRE PRESSURE N-SYSTEM LEAKAGE FROM PRESSLT<tATON THROUGHOUTPOWER ASCENSION
  • NOTAMANDATEDTEST

" THE MAY NOT BE PERFORMED IF SHUTDOWN MARCH HAS PREVKXELY BEEN DEMONSTRATED Figure 1

t POWER ASCENSION PLAN SHEET 2 OF 6 DETEfWNE ADJUST RX POWER AN O O 8.5.6.2.

MANUAL RAISE RAISE 8.5'4'3 '8'5.4 ~6 LOWER REPLACE RAISE OPENINGS OF PRESSURE PESSUFE TEST HPCI AT PRESSURE RCE. m PESSURE RELEF VALVES TO TO 150 PSG TO<150 PSG TESTORFICE TO 350 PSG FROM CCNTRM 600 PSG EPR SET PONT

-O ^ -0 0 6 2 24 y 12 6 4 0 8 8

NSPECT DRYWELL s TESTMSN BETWEEN 600 AND 1000 PSG 8 OPEN!NG Q

C INSPECT PLANT FOR g

SYSTEM TGHTNESS ESPONSECHECK AND SJAeS SETUPOFTHE STEAM HEATUP TO 1000 PSIG SucTmTEST SEAL NGLUTOR TIME IN HOURS O O O I

NOTE-

1. HPCI & RCC TESTNG SATISFACTORLY COMPLETED WITH AUXLIARY BOLER MAY BE DELETED.
2. THIS IS A PLAN FROM WhD DALY SCIEDULES WILL BE DE'KLOPED TESE DALY SCHEDULES WLL TAKE NTO CONSIDERATON PLANT MO EOUMENTSTATUS.
3. MONITOR ENR PRESSUE N-SYSTEM LEAKAGE FROM PESSURATION TMOUGHOUTPOWERASCENSION
  • NOTAIMNDATEDTEST i

" THIS MAY NOT BE PEFFORED F SHUTDOWN MARG 2J HAS PREVIO'JSL1f i

BEEN DEMONSTRATED Fi;u.e 1

O t

POWER ASCENS!ON PLAN -

SHEET 3 OF 6 MCX)E SWITCH TO RN(APRM RRJCTIOfLAL

-O~

s WTTHN 4 HRS OF RLN -8 M.1-3) s APPHOVAL s 926 PROCESS COMPsITER CHECKS FOR 25Y.

s N APRM n. _ _ _ _ _6_ _ _ _ _ _ _ _ _ _ _ _ _ _ .o_ _ _ _ _ _ _ _ _ _ _ _6 _ _ _ _ _ _ _ _ EPIC TESTING s

8 CO WLETE T 8.5.5.1/8.5.5.6 3.M.4.o 8.5.4.1/8.5.4.6 ____________l OVERLAP s a R N TEST HPCIFLOW N 8 s F6 TION O ROtt ,

m FROuCR&

E 1STOP TESTFROMCR & POWER TURB OS & l OPER-5 6 TURBWE : MWO VALVE BALANCE lN d 8

RAISEPOWER 8 TO15-20 CTP e PHASEGEN 8 6N d

REMOTE SD PANEL REMOTE SD GENERATOR PANEL OFF-LINE OFFLNE TESTNG A

SHUTDOWN 8 TO 800 PSIG gV Y n n A n

" v n n v

8 8

8 4 Y 6 Y 4 V 24 Y 8 8 8 4 12 U g

e s a a

e MN OR s s ADS,CS. s 8

a a l RXWATER l LPCI l l TRPTEST s LEVEL  : ________

e TESTNG s a  ;

j M&S 8  : FOR s

ISOLA- 3.bQ_

. O l LCO l  : TION a -

a i a

DRYWELLTEMP PROFILE e 8. A.9  : 'C i 9: l SvCiv TESTNG l
ye3 a

s__________________________8 SCRAM --O-a

25 % 8 8

s 8 82.4 8 a

s

PRESS 8 l NO a REG. TEST 8 _________

s__________________________s 12 FDC MODE l THRUST BEARNG  :

M CH
WEARDETTEST s__________________________I TESTNG TURBINE RLW  !

l uort. , tu neOWeR

12 8
  • NOT A MAPOATED TEST ------@y g3 M] M d ---

TESTING - 1000 PSIG TO 25%

TIME IN HOURS Figura 1

O POWER ASCENSION PLAN .

SHEET 4 OF 6 ASSESSMENT APPROVAL PONT1 FOR 50%

SCRAM FOR SDOCR l gpg.

