ML18038A043
| ML18038A043 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/07/1985 |
| From: | Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| (NMP2L-0465), (NMP2L-465), NUDOCS 8508130235 | |
| Download: ML18038A043 (651) | |
Text
REOi~lOY:INFORI1ATION DISTRISU%003YSTEN (RIDS) e f ACCESSION NBR: 8508130235 DOC ~ DATE: 85/08/07 'OTARIZED; NO DOCKET FACIL:50-410 BYNAME Nine Mile Point Nuclear Station< Uni t 2E iViagara Hoha 05000010 AUTH AUTHOR AFFILIATION MANGAN,CD V. .Niagara Mohawk Power Corp.
RECIP.NAME RECIPIENT AFFILIATION BUTLER l'I ~ Licensing Branch 2
SUBJECT:
Forwards proposed rev to FSAR Chapter 14 L draft revised responses to stated questions, Meeting within next 30 days requested. Tables deleted from chapter listed.'Matl will be inoorporated in cloture PEAR amend, DISTRIBUTION CODE: B001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Licensing Submittal PSAR/FSAR Amdts 8, Related Correspondence NOTES: D I
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c' Nll@SAQA U liKOOHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE. N.Y. 13202/TELEPHONE (315) 474-1511 August 7, 1985 (NMP2L 0465)
Mr. Walter Butler, Chief Licensing Branch No. 2 U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Butler:
Re: Nine Mile Point Unit 2 Docket No. 50-410 Enclosed is our proposed revision to Chapter 14 of the FSAR. We have had several informal telephone conversations with your staff concerning the scope of the revision. We anticipate incorporating this material in the FSAR in a future amendment, however, we request a meeting with your staff in the next 30 days. We expect that all outstanding questions can be resolved during this meeting, which will facilitate an expeditious review by your staff and keep the Unit 2 testing program on schedule.
In order to assist your review we have provided a complete version of Chapter 14 except for those Tables which have been deleted. The deleted Tables are:
14.2-2 thru 14.2-24, 14.2-26, 35, 37, 45, 66, 67, 70, 83, 84, 85, 87, 88, 89, 90, 91, 92, 93, 94, 96, 97, 98, 99, 111, 124, 127, 130, 205, 222, 229, 301, 401 and 402.
Also included in this package are draft revised responses to guestions 640.06, 640.08, 640.11, 640.13, 640.19, 640.22, 640.34, 640.34-2, and 640.35.
In addition we have included the appropriate revised pages of Table 1.8-1.
During our previous discussions, your staff raised some concerns regarding the adequacy of some of our proposed test acceptance criteria. We believe that we understand your concerns and we are working on revising these areas.
We will be prepared to present and discuss our proposed acceptance criteria during the review meeting with your staff.
Very truly yours, 8508130235 850807 ADOCK 05000410 PDR PDR p~ /n.'j. /(aa L GW/rl a Senior C. V. Mang Vice President i, zPJ gpss rye Enclosures o/ g+ /Pug xc: R. A. Gr amm, Project File (2)
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" U MOHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 Mr. Walter Butler, Chief Licensing Branch No. 2 U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Butler:
Re: Nine Mile Point Unit 2 Docket No. 50-410 Enclosed is our proposed revision to Chapter 14 of the FSAR. We have had several informal telephone conversations with your staff concerning the scope of the revision. We anticipate incorporating this material in the FSAR in a future amendment, however, we request a meeting with your staff in the next 30 days. We expect that all outstanding questions can be resolved during this meeting, which will facilitate an expeditious review by your staff and keep the Unit 2 testing program on schedule.
In order to assist your review we have provided a complete version of Chapter 14 except for those Tables which have been deleted. The deleted Tables are:
14.2-2 thru 14.2-24, 14.2-26, 35, 37, 45, 66, 67, 70, 83, 84, 85, 87, 88, 89i 90, 91, 92, 93, 94, 96, 97, 98$ 99, 111, 124, 127, 130, 205, 222, 229, 301, 401 and 402.
Also included in this package are draft revised responses to guestions 640.06, 640.08, 640.11, 640.13, 640.19, 640.22, 640.34, 640.34-2, and 640.35.
In addition we have included the appropriate revised pages of Table 1.8-1.
During our previous discussions, your staff raised some concerns regarding the adequacy of some of our proposed test acceptance criteria. We believe that we understand your concerns and we are working on revising these areas.
We will be prepared to present and discuss our proposed acceptance criteria during the review meeting with your staff.
Very truly yours, C. V. Mang Senior Vice President GW/rla Enclosures xc: R. A. Gramm, NRC Resident Inspector Project File (2)
Nine Mile Point Unit 2 FSAR TABLE ).8-1 (CONT)
Re lator Guide 1.58 Revision 1 Se tember 1980 Cont Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel FSAR Section 2.4 Position The Unit 2 project complies with the Regulatory Postion (paragraph C) of this guide through the alternate approaches described below and in Chapter 14.
BOP The quality assurance program for Unit 2 is currently in compliance with Regulatory Positions C.5, 7, 8, and 10 of this regulatory guide. Regarding Regulatory Position C:6 of this regulatory guide and Section 3.5, Education and Experience Recommendations, of ANSI N45.2.6-1978, the following alternatives are proposed for personnel education and experience for each level:
3.5.1 Level I Two years of related experience in equivalent inspection, examination; or testing activities, or
- 2. High school graduation/general education development (GED) equivalent and 6 months of related experience in equivalent inspection, examination, or testing activities, or
- 3. Completion of college-level work leading to an associate degree in a related discipline plus 3 months of related experience in equivalent inspection, examination, or testing activities.
Four-year college graduate plus 1 month of related experience or equivalent inspection, examination, or testing activities.
a Lhl as% MJa aa a,aua 64 of 169
<<8508130235-
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Nine Mile Point Unit 2 FSAR TABLE 1. 8-1 (Cont)
Re lator Guide 1.70, Revision 3 November 1978 Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants - LNR Edition Position The Unit 2 FSAR has been prepared following the format and content requirements contained in this regulatory guide, except in some cases where the content requirements were described or presented to conform to the Unit 2 established programs. The differences are not considered an exception as the material is presented in a manner consistent with the intent of this regulatory guide.
84 of 169
Nine Mile Point Unit 2 FSAR 14.2 SPECIFIC INFORMATION TO BE INCLUDED IN FSAR INITIAI TEST PROGRAM 14.2. 1 Summary of Test Program and Objectives The Nine Mile Point Unit 2 startup and test program consists of three phases which begin as systems and components and structures are nearing construction completion and ends with the rated power warranty run for the sCation.
The objectives of the startup and test program are as follows:
- l. Ensure that the construction of the plant is acceptable.
- 2. Ensure that the initial test program is properly completed and documented.
- 3. Demonstrate, to the extent practical, that the plant structures, systems, and components operate in accordance with their design and performance requirements.
