ML20087M983

Affidavit of Ja Notaro & WE Gunther in Support of 840320 Supplemental Motion for Low Power OL

ML20087M983
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	03/30/1984
From:	Gunther W, Notaro J LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20087M974	List: ML20087M973 ML20087M975 ML20087M978 ML20087M981 ML20087M983
References
OL, OL-4, NUDOCS 8404020255
Download: ML20087M983 (17)

Text

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UNITED STATES OF AMERICA

. NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

)

LONG ISLAND LIGHTING COMPANY ) Docket No. 50-322

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(Shoreham Nuclear Power Station, )

Unit 1) )

AFFIDAVIT OF JACK A. NOTARO AND WILLIAM E. GUNTHER, JR.

Jack A. Notaro and William E. Gunther, Jr., being duly sworn, depose and state as follows:

(1) My name is Jack A. Notaro and I have been the Chief Operating Engineer for the Shoreham Nuclear Power Station (SNPS) since April 1983. Prior to that time, from July 1978 through April 1983, I was assigned as Operating Engineer for Shoreham. During March-April 1981, I was assigned to the Op-erations Section of the Millstone Nuclear Power Station for the completion of a refueling outage and power operation training at greater than 20% power. My duties and responsibilities as Chief Operating Engineer of Shoreham include the formulation and implementation of the training programs for all station personnel, direction of the day-to-day operation of the unit, including startup operation and shutdown of all station equip-ment and development and review of the Operation Section of the Station Operation Manual and the overall management of the Operations, Training and Security sections of the station.

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1 (2) I have a Bachelor of Mechanical Engineering degree (1970) and a Master of Business Administration degree (1974).

I completed the General Electric BWR simulator program in July 1976 and obtained certification at the RO and SRO levels. In November 1982, I obtained a Senior Reactor Operator license on Shoreham.

(3) My name is William E. Gunther, Jr. and I have been the Operating Engineer for Shoreham since April 1983. My du-ties and responsibilities include the direction of the day-to-day operation and shutdown of all station equipment, final ver-ification of all operating procedures, participation in initial requalification and replacement training programs for licensed and unlicensed operators and the establishment and maintenance of system operability to support fuel load.

(4) I have a Bachelor of Science degree in Electrical Engineering (1970) and a Master of Science degree in Electrical Engineering (1971). I earned a Senior Operator Certification from the General Electric Company on the Brunswick Unit 2 BWR in 1975 and I completed the General Physics Company BWR si-i mulator-pro ~ gram in December 1981 and obtained certification at the RO and SRO levels. In November 1982, I obtained a Senior Reactor Operator license on Shoreham, i

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l (5) The purpose of this affidavit is to describe the j l

steps involved in the following phases:

Phase I: Fuel Loading and Precriticality Testing Phase II: Cold Criticality Testing Phase III: Heatup and Low Power Testing to Rated Pressure / Temperature Conditions (approximately 1% rated power)

Phase IV: Low Power Testing (1-5% rated power) 4 These various phases will be described below, with a brief ex-planation of the testing and operations to be conducted during each phase.

Phase I: Fuel Loading and Precriticality Testing (6) Fuel loading and precriticality testing involve placing fuel in the vessel and conducting various tests of re-actor systems and support systems. Initial core loading in-volves the placement of 560 fuel bundles in specified locations within the reactor vessel. This major step requires signifi-cant testing as fuel loading progresses, and it takes at least 288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br />. The following testing is associated with initial l

core loading:

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(A) Water chemistry surveillance '

testing. This testing must be performed prior to, during and after the fuel loading operation. The purpose of water chemistry surveillance testing is to ensure clarity of the water so that the fuel loading process i can proceed and to minimize the amount of the corrosion products in the primary system.

(B) Control rod drive stroke time and friction tests. These tests are performed during the fuel loading step to ensure that the reactor shutdown capability is maintained i at all times and to ensure the control rod drive mechanisms are performing as designed.

(C) Installation, calibration and utilization of special startup neutron in-strumentation. This instrumentation is re-i quired for core loading activities to ensure l proper monitoring of core conditions by the Operating, Reactor Engineering and Instrumen-tation and Control personnel. Source range monitor testing and alignment tests calibrate the neutron monitoring instrumentation and verify proper final alignment of this vital equipment.

(D) Core verification instrument op-erability check. These checks are performed to verify that the equipment utilized to de-termine that the core has been loaded cor-rectly is operable. Final core verification checks are completed at this time.