NOAMAL SCRAM TIME DATA ncTNG N OPERATIONS /

g TURBINE POWER TO TP 87-147 T 8.M.1 -4.1 TSI& EPR 20-25 % SDFROM SETPONT TURBNE lOBSERVATKY4 RiCOVER mSETPONT m '8 CAD COMPLETE 8 RECAL BUILD DECAY OUTSOE TO m' ONLNE n

NOTE 4 H IEAJ uv CONT N n POWF_R TO 70%CTP x TIMETEST -

Y V

13  % 720 12 Y 48 Y 5 U 24 U ANALY$~~~8 8

MGW{T  ! l s a a DATA NO l l ASSESSENT f

/s I I' 4 til AFTER RUN I l l DRYRUN

- w-O l  ; ,

a wAuaunu SDOCR l

, s i

8 i eROCeSS COUP ANALYZE s e i a PROCESSCOMP l s o,3 s

P-1 l DATA l l l RECOVER f I 9.-5 LPRM CAL i  :

TRANRG OD-1 AT25%

f l l 8 8 OD-1 AT25% 8  : OPERATORS , l

._____Q 30 8 s a RX EICIEST'i l 9.3 8 8 8 9.3 8

HEAT BALANCE l l l HEATBALANCE ! -

________a 12

9 99
8, CORE N ,

9.19. 9.22 8 8 tRFGlMANCE 8 I i NOTE-l DwwuP  ;

l l 4. FIVE FULL SHIFTS OF OPERATON s a FOR EACH CFTHE FOUR WATCH SECTIONS l HPCI l _

s COLD OUICK e

  • NOTA MAP 0ATEDTEST START TESTING - 1000 PSIG TO 25%

l l TIME IN HOURS Figure :

POWER ASCENSION PLA.N l SHEET 5 OF 6 ASSESS 44ENT POINT 2 APPROVAL FOR 75 %

k rwReATERtEvaCONmOt- O 8.M.1-4.1 8 RAISE 9.17 RAISE 50 % TURB g 8 RAISE SCRAM RAISE RAISE 75 % 8 POWER JET POWER RXENG ASSESSMDR l SETPOINT POWER SURV RX ENG TO50%

POWER TO 40% PUMP CAL TESTS TO 95%

O 0 O n TO 60% n TESTS n TO 75% n TESTS A

3 , 3 g ,, d-G 4 v

2 J4 Y 4

'[' 48 l l l CvSv l l J

e , e mu i l i TtSr G :

i

________, i

!  ! OPE TONS / MBNN 9,37  :

i DWTEMP e OBSERVATION  : 8 a

PROFILE 8 JET  : e

' 8 8

9.19.922

! PUMPCAL !  ! COREPERFORMANCE a l 9.19 922 e i e ,

8 COREPERFORMACE ,

l 8

  • BYPASS l
  • M TUBE e

e I

! VALVE I  : POSITONREADINGS l SCOOP TUBE TESTRKs 8'

  • e 8 POSITION READINGS ! '

8

  • 82.4 RX e l 9.28  !
PROCESS COMP e
  • EPIC TESTNG l l 82.4Rx l POWER ASCENSION TO 100% 8 BEAR 2 l

e PRESS REG. TEST Woe 7TES 8

; TIME IN HOURS -

8.1.1.20  : .IURBINE SHAFT B

e WATEREVELCHANGE 8 s VOLTAGE CHECK l

' THRUST BEARINGS l NOTE: -

'  ; 926teRu i WEAR DETTEST 8

RESPONSE TEST :
  • NOT A MANDATEDTEST - 8 9.5 '

9.1 s

CAL O

CALs

' !NN n l PRocEYscouP i Figure 1 l DW TEMP PROFILE i

POWER ASCENSION PLAN SHEET 6 OF 6 POINT 4

  • 95%

APPROVAL SCOOPTUBE FOR 100 % POSITION READING 8#.14.1 h PCM I

RAISE 9.17 RAISE 9.17  : RAISE RAM SCRAM MGt4T E M ffT POWER JET PUMP POWER JETPUMP I POWER 100Y.RX MGMT ASSESSuenT u TO ,m TO sa ca TO m cat , TO im ENcTeSTS ASSeSSueNT k

4 5 3 12 3 18 48

  • gg I 8 g

8 SCOOPTUBE!  !

POSITON I I  :

8 8 READING 8 8 s

NORMAL s OPERATONS /

l H W N 93  : NORMAL OBSERVATION  :  ; OPERATIONS /

8 9.19 9.22  : OBSERVATON l COREPERFMENCE s

. 8 8

CmertowCAL j

9.17 l
JETPUW CAL e l mRUST BEAREG i 8

s WEAR DETTEST POWER ASCENSION TO 100%  ! TIP AUGNMENT  :

TIME IN WJURS l 93 9.i i I LPRM CAL APRMCAL !

NOTE: l O eROCeSS l

NOTA MANDATEDTEST l COwUTER I i

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