- 4. Utilize and evaluate, to the extent possible, the plant procedures.
- 5. Provide training and hands-on experience to the plant operating and maintenance personnel.
- 6. Demonstrate, where practical, that the plant is capable of withstanding anticipated transients and postulated accidents.
- 7. Effect a safe and efficient fuel loading.
- 8. Bring the plant to rated capacity and sustained power operation.
The three major phases of the test program are intended to provide a 'ystematic and controlled approach to plant startup. The three phases, preliminary testing, preoperational testing, and startup testing, are described in the following paragraphs. All three phases are conducted under the direction of NMPC with the preliminary and preoperational phases administratively controlled by the startup administration procedures (SAPs) and the startup phase by the site administrative procedures (APs).
14.2-1
Nine Mile Point Unit 2 FSAR 14.2.1.1 Initial Test Program Phases The three phases of the initial test program can be summarized as follows:
- 1. Preliminary testing - tests performed subsequent to release of the equipment, system, or structure from construction. This test phase verifies proper installation and operation of equipment, systems, and where applicable, structures. Preliminary test activities may be categorized into two phases:
a ~ Component verification - includes cleaning, calibration, electrical logic and equipment tests, initial energizing, and equipment operation.
b.- System preparation - includes flushing and initial system operation;
- 2. Preoperational testing - performed after system turnover and usually prior to fuel load to verify that the performance of plant systems and components will meet applicable performance design and regulatory requirements. Two types of tests are included in the term preoperational testing:
a 0 Preoperational'ests - performed to provide verification that structures, systems, and components meet performance requirements and satisfy the design criteria to the extent possible. These tests are performed on safety-related systems as specified in Regulatory Guide 1.68, systems designated under the augmented Quality Assurance Program and other systems important to reactor safety or the safe shutdown of the reactor.
- b. Acceptance tests - similar to preoperational tests except they are performed on non-safety systems and are not specified in Regulatory Guide 1.68.
- 3. Startup testing - consists of fuel loading, precritical, low power, and power ascension tests that ensure fuel loading in a safe manner, confirm the design bases, demonstrate where practical that the plant is capable of withstanding the anticipated transients and postulated accidents, 14.2-2
Nine Mile Point Unit 2 FSAR and ensure that the plant is safely brought to rated capacity and sustained power operation.
14.2.1.2 Preliminary Testing Typically, preliminary tests include, but are not limited to:
Valves a ~ Inspect, adjust, packing and packing followers, check operator alignment, and verify lubrication.
- b. Verify and adjust motor-operated valve torque and limit switches, verify operation and control capability.
C. Verify setpoints or bench test relief and vacuum valves.
- 2. Piping
- a. Verify installation and adjust hangers and supports.
- b. Verify completion and/or complete integrity testing.
- c. Hydrostatic testing.
- d. "
Flow balancing.
- 3. Flushing/cleaning
- a. Includes general flushing, proof flushing, wipe tests, and coupon tests.
- b. May include low velocity flushes to rinse or chemically clean pipe, vessel and tanks or high velocity to remove foreign material.
Rotating equipment a ~ Check anchoring, align and lubricate as necessary.
- b. Confirm correct rotation.
C. Measure operating parameters.
14.2-3
Nine Mile Point Unit 2 FSAR
- 5. Electrical circuits a ~ Verify annunciator operation.
- b. Verify control and interlock logic.
C. Confirm equipment sizing.
- d. Verify installation, calibrate and set protective devices and relays and thermal overloads.
- 6. Instrumentation
- a. Calibrate instruments and process loops.
- b. Adjust setpoints.
- c. Verify instrument circuit continuity and operation.
14.2.1.3 Preoperational Test Phase The preoperational test phase commences after system turnover which normally occurs as construction and preliminary testing near completion. During this period, some preliminary testing may be ongoing in addition to the preoperational tests. Plant operating and surveillance procedures are used to the extent practical during the preoperational test phase to operate the systems and to support the test program. In some cases, interim operating procedures may be used to operate systems and equipment during the preliminary and preoperational phases to compensate for nonstandard system conditions and/or to debug the intended operating procedure.
During this period, systems are operated in accordance with the preoperational or acceptance tests in which system parameters are tested, adjusted and recorded in as many modes of operation as can be simulated. The systems are also operated in conjunction with other systems during integrated tests to verify performance characteristics under near-actual operating conditions. The following are some of the types of data that may be checked and recorded during a preoperational test:
- 1. Design characteristics.
- 2. System interlocks.
14.2-4
Nine Mile Point Unit 2 FSAR
- 3. Pump head, capacity.
- 4. System flows.
- 5. Heat-up characteristics, when attainable.
- 6. Tuning of system controls.
- 7. Response to simulated safety signals and/or loss of power.
- 8. Operating times.
This phase of testing verifies the ability of the plant to support fuel load and power operations.
14.2.1.4 Initial Startup Test Phase The initial startup test phase commences with the receipt of the operating license and the preparation for fuel load and extends through the 100-percent rated power/100-hr warranty demonstration. The initial startup test phase is divided into six testing plateaus: open vessel (including fuel loading), heatup, low power, medium power, full power, and ~
rated power warranty run. Testing performed during this phase of the program ensures that fuel loading is accomplished in a 'safe manner, confirms the plant design basis, demonstrates, to the extent possible, the plant' ability to withstand anticipated transients and postulated accidents and verifies that the plant can be safely brought to rated power and sustained power operations.
14.2.2 Organization and Staffing The Unit 2 startup and test organi"ation and interfaces to plant operations, SWEC, General Electric, and other selected NMPC organizations are snown in Figure 14.2-7 and are discussed in the following sections.
The Unit 2 operational organization is discussed in Chapter 13. The initial startup test phase is performed under the control of the Station Superintendent and coordinated by the Reactor Analyst. The responsibilities of the operations organization during the startup and test program are discussed in the following sections.
, Staffing levels during tne s=artup and test program will be commensurate with schedule and project needs and requirements.
Nine Mile Point Unit 2 FSAR 14.2.2.1 Startup and Test Organization and Responsibilities The startup and test organization, under the direction of the Startup Manager, has overall responsibility for the development, implementation, control, and conduct of the preliminary and preoperational phases of the Unit 2 test program. This organization is comprised of NMPC test engineers and technicians augmented by personnel from other NMPC organizations, Stone and Webster Engineering Corporation (SPEC), General Electric Company (GE), and others, as contractually established.
The Startup Manager reports to the Station Superintendent for the implementation and conduct of the test program and to the Project Director for startup and test activities in support of the project budget and schedule. During this period, the *Unit 2 staff supports the test program as directed by the Startup Manager. Upon receipt of the operating license the Startup Manager and his staff support fuel load and the power ascension program, as directed by the Station Superintendent and Supervisor Operations.