The tests listed in (A) through (D) above involve valu-able supplemental training and experience for personnel as-signed to the Reactor Engineering Section, Radiochemistry Sec-tion, Operating Section, Maintenance Section and Instrumentation and Control Section. The training described in l

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l steps (B), (C) and (D) can be fully accomplished only during the fuel load operation.

(7) Following placement of the fuel in the vessel, a number of tests must be performed to verify the operability of systems prior to going critical in the reactor. This phase of startup testing takes approximately 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> and includes the following:

(A) Local Power Range Monitor (LPRM) sensitivity data. During this test, the 31 local power range monitor strings are cali-brated and verified to be operable. Instru-mentation and control technicians will per- .

form this testing, and obtain training in the use of calibration procedures and special test equipment.

(B) Zero power radiation survey for background readings. Various locations in the plant are surveyed by health physics technicians to determine background radiation levels with fuel in the vessel.

(C) Recirculation system instrument calibration checks. Operation of the recirculating pumps with fuel in the vessel is conducted to determine core internal pres-sure drops and to verify system performance.

Operation of the system above minimum speeds with the vessel internals installed can be accomplished only with fuel in the reactor.

(D) Control rod drive scram time testing. Following fuel load, each control rod drive mechanism is scrammed from its full withdrawn position following control rod cou-pling surveillance testing to verify that rod insertion can be accomplished within the pre- -

scribed time.

(E) Cold MSIV timing. This functional test of the main steam isolation valves verifies that their opening and closing times are within technical specification acceptance criteria.

Again, the testing and activities described in (A) through (D) above can be accomplished only after fuel has been placed in the vessel. The experience and training gained from these activities will be an invaluable Shoreham-specific aug-mentation to the years of extensive preoperational training that the reactor operators have previously undergone.

Phase II: Cold Criticality Testing (8) This phase involves a specified control rod with-drawal sequence that results in achieving reactor criticality at extremely low power levels (.0001% to .001% of rated thermal power). In addition, this step involves shutdown of the reac-tor by inserting all control rods in reverse order. While withdrawing each rod, reactor operators monitor the effect of its withdrawal in terms of neutron flux. By analysis and cal-culation, Reactor Engineerinq personnel are able to assign a

" worth" to each control rod, i.e., the effectiveness of each rod in controlling reactivity. Important operator hands-on ex-perience is gained during this step. Reactor operators must annually perform a minimum of ten reactivity control

manipulations. This experience provides additiona'l training for reactor operators in the use of appropriate instrumentation and equipment to determine when criticality is achieved during' the withdrawal of control rods. This important experience on the Shoreham reactor can be gained only after fuel has been placed in the vessel. Similarly, Reactor Engineering personnel obtain valuable training and experience during this closely monitored activity. LILCO plans to repeat the operations dur-ing this phase of low power testing to offer each operating shift crew this valuable BWR experience.

(9) Cold criticality testing requires plant mainte-i nance personnel to install vessel internals in accordance with station procedures and with all refuel floor constraints in place. Maintenance personnel gain experience with the op-eration of the refuel bridge and reactor building crane.

(10) Also performed at this time is the installation of i

j the expansion and vibration instrumentation. Cold baseline data are obtained at this point to determine pipe movement as heatup occurs later in the low power test program. The data provide a benchmark against which subsequent test results can be assessed.

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(11) During the course of fuel loading, precriticality 1

testing, and cold criticality testing, the plant staff must i place in service, operate, test, and maintain 41 systems.

These reactor systems and support systems include the follow-1 I

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! i Control Rod Drive System (CRD)

Core Spray System Diesel Generator 4160 V System J 480 V System l 120 V AC Instrument Bus l 120 V AC Reactor Protection System (RPS) l 120 V AC Ininterrupted Power Supply 125 V DC System 24 V DC System l Low Pressure Coolant Injection (LPCI) i HVAC-Drywell Cooling Reactor Building Closed Loop Cooling Water System (RBCLCW) i Reactor Building Normal Ventilation System (RBNVS)

Residual Heat Removal System (RHR)

Reactor Recirculation System

! Service Water

Reactor Building Standby Ventilation System (RBSVS)

! Standby Liquid Control System Condensate System I

Feedwater System HVAC - Control Room

HVAC - Turbine Building Reactor Water Cleanup System l Station Air System l Turbine Building Closed Loop Cooling System i Containment Area Leakage Detection System i