14.2.2.1.1 Station Superintendent The responsibilities of the Station Superintendent are discussed in Chapter 13. Additionally, included among his responsibilities, but not limited to, are the following startup and test program responsibilities:
Technical adequacy of the startup and test program and its compliance with NRC regulations and licensing commitments.
Approval of procedures during the startup test phase, as established in the technical specifications and APs.
- 3. Report test program status and problems to the NMPC General Superintendent Nuclear Generation.
Coordinate station department heads in their job assignments of plant staff to support and accomplish test program objectives.
- 5. Manage and di rect the startup test phase of the plant.
14.2-6
Nine Mile Point Unit 2 FSAR
~ 14.2.".1.2 2 2 Startup Manager The responsibxlitxes or. the Startup Manager include the following:
Chairperson of the Joint Test Group (JTG).
- 2. Develop plans, schedules, methods, procedures, and data systems for the testing and evaluation of all plant equipment and systems to permit acceptance and licensing.
- 3. Provide management direction to the startup and test, program, coordinate plant operations and all others involved in testing the plant to assure a thorough and efficient integration of the testing and operations efforts.
- 4. Manage and direct test program personnel relating to the attainment of startup and test program objectives.
- 5. Manage and direct assigned personnel in obtaining specifications and procedures to provide or as 1st the establ x shment oi quali tatzve and /or quant'ative acceotance criteria.
- 6. Provide recommendations, di spositions, and e ffect
~
corrective actions where equipment, system and/or program deficxencxes could adversely affect the performance oi safety-related functions.
7, Preparation and control of the Startup Administrative Procedures (SAPs).
- 8. Review and approval of preoperational tests and their results as the chairperson of the JTG.
- 9. Review and concur with all staffing requirements of the startup and test department.
- 14. ". ". 1. 3 Test Croup Managers Test Group Managers report to the Startup Manager. The responsibilities of a Test Group Manager include:
- 1. Represent the startup and test organization on the JTG.
14.2-7
Nine Mile Point Unit 2 FSAR
- 2. Assume the responsibilities of the Startup Manager as described in Section 14.2.2.1.2 and the SAPs during his absence and any other duties specifically delegated.
- 3. Directing the preparation of program status and other startup and test program related reports.
Develop, monitor, and coordinate the preparation and implementation of plans, schedules, methods, and procedures for testing and evaluation of plant systems and components for verification of performance and acceptance.
- 5. Manage, direct, coordinate and monitor the act'ivities-of test personnel and others performing tests or other test program activities during the Startup and Test Program.
- 6. Identify- problem areas and recommend and/or implement corrective actions where deficiencies could adversely affect the performance, safety-related functions or operating efficiency 'of plant systems or equipment.
- 7. Certification of test personnel.
- 8. Review and approval of preoperational and acceptance tests and their results as the startup and test member of the JTG, or as the designated alternate to the Startup Manager.
- 9. Review and approval of other test procedures and their results as procedurally established.
14.2.2.1.4 Lead Engineers Lead Engineers report to a Test Group Manager. The responsibilities of a Lead Engineer include:
- 1. Provide discipline expertise, guidance, and direction to test personnel and others.
- 2. Review and approve test procedures and their results as procedurally established.
14.2.2.1.5 Test Group Supervisors Test Group Supervisors report to a Test Group Manager. The responsibilities of a Test Group Supervisor include:
14.2-8
Nine Mile Point Unit 2 FSAR
- 1. Review and evaluate test procedures, test results, and other documentation as procedurally established.
- 2. Ensure that systems and equipment are properly tested and operated.
- 3. Provide direction and guidance to test personnel.
14.2.2.1.6 Test Engineers Test Engineers prepare and perform tests and inspections on plant systems and equipment, are responsible for all tests performed on their assigned systems, document deficiencies and their resolutions, provide corrective measures, methods and recommendations, as appropriate, for the correction of deficiencies and other problems. Test Engineers are assigned duties and certified commensurate with their technical background, experience, and prior satisfactory performance of assigned tasks.
A Level I Test Engineer generally assists other test engineers on their assigned systems. The extent of unassisted independent assignment is dependent on certification and past performance.
- 2. A Level II Test Engineer generally functions as a system engineer, performs all tests and inspections for which he is certified, and evaluates their results for acceptability and initiates corrective action, where appropriate.
A Level III Test Engineer performs the same functions as a Level II Test Engineer and additionally provides guidance and technical expertise to other Test Engineers and may provide reivew or approval of activities and their results as designated in the appropriate procedures or as delegated.
14.2.2.1.7 Test Support Personnel Test support personnel assist the system engineer or other Test Engineer in the performance of startup and test activities.
A Test Support Person, Ievel I, performs limited startup and test activities under the direction, direct control, and/or supervision of the Test Engineer. These activities may include, but are 14.2-9
Nine Mile Point Unit 2 FSAR not limited to, data recording, test setup, performance, or direction of approved test procedures. The Test Engineer or other certified individual verifies and/or monitors the entire activity performed and .assures that each step or portion was performed properly and is acceptable.
A Test Support Person, Level II, performs various tests and inspections based on certification and as directed by the Test Engineer. These activities do not require the Test Engineer to verify each step or portion of the activity. The Test Engineer monitors the process, provides overall direction, and determines the acceptability of the activity.
'I 14.2.2.2 Startup and Test Program Staff Organization and Responsibilities 14.2.2.2.1 Project Advisory Engineer The Project, Advisory Engineer (PAE) is the senior SWEC Advisory Operations Division (AOD) representative on site.
The PAE reports to the Startup Manager. The respon ibilities of the FAE include:
- 1. Provide technical support and liaison with AOD and SWEC engineering and other SWEC organizations.
Represent SWEC on 0he JTG.
- 3. Manage the SWEC AOD Cherry Hill Operations Center (CHOC) support.
14.2.2.2.2 Startup Adm nistrative Manager The Startup Administrative Manager reports to the Startup Manager and is responsible to manage and direct the startup and te st organization administrative, planning and scheduling, jurisdictional transfer. and turnover functions.
14.2-10
Nine Mile Point Unit 2 FSAR 14.2.2.3 Station Staff Responsibilities During the Startup and Test Program 14.2.2.3.1 Plant Operations Plant Operations consists of those personnel who operate Unit 2 under the direction of the Supervisor Operations, as described in Chapter 13. This group is responsible for the operation of plant equipment and systems during the startup and test program.
The startup test program is implemented by the plant operations department using procedures developed and approved in accordance with the Aps, These procedures are prepared by members of the station staff and others as required under the direction of the Station Superintendent.
Technical expertise from other organizations and GE is used whenever necessary.
14.2.2.3.2 Station Support Staff The station support staff consists of those station personnel who maintain Unit 2. Duties and general responsibilities are provided in Chapter 13. The station support staff, under the technical direction of the Station Superintendent, supports the startup and test program by maintaining all plant equipment, systems, and structures after release to NMPC and by providing technical assistance and manpower support to the extent practical.
The station staff assumes complete control and responsibility for the operation, testing and maintenance of Unit 2 at fuel load.
The Reactor Analyst is responsible to the Station Superintendent for ensuring that, all startup test phase procedures are written, reviewed, and approved; coordinating startup test phase testing; ensuring proper documentation of the startup test phase testing; and maintaining test results.
14.2 '.4 General Electric Company 14.2.2.4.1 Site Operations Manager The GE Site Operations Manager (SOM) is the senior NSSS vendor representative on site at or near fuel loading and is the official GE spokesman for preoperational and startup testing concerns and requirements. He coordinates with the
Nine Mile Point Unit 2 FSAR Station Superintendent and the Startup Manager for the performance of his duties, which include the following:
- 1. Review of all NSSS test procedures> including changes and results.
Provide administrative support and supervision to GE onsite personnel involved in the test program.
F
- 4. Represent GE on the JTG.
14.2.2.4.2 Operations Superintendent The GE Operations Superintendent is responsible to the GE SOM for the administrative and technical superyision of GE shift superintendents. The Operations Superintendent works directly with the NMPC Supervisor Operations and provides GE technical support to the operating organization.
14.2.2.4.3 Shift Superintendents The GE Shift Superintendents provide technical support to the Unit 2 shift operations personnel in the testing and operation of GE supplied systems. They provide 24-hr/day shift coverage as required, beginning with fuel loading, and report to the GE Operations Superintendent.
14.2.2.4.4 Lead Engineer Startup Test, Design and Analysis (STD&A)
The GE Lead Engineer STD&A is responsible to the GE SOM for supervising the GE STD&A engineers, verifying core physics parameters and characteristics, and documenting that the performance of the NSSS and its components conform to acceptance criteria. He works with the Reactor Analyst or his representative to coordinate and effect implementation of the startup test program, including any special testing required to confirm these acceptance criteria.
14.2.2.4.5 GE Startup, Test, Design and Analysis Engineers The GE STD&A engineers assist in the execution of the initial startup test phase.
- 14. 2-12
Nine Mile Point Unit 2 FSAR
- 14. 2. 2. 5 Joint Test Group Membership and Responsibilities The Joint Test Group (JTG) is a committee representing organizations responsible for the content, conduct and/or results of startup and test program activities during the preliminary and preoperational phases of the startup and test program. The JTG provides a coordinated independent technical review of procedures and their results, resolution to unacceptable items, identification of which item or items must be repeated or performed in addition to completed items or procedures to satisfactorily complete the test or activity. Some of the specific responsibilities of the JTG include:
- 1. Approval of all preoperational and selected preliminary test procedures and their revisions
- 2. Approval procedures.
'f (see Section 14.2.3.2).
the results of all preoperational test
- 3. Ensuring the adequacy of test procedures and methods.
- 4. Ensuring that test procedures meet the requirements of the FSAR ~
- 5. Approval of any contractor test procedures and their results when used to satisfy startup and test program requirements on safety-related systems.
- 6. Approval of the results of preliminary test procedures which satisfy preoperational test acceptance criteria.
The JTG membership and their individual responsibilities consist of the following:
14.2.2.5.1 Startup Manager The Startup Manager is the chairman of the JTG. He is responsible to convene and conduct the meetings and to attempt to achieve a consensus from its membership.
14.2-13
Nine Mile Point Unit 2 FSAR 14.2.2.5.2 Startup and Test A Test Group Manager represents the startup and test organization and is responsibl'e for providing a technical review of the proposed activities, documents and their results, The Test Group Manager serves as Chairman during the absence of the Startup Manager.
14.2.2.5.3 Plant Operations Representative The Plant Operations Representative provides an operational review of the proposed activities, documents and their results. He additionally ensures that plant operating, emergency, and surveillance procedures are available as required to support the startup and test program.
14.2.2.5.4 NMPC Site Technical The NMPC Site Technical Representative is responsible to review the JTG items for '"compatability with license commitments, general design requirements, technical specifications, surveillance, and operational'ssessment requirements. He additionally acts as liaison to the SORC, obtains SORC reviews as necessary, and communicates any SORC comments to the JTG.
- 14. 2. 2. 5. 5 Stone and Webster Engineering Corporation PAE represents SWEC on the JTG and is responsible
'he for the SWEC engineering review of preoperational test acceptance criteria and other items within SWEC's scope of design.
14.2.2.5.6 General Electric Company The GE .Site Operations Manager represents GE on the JTG and is responsible for JTG agenda items within GE's scope of design for compatability with GE requirements.
14.2.2.5.7 Conditional Members Conditional members are representatives from any organization having responsibility and/or expertise in an area of the JTG meeting agenda.
In this situation, the representative Will be requested to attend the meeting by the JTG Chairman.
14.2-14
y l I
Nine Mile Point Unit 2 FSAR 14.2.2.6 Unit 2 Support of the Startup and Test Program 14.2.2.6.1 Unit 2 Project Management The Unit 2 project management organization is managed and directed by the Project Director and is described in the PSAR. Support to the startup and test program is provided through the various project groups. Included in this support are such functions as:
- 1. Preparation, review, approval, and maintenance of the integrated project schedules.
- 2. Completion of construction activities in preparation for release and turnover of systems to NMPC.
- 3. Design control and control of design documents.
14.2.2.6.2 NMPC Quality Assurance Pro'ect ualit Assurance The NMPC Project Quality Assurance Organization is described in the PSAR. Additionally, the Project QA organization supports the startup and test program by reviewing and noting any outstanding construction QA documents associated with equipment and systems being turned over construction to NMPC and surveillance and/or reviewing documentation of activities performed on equipment released to NMPC.
ualit Assurance Nuclear The Quality Assurance-Nuclear Organization is described in Chapter 17.
14.2.2.6.3 Stone and Webster Engineering Corporation SWEC provides engineering services required for construction, system release and turnover, testing, and design-related problems discovered during the startup and test program. Additionally, SWEC reviews preoperational test procedure acceptance criteria and other items within their scope of design through the SWEC PAE.
14.2.2.6.4 General Electric Company The General Electric Company is the supplier of the BWR nuclear steam supply system (NSSS) for Unit 2 and is responsible for generic and specific Unit 2 designs and the 14.2-15
Nine Mile Point Unit 2 FSAR supply of the NSSS. During the construction phase, the GE Resident Site Nanager is responsible for all NSSS equipment disposition.
14.2.2.7 Site Operations Review Committee The Site Operations Review Committee (SORC) is described in Chapter 13 and provides direction to the startup and test program by performing the following:
- 1. Review and approval of the SAPs governing the organizational makeup and responsibilities of the startup and test organi ation and the JTG.
- 2. Rcvla1w oi - y~Lem pre:opc.rat ion~1 t.ac;t. rc.c u I Lu uL't c:r JTG approval for system acceptance and readiness to support plant operation.