RBSVS & CRAC Chilled Water Systems Neutron Monitoring Instrumentation i

Rea'ctor Manual Control l Radwaste Liquid Collection and Processing Circulating Water Demineralized Water i Well Water and Domestic Water System l Normal Station Service Transformer and 138 KV System i Reserve Station Service Transformer and 69 KV System i

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l Fire Protection System Fire Suppression System Reactor Vessel Water Level Radiation Monitoring System Heat Tracing System The operation of these systems provides valuable training and experience to operating plant personnel, including licensed operators. LILCO plans to repeat certain of the ac-tivities in this phase of low power testing to provide addi-tional, valuable BWR operating experience. It is estimated that there will be 5000 total manhours of training accomplished and achieved during fuel loading, precriticality testing, and cold criticality testing described above.

Phase III: Heatup and Low Power Testing to Rated Pressure / Temperature Conditions (Approximately 1% Rated Power)

(12) During this phase of low power testing, reactor heatup and pressurization commences and the power level is taken in progressive steps to 1% of rated power. Along the way, the heatup and pressurization of the reactor vessel and associated piping systems enables the plant staff to perform important tests relating to thermal expansion of piping and in-tegrated system operation under actual operating conditions.

The principal steps associated with this phase of low power testing are described below.

(13) Rod withdrawal sequences are followed to achieve criticality and system heatup from ambient conditions to 150 psig. During this step, the following tests and training are accomplished:

(A) Conduct Source Range Monitor (SRM) response testing to verify source range moni-toring calibration and response; (B) Establish condenser vacuum follow-ing establishment of steam seals and other main turbine auxiliary systems; (C) Obtain initial baseline readings for Nuclear Steam Supply (NSS) system thermal expansion; (D) Place steam jet air ejectors in service on main steam; (E) Achieve warmup of the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) system's; (F) Achieve controlled warmup of reac-tor feed pump turbines and integrated op-erations of the condensate and feedwater sys-tems; (G) Obtain Intermediate Range Moni-tor / Source Range Monitor (IRM/SRM) overlap data; (H) Obtain Intermediate Range Monitor

! (IRM) range 6-7 overlap data; and I

i (I) Perform an Average Power Range Mon-itor (APRM) calibration while heating up.

Operating personnel and instrumentation and control 1

t technicians receive valuable training and experience in the course of these steps.

(14) With the reactor at 150 psig and during the con-tinued heatup from 150 to 250 psig, the following system tests are performed:

i (A) Drywell inspection; i

(B) Data gathering for Nuclear Steam Supply (NSS) system thermal expansion; i

(C) Data gathering for Balance of Plant (BOP) system thermal expansion; I

(D) Operation of Main Turbine Electro-Hydraulic Control (EHC) System; (E) Data gathering for Reactor Building Closed Loop Cooling Water (RBCLCW) steady state performance; (F) RCIC initial operability demonstra-

, tion with manual start and hot quickstart, condensate storage tank (CST) to CST recirculation; I

(G) Motor Operated Valve (MOV) dynamic I testing on Residual Heat Removal (RHR) sys-tem; (H) HPCI initial operability demonstra-tion with manual starts and hot quickstarts, CST to CST recirculation; (I) Maintenance of suppression pool within technical specifications using RHR suppression pool cooling; (J) Operation of steam seal evaporator, radwaste evaporator and main condenser demorating system; i

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(K) Verification of capability to shut down the reactor from outside the control room utilizing the Remote Shutdown Panel.

l (15) With the reactor at 250 psig and during the con-tinued heatup from 250 psig to 350 psig, the following testing is performed:

(A) Maintain EHC pressure setpoint at 250 psig and withdraw control rods to open turbine bypass valves (BPV) for Safety Relief Valve (SRV) testing; (B) Functionally test the Safety Relief Valves (SRV) manually opening one SRV at a time; (C) Obtain drywell piping vibration data while performing the SRV tests; (D) Gather data for system thermal ex-pansion tests.

(16) With the reactor coolant system pressure between 350 psig and 550 psig, the following testing is performed:

(A) Place one reactor feedwater pump and the low flow feedwater controller in ser-vice and monitor their operation to ensure that they perform their function of supplying water to the reactor vessel at the appropri-ate flow rate; 1

l (B) Gather data for system thermal ex-i pansion tests; (C) Perform Average Power Range Monitor (APRM) heatup rate calibration; (D) Verify loose parts monitoring system operability.