- 3. Review and acceptance of initial startup test procedures and their results.
Authori" ing the progressive levels of the power ascen ion program.
- 14. ". 2. 8 Qual i fications 14.2.2.8.1 General Personnel performing startup and test program activities are selected for their positions based on procedural requirements and as determined by the Startup Manager.
I Related experience and training may be used to satisfy academic and experience requirements of each position/level on a one for one basis. However, when required, thiS time or training may not be used to satisfy other areas of qualification requirements.
14.2.2.8.2 Evaluation for Certification When each individual is evaluated for certification and qualification, the following criteria are considered and where appropriate. noted on the individual's certification form:
Previous experience in the nuclear or related industry.
Candidate' past performance.
Nine Nile Point Unit 2 FSAR
- 3. Demonstration of capability by actual performance, while under the guidance of a individual certified in the area(s), to evaluate the individual' ability to be certified to perform independently.
- 4. Oral and/or written exams.
- 5. Training and education.
- 6. Other factors/criteria, as appropriate.
Details for the certification of startup and test personnel during preliminary and preoperational testing are contained in the SAPs. During the startup test phase, all personnel are certified in accordance with the methods described in Section 14.2.2.8.9.
14.2.2.8.3 Startup Manager The minimum qualifications of the Startup Manager (Level III) are a Bachelor's degree or equivalent in Engineering or related field and 10 years experience in power plant operations or testing, or an associate level education or equivalent and 12 years experience in power plant operations or testing. At least seven years should be nuclear.
Previous experience in testing and supervisory/management roles during a preoperational test program is mandatory.
The Startup Manager must have a good understanding of regulatory requirements, codes, and standards and must have the ability to communicate effectively in an oral and written capacity.
14.2.2.8.4 Test Group Manager The minimum qualifications of a Test Group Manager (Level III) are a Bachelor's degiee or equivalent in Engineering or related field and eight years experience in power plant operations or testing, or an associate level education or equivalent and ten years experience in power plant operations or testing. At least five years should be nuclear. Previous . experience in testing and supervisory/management roles during a preoperational test program is mandatory. A Test Group Manager must have a good understanding of regulatory requirements, codes, and standards and must have the ability to communicate effectively in an oral and written capacity.
14.2-17
Nine Mile Point Unit 2 FSAR 14.2.2.8.5 Lead Engineer The minimum qualifications of a Lead Engineer (Level III) are a Bachelor's degree or equivalent in Engineering or related field and seven years experience in power plant operations or testing or an associate level education or equivalent and nine years experience in power plant operations or testing. At least four years should be nuclear. - Previous experience in testing and supervisory/management roles during a preoperational test program is desirable. A Lead Engineer must have a good understanding of regulatory requirements, codes and standards related to his field or discipline and must have the ability to communicate effectively in an oral and written capacity.
14.2.2.8.6 Test Group Supervisor The minimum qualifications of a Test Group Supervisor (Level III) are a Bachelor's degree or equivalent in Engineering or related field and five years experience in power plant operations or testing, or an associate level education or equivalent and seven years experience in power plant operations or testing. At least three years should be nuclear. Previous experience in a testing role during a preoperational test program is desirable. A Test Group Supervisor should have a good understanding of regulatory requirements, codes and standards and must have the ability to communicate effectively in an oral and written capacity.
14.2.2.8.7 Test Engineers Test En ineer Level I The minimum qualifications, of a Test Engineer (Level I ) are a Bachelor's degree or equivalent in engineering or related field, or an associate level education or equivalent and two years experience in power plant operations or testing. A Test Engineer, Level I, should have a general understanding of regulatory requirements, codes and standards as related to his activities and discipline and must have the ability to communicate effectively in an oral and written capacity.
Test En ineer Level II The minimum qualifications of a Test Engineer (Level II) are a Bachelor's degree or equivalent in engineering or related field and two years experience in power plant operations or testing, or an associate level education or equivalent and four years experience in power plant operations or testing.
14.2-18
Nine Mile Point Unit 2 FSAR Previous experience in a testing role during a preoperational test program is desirable. A Test Engineer, I.evel II, should have a general understanding of regulatory requirements, and a good understanding of codes and standards as related to his activities and discipline and must have the ability to communicate effectively in an oral or written capacity, Test En ineer Level III The minimum qualifications of a Test Engineer (Level III) are a Bachelor's degree or equivalent in engineering or related field and four years experience in power plant operations or testing, or an associate level education or equivalent operations nuclear.
'r and six years experience in power plant testing. At least two years should be Previous experience in a testing role during a preoperational test program is desirable. A Test Engineer, Level III, should have a good understanding of regulatory requirements, codes and standards as related to his activities and discipline and must have the ability to communicate effectively in an oral or written capacity..
14.2.2.8.8 Test Support Personnel Level I The minimum qualifications of a Level I are a High School Degree or GED equivalent. Technical training or some on the job training for a particular discipline is desirable. A Test Support Person, Level I, should have a general understanding of the administrative and technical procedures and requirements, and any codes and standards relative to his activities and discipline and must have the ability to communicate effectively in an oral or written capacity.
Level II The minimum qualifications of a Level II are a High School degree or GED equivalent and either technical training in a particular discipline and three years experience in power plant operations or testing, or five years-on-the job training for a particular discipline, and have demonstrat'ed the ability to perform the activities for which they will be certified. A Test Support Person, Level II, should have a good understanding of the administrative and technical procedures and requirements, and any codes and standards relative to his activities and discipline and must have the ability to communicate effectively in an oral or written capacity.
14.2-19
Nine Mile Point Unit 2 FSAR 14.2.2.8.9 Plant Personnel Operating, maintenance or other unit or site personnel when etc performing normal plant operating, maintenance, activities are qualified in accordance with the requirements discussed in Chapter 13 and Section 1.8.
When plant unit or site personnel perform startup and test activities as described in the startupand administrative certified in procedures they shall be qualified accordance with their requirements.
14.2.2.8.10 Joint Test Group JTG members are qualified to perform the duties and responsibilities of the JTG by their respective position qualifications and certifications.
h 14.2.2.9 Certification of Test Personnel 14.2.2.9.1 Certification Authorities The Startup Manager is certified by the Station Superintendent and approved by the General Superintendent Nuclear Generation; Test Group Managers are certified by the Startup Manager and approved by the Station Superintendent.
All other startup and test personnelStation are certified by a Test Group Manager and approved by the Superintendent or Startup Manager.
14.2.2.9.2 Certification Startup and test personnel are evaluated and certified based on the criteria and methods described in the SAPs. Each certification describes the area and level to which each individual is certified.
14.2.2.9.3 Recertification Recertification and reevaluation of startup and test personnel are conducted, as a minimum, on a yearly basis.
14.2.3 Test Procedures 14.2.3.1 Test Procedure Development; and General Information The Unit 2 SAPs establish the methods for preparing, approving, revising and controlling preliminary, preoperational and acceptance test procedures. The site 14.2-20
Nine Mile Point Unit 2 FSAR administrative procedures (APs) establish the methods for preparing, approving, revising and controlling initial startup test procedures. Both also define and specify procedure content, format and style guidelines.
Test procedures are developed by startup and test, site/unit personnel and others, as required, utilizing the appropriate design documents, vendor information, codes, standards, etc.
in order to provide detailed methods to anddemonstrate structures the to capability of the equipment, systems perform their design functions.
14.2.3.1.1 Plant Procedures The following program outlines the qualification and interface of plant operating procedures with the test procedures utilized during the startup and test program:
- 1. If required, procedures to operate equipment and systems and to support testing will have been prepared and approved before preoperational testing begins on the associated system using the best information currently available from the principal designer and responsible equipment suppliers.
- 2. Preoperational test procedures will utilize these procedures as nearly as possible (see Section 14.2.9).
Plant procedures required to support startup 3.
testing will be updated and revised, drafted, developed, and approved utilizing the if previously results of preoperational testing, including the use-testing of plant procedures where practical, before startup testing of the applicable systems.
Exceptions will be those plant procedures required to be verified during the startup test phase.
4, Startup test procedures will either be updated, if already drafted, or developed utilizing the results of preoperational testing and the updated plant procedures.
14.2.3.2 Preliminary Test Procedures Preliminary test procedures are developed and used to initially verify equipment, 1.2.
systems, and structures format as content described in Section 14 ~ 2 ~ The and requirements are similar to preoperational test procedures and are described in the SAPs.
14.2-21
0
'I
Nine Mile Point Unit 2 FSAR luminary t re 1 a" t pc'occ~dur e 'Lhd - el e ut ' <<d 1 .". ~ vc:r f y L
<<i <ty- elo a preoperatxonal test procedure acceptance L te~i tulL~ o'on~ uL ei>u~pm~nt ul wlilin w ~
l l 4~ u .cJ to satisfy criteria and revisions are procedures reviewed and approved by the JTG; all other prelzmznary test are approved by a Test Group Manager.
14.2.3.3 Preoperational and initial Startup Test Procedures Preoperational and initial startup test procedure content is similar to that described in Regulatory Guide 1.68, the format, varies but all the elements discussed in the guide are included.
All Preoperational test procedures and their revisions are reviewed by 'the Quality Assurance - Nuclear Department for any applicable quality requirements.
All preoperational tests are approved by the JTG.
A].l startup test procedures and their revisions are approved by the General Superintendent Nuclear.
Review and approval of preoperational and startup te t, procedures is controlled in accordance with the respect vely. SAps'Ps, Figure 14. 2 shows the review and approval cyc] e for preliminary and preoperatxonal test procedures and igure 14. 2-2 shows the review and approval cycle of initial startup test procedures.
14.2.4 Conduct of Testing 14.2.4.1 Preliminary Test'g Preliminary testing is conducted in accordance with the SAps under tpe controI of Unit 2 Startup and Test Department subsequent to reIease of equipment, system, or structure from construction.
This test pnase ve i fme proper installation and operation of equipment, systems, and where applicable, structures. At the txme of 'he ini ti al equipment run, the equipment and systems are operated by plant operations personnel as dz rected by the Test Engineer. Subsequent operation is under the control of the Station Shift Supervisor (SSS). To support test activities, these operations may be under the general direction of the Test Engineer. During these operations, operating parameters for equipment will be 14.2-22
Nine Mile Point Unit 2 FSAR monitored and recorded as necessary in accordance with the system operating procedures, interim operating procedures, or as determined by the SSS and/or Test Engineer to ensure that the operating envelopes of the equipment are not, inadvertently exceeded.
I Preliminary test procedures may be generic or specific type procedures. Generic tests are performed repetitively on groups or types of components and equipment. The range and installed systems may vary but the basic test method remains the same. During the performance of generic procedures the step-by-step details and sequence are determined by the Test Engineer. Specific procedures are applied to a limited scope and provide greater detail than generic procedures.
Test results obtained during preliminary testing may be used in place of'etesting during preoperational testing provided the preliminary test and its results are approved the JTG.
These preliminary tests shall be identified in the preoperational test procedure.
14.2.4.2 Preoperational Testing Preoperational testing on a system commences after the required preliminary testing of individual equipment, subsystems, or systems is completed. Testing is performed with preoperational test procedures approved in accordance with the SAPs.
Since a significant period of time may have elapsed between the time a preoperational test, was approved and the time the test is to be performed, the test is reviewed prior to initiating the test; any changes in the equipment or system since the procedures approval are researched and the procedure revised as necessary in accordance with 14.2.3.3.
The procedure may then be approved for performance by the Startup Manager.
14.2.4.2.1 Pretest Review Approval by the Startup Manager to perform a preoperational test requires completion of a pretest review. This review includes, as a minimum, the following elements:
Review of the status of the procedurs (operating or other) required to support the test. The Startup Manager shall be notified if is unavailable to support the test.
a required procedure Attaching a copy of the system flow diagram for mechanical systems or an electrical one-line 14.2-23
Nine Mile Point Unit 2 FSAR diagram for electrical systems marked up with any design changes that are installed in the field but not yet incorporated on the drawing, to show system design configuration at the time of the test.
- 3. Check to ensure that the test prerequisites can be met.
14.2.4.2.2 Test Performance Res onsibilities
- 1. Implementation and scheduling all tests is the responsibility of the Startup Manager.
- 2. The performance of the test procedure, its direction, coordination and verification is the responsibility of the Test Director..
- 3. The responsibility for operation of systems and equipment, coordination of in process tests, maintaining and controlling plant operating status and assignment of operating personnel to assist in performance of the test procedures rests with the plant operations group through the on-duty SSS.
In emergencies, the Test Director or SSS are authorized to depart from approved procedures where necessary to prevent injury to personnel or the public or to prevent damage to the facility and its equipment.
Pretest and Preshift Briefin s Prior to test commencing, the Test Director and SSS discuss the test, its effects on other systems, control room indications, alarms, expected start and stop times, and any other factors that may influence test performance or plant conditions.
When the personnel that are to be involved in the test are assembled, the Test Director and SSS, if available, shall conduct a pretest briefing to explain the test and the involvement required of all participating personnel.
Additional briefings and updates are conducted for oncoming shift personnel and at other times as necessary during test performance by the Test Director.
14.2-24
Nine Mile Point Unit 2 FSAR Reverification of Prere isites Following a test interruption which results in a halt in testing during a preoperational test, the Test Director shall review the test prerequisites for possible reverification. The results of the review entered in the test summary and any reverified prerequisites listed.