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(17) With the reactor coolant system pressure between 550 psig and 800 psig, the following testing is performed:

(A) Conduct a drywell temperature in-spection and gather data for system thermal expansion tests; (B) Obtain Reactor Building Closed Loop Cooling Water System (RBCLCW) performance data; (C) Scram selected control rods to ob-tain scram time data.

(18) With the reactor coolant system pressure at 800 psig and heatup to 920 psig, the following occurs:

(A) Scram selected control rods for

scram time data; (B) Obtain system thermal expansion data for nuclear steam supply systems and balance of plant systems.

Phase IV: Low Power Testing (1-5%)

(19) During this phase of low power testing, the power level is taken in progressive steps from 1% to 5% of rated thermal power. With the reactor coolant system at rated tem-perature and pressure, the operator will withdraw rods and open one Main Turbine bypass valve to establish a steam flow such that core thermal power is less than 5% rated thermal power.

Once this condition is established, the following tests are performed:

l (A) Demonstrate RCIC operability; (B) Demonstrate HPCI operability; (C) Perform dynamic motor operated valve tests, inservice leak tests and hot hanger sets on plant systems; (D) Align Traversing Incore Probe (TIP);

(E) Calibrate the bottom reactor pres-sure vessel head drain line flow indicator and perform main steam isolation valve func-tional tests; (F) Perform RCIC and HPCI controller tests (CST to CST recirculation); and (G) Perform IRM/APRM overlap calibration.

(20) After the completioh of the tests just listed, the first cooldown to ambient conditions will commence. During this cooldown, the following activities take place:

(A) Perform source range moni-tor / intermediate range monitor overlap calibration; (B) Position one turbine bypass valve so that core thermal power is less than 5%

and maximum steam flow is available for HPCI; (C) Perform a HPCI/RCIC stability test to demonstrate the stability of the control-1er setting from the 1000 psig test; (D) Perform a drywell and reactor building inspection of system thermal expan-sion instruments.

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(21) Then comes a second heatup to rated c'onditions.

During this heatup, the key activities include:

(A) Demonstration of the source range and intermediate range monitor response to control rod withdrawal; (B) Gathering of system thermal expan-sion data; (C) Calibration of the average power range monitors.

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(22) When the plant is at rated temperature and pres-sure, the plant staff verifies that core thermal power is less than 5% rated thermal power by performing a heat balance.

After the verification of core thermal power is complete, a RCIC cold quickstart and endurance run are performed.

(23) Subsequent to the completion of the second test period at 920 psig, the plant will be cooled down to ambient conditions. During this cooldown, the plant will obtain nuclear steam supply system thermal expansion. data for the sec-ond time. When ambient conditions are reached, the low power tests are concluded. Repeated startups and heatups to rated l conditions will be performed at Shoreham, however, so that each

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operating crew can be given the opportunity to experience plant response to the tests and activit'ies presented above.

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, (24) In order to support and perform all of the func-l tions and tests performed during Phases III and IV described above, the plant staff will be required to place in service, operate, test and maintain 54 plant systems. In addition to the reactor systems and support systems listed in paragraph 12 above, these are as follows:

Automatic Depressurization System (ADS)

HPCI Offgas System RCIC Generator Seal Oil System Main Steam System Turbine Generator Turbine EHC l

, Turbine Lube Oil System Steam Seal System Area Leakage Detection Reactor Vessel Pressure and Temperature Systems Remote Shutdown System It is important to emphasize once more that the operation of these systems and the various functions and tests performed during Phases III and IV of isw power testing, as with the ac-tivities during Phases I and II, will provide valuable training and experience to operating plant personnel, including licensed operators. As noted in this affidavit LILCO intends to expand the fuel load and precriticality testing, cold criticality testing and low power testing activities to provide Shoreham's operating personnel with additional operating experience above l

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that which would result from a conventional fuel load and low power testing program. It is estimated that 6000 manhours of training will occur during Phases III and IV, in addition to the 5000 manhours during Phases I and I.

8 A ot'aro V ax= 1221 William E. Gunther, #1.

STATE OF NEW YORK )

) To-wit:

COUNTY OF SUFFOLK )

Subscribed and sworn to before me this 3 O day of March, 1984.

My commission expires: MaAofJb/9f6'j ry Public W QA b CONNIE 4AARIA PARDU A0TARY PUBUC, Stats of New Yor, No. 52415310 Qualitted in Sutto:k County I

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