Preo erational Test Summar A preoperat'ional test summary shall be prepared by the Test Director for all preoperatzonal test procedures. The test summary includes significant events during the test, a description of any problems found during the test and reference to their resolution, any reverification of prerequisit'es required and an evaluation of the test results with reference to the acceptance criteria. This shall in particular note if any acceptance criteria'ave not been met. The test summary is attached to the record copy of the test procedure.
14.2.4.3 Initial Startup Testing Startup testing is conducted by personnel from plant operations, startup and test, GE, and groups as required under the direction of the on-duty SSS in accordance with the APs.
During this phase, plant operating procedures are utilized in conjunction with the approved test procedures.
The final authority to start, continue, or end a test is the responsibility of the SSS after all required approvals have been obtained.
The master tracking system is used to ensure that prerequisites for initial fuel loading and the beginning eachof initial startup testing are fulfilled. In addition, individual startup test procedure specifies prerequisites that must be validated prior to test performance. The on-duty SSS and respective test personnel ensure that all prerequisites are satisfied prior to performance of any initial startup test.
14.2.4.4 Modifications to Test Procedures During Testing 14.2.4.4.1 Preliminary Tests Due to their nondetailed nature, field revision of generic preliminary tests is not applicable.
14.2-25
Nine Mile Point Unit 2 FSAR During performance, any changes to a specific preliminary test procedure that changes the intent, scope, or acceptance criteria of the test are made on a field revision form (FRF) prior to implementation of the change in accordance with the SAPs.
14.2.4.4.2 Preoperational Tests During performance, no changes may be made to the procedure that change the intent, scope or acceptance criteria of the test without the prior approval of the JTG. These changes are made on an FRF in accordance with the SAPs. The Test Director may elect to perform unaffected sections of the test while awaiting resolution from JTG, provided test sequence is not mandatory.
Other exceptions and minor corrections to the test procedure are authorized in accordance with the SAPs.
14.2.4.4.3 Startup Tests Modification to initial startup test procedures are classified as major, or minor changes. A major change changes the intent of the procedure and requires development of a revision to the procedure. Such a revision requires approval of the organizations that originally approved the test procedure. When a procedure in progress cannot be followed or completed and a major change to the procedure is required, the test is held at that point, the system placed in a stable condition, and the necessary approvals obtained in accordance with the APs prior to continuing the test.
Minor changes do not change the intent of the test procedure and may be made with the concurrence of the duty SSS at the time the test is run. Ninoi changes to procedures are made in accordance with the APs which detail the method of entry of the change and the required approvals.
14.2.4.5 Modifications and Deficiencies 14.2 '.5.1 Preliminary and Preoperational Phases The SAPs contain administrative controls for identifying, reporting, and tracking of deficiencies and modifications during these phases.
Changes to plant system and equipment design .are reviewed and approved in the same manner as the original design by the approved design organization.
- 14. 2-26
0 I
Nine Mile Point Unit 2 FSAR Deficiencies not requiring a change to the plant design are reviewed, resolved, approved, and corrected by the appropriate personnel in accordance with the SAPs.
To ensure the validity of test results during these phases, work on equipment after preliminary testing is administratively controlled by the SAPs. Control is accomplished by the use of work control documents and equipment tagging. The work control documents establish the scope, inspection and retesting required to complete the activity. Tagging is utilized to alert personnel that the equipment may be tested and in service and will require authorization prior to performing any work affecting the equipment.
14.2.4.5.2 'nitial Startup Test Phase Modifications and deficiencies during this phase are handled in accordance with the requirements established for the operational phase described in Chapter 13 and controlled in accordance with the APs.
14.2.5 Test Procedure Results Review and Approval 14.2.5.1 Preliminary Test Procedures The Test Engineer reviews the results of each preliminary test to ensure it meets the requirements noted on Where the data sheet and/or procedure acceptance criteria. test results are unacceptable, the Test Engineer shall initiate steps to obtain corrective action as described in the SAPs.
A Lead Engineer reviews the results of all preliminary tests and approves the results of all generic preliminary tests.
A Test Group Manager approves the results of all nongeneric preliminary test procedures.
Preliminary test results which require JTG approval are attached to their associated preoperational test for review and approval during the review and approval of the preoperational test results.
14.2.5.2 Preoperational Test Procedures Completed preoperational test procedures are reviewed in accordance with the SAPs.
After the initial review, the preoperational test is submitted to the JTG for review and approval.
14.2-27
Nine Mile Point Unit 2 FSAR When the preoperational tests for a system are complete and approved by the JTG, the completed procedures are submitted to the SORC and Station Superintendent for review and acceptance.
Figure 14.2-3 shows the review and approval cycle for preliminary and all preoperational test results.
14.2.5.3 Initial Startup Test Procedures The various startup test plateaus are described in Section 14.2.10. Startup test conditions are shown 'in Figure 14.2-5. The decision to proceed from one startup test plateau to the next will be based upon successful completion of the tests and the discretion of the SORC and General Superintendent Nuclear Generation. Any required retesting is determined during the review cycle. If a startup test is not fully acceptable, the SORC and General Superintendent Nuclear Generation can approve the procession to the next plateau in accordance with the APs.
The review and approval cycle for initial startup test procedure results is controlled in accordance with the APs and is shown in Figure 14.2-4.
14.2.6 Test Records Test records and procedures are kept in accordance with the SAPs and APs which contain the generic procedures for filing and record keeping to be applied to test documentation.
14.2.7 Conformance of Test Program with Regulatory Guides The Unit 2 startup and test program complies with the intent of the following regulatory guides with exceptions as noted or described in the appropriate sections of the FSAR. Areas where the guide(s) do not apply are not considered exceptions.
Re ulator Guide 1.9 - See Section 8.3.
Re ulator Guide 1.20 - The alternative approved for vibration testing of reactor internals will be in accordance with the provisions of Regulatory Guide 1.20 for nonprototype Category I plants.
Re lator Guide 1.22 - See Chapter 7.
Re ulator Guide 1.30 - See Chapter 17.
14.2-28
Nine Mile Point Unit 2 FSAR Re lator Guide 1.52 - The standby gas treatment system (SGTS) will be tested in accordance with Regulatory Guide 1.52 as described in Table 14.2-77. The design of the SGTS is described in Section 6.5.1. Alternative methods used to meet the intent of the regulatory guide are discussed in Section 1.8.
Receulatorg Guide 1.58 Startup and test personnel involved in testing meet the requirements of Regulatory Guide 1.58 and ANSI 3.1-1978 with exceptions as discussed in this chapter.
Unit 2 plant personnel meet the requirements of this regulatory guide as discussed in Chapter 13 and Section 1.8.
GE startup 'operations personnel supporting the startup test phase meet the requirements of this regulatory guide as discussed in Section 1.8 and Table 14.2-403.
Re ulator Guide 1.68 - Unit 2 complies with this regulatory guide with the exception of the format as described in Appendix C. The difference is not considered an exception however, as the guide specif ies required elements while merely implying a format.
Re ulator Guides 1.68.1 and 1.68.2 - Unit 2 complies with Regulatory Guides 1.68.1 (Tables 14.2-27, 30, and 31) and 1.68.2 (Table 14.2-104).
Re lator Guide 1.68.3 Unit'2 complies with Regulatory Guide 1.68.3 as described in Section 1.8.
Re lator Guide 1. 108 - Unit 2 complies with Regulatory Guide l. 108 with the exception of the sequence discussed in Regulatory Position C. 2. a. (5) . Unit 2 will comply with the intent of this position by noting the stabilized operational parameters of the diesel generators at the completion of the test described in C.2.a.(3) during the diesel generator preoperational tests (Tables 14.2-125 and 126). Prior to performance of one the sections of the loss of power preoperational test (Table 14.2-129) in which the requirements of C.2.a.(2) will be verified, the diesel generators will be started, loaded and allowed to run until the same operating parameters have been reached and stabilized. The units will then be shutdown and the test performed while the equipment is 'still at operating temperatures.
Re lator Guide 1.128 - See Section 8.3.2.
14.2-29
Nine Mile Point Unit 2 CESAR 14.2.8 Utilization of Reactor Operating and Testing Experience in Development of Test Program Since every reactor/plant in a GE BWR product line is an evolutionary development of the previous plant in the product line (and each product line is an evolutionary development from the previous product line), it is evident that the current plants have the benefits of experience associated with the successful and safe starting of 25 or more previous BWR plants. The operational experience and knowledge gained from these plants and other reactor types has been factored into the procedures related to the startup and test program.
Additionally, a committee of NMPC operations technical staff and staff engineers (technical services review) reviews reactor operating and testing experiences'he group routinely reviews licensee Event Reports, information from the Nuclear Plant Reliability Data System (NPRDS), NRC ISE Bulletins, NRC Circulars, and NRC, INPO, and NSAC Information Reports. This group reviews test procedures for the startup and test program through the technical staff representative to the JTG and SORC. These same individuals continue to provide input to operations management after commercial operation.
14.2.9 Trial Use of Plant Operating and Emergency Procedures To the extent practical . throughout the startup and test program, test procedures= utilize operating and emergency procedures where applicable in the performance of the tests.
Additionally, after the equipment and systems have been initially tested and placed in service to support other test activities these procedures are utilized as applicable and to the extent consistent with the completion status of the equipment and system. The use of these procedures is intended to achieve the following:
- 1. Prove the specific procedure or identify where changes may be required.
- 2. Provide training of plant personnel in the use of these procedures.
- 3. Increase the level of knowledge of plant personnel of the systems being tested.
Test procedures may use these operating and emergency procedures by referencing the procedure directly or by extracting a series of steps from the procedure or they may 14.2-30
0 Nine Mile Point Unit 2 FSAR use a combination of both methods. A description and summary of plant procedures and a schedule for their development are given in Section 13.5.
14.2. 9. 1 Interim Operating Procedures ( IOPs)
IOPs are utilized to trial test the station operating procedures and to allow operation of systems in nonstandard configurations during the test program due to incomplete testing or construction. IOPs are reviewed, approved, and revised in accordance with the SAPs.
14.2.10 Initial Fuel Loading and Initial Criticality 14.2.10.1 Fuel Loading and Shutdown Power Level Tests Fuel loading and initial criticality are conducted in accordance with written procedures after the applicable prerequisite tests have been satisfactorily completed and an operating license has been issued. In the actual sequence for performing startup tests (SUTs) the tests are grouped into plateaus. All tests within a plateau will be completed, or justification given for exceptions, before proceeding to the next plateau (Sections 14.2.4.3 and 14.2.5.3) ~ All exceptions must indicate a point at which resolution must occur before the test proceeds, The normal sequence of tests within the program is as follows:
- 1. Core performance analysis.
- 2. Steady-state testing.
- 3. Control system tuning.
- 4. Major trips.
The actual testing sequence can vary from the recommended test sequence because of equipment problems and other considerations. Prior to approving fuel loading, certain actions must be verified by the steps in the following sections, which are performed at the completion of most of the preoperational testing.
14.2-31
Nine Mile Point Unit 2 FSAR 14.2.10.1.1 Loss of Power Demonstration - Standby Core Cooling Required (Table 14.2-129)
This test demonstrates the capability of the emergency diesel genera-tors to start automatically and assume all of the emergency core cooling loads in a loss of normal auxiliary power and the capability of the off-site power system to supply power to start and run emergency core cooling and selected normal loads during a simulated LOCA condition.
14.2.10.1.2 Cold Functional Testing Cold functional testing is defined as an integrated system operation of various plant systems that can be operated prior to fuel loading. The intent is to observe any unexpected operational problems from either an equipment or a procedural standpoint and to provide an opportunity for further operator familiarization with the system operating procedures under operating conditions.
Some cold functional testing is accomplished during the preoperational test program. For example, integrated and simultaneous operation of the following systems may take place duirng the flush of the total system: condensate system, condensate demineralizer system, low pressure coolant 'njection (LFCl) system, core spray systems, reactor water cleanup (RHCU) system, service water systems, turbine building closed cooling water (TBCLCW) system, reac- r building closed cooling water (RBCLCW) system, and others.
As required, additional integrated system performance will be demonstrated prior to fuel loading.
14.2.10.1.3 Routine Surveillance Testing Because the interval between completion of a preoperational test on a system and system operation may be of considerable length, a number of routine surveillance tests must be performed prior to ruel loading and must be . repeated on a routine basis. The Technical Specifications (Chapter 16) detail the test frequency. In general, this surveillance test program is instituted prior to fuel loading by the plant operating staff.
14.2.10.1.4 Master Tracking System (MTS) detailed list of items that must be completed, including the preoperational tests, work requests, design changes, and proper disposition of all exceptions noted during preoperational testing listed in Table 14.2-1, is rechecked to verify completion prior to the final approvals for fuel loading and for those items required, at each significant 14.2-32
Nine Mile Point Unit 2 FSAR new step such as heatup, opening main steam isolation valves (MSIVs), and turbine generator operation.
14.2.10.1.5 Initial Fuel Loading (Open Vessel Plateau)
Fuel loading requires the movement of the full core complement of assemblies f rom the fuel pool to the core, with each assembly identified by number before being placed in the correct coordinate position. The procedure controlling this movement is arranged so that operability checks of installed neutron instrumentation are made at predetermined intervals throughout the loading, thus demonstrating reliable monitoring capability to ensure subcriticality is maintained throughout fuel loading. A complete check is made of the fully loaded core to ascertain that all 'assemblies are properly installed, correctly oriented, and occupying their designated positions.
14.2.10.1.6 Zero Power Level Tests (Open Vessel Plateau)
At this point, a number of tests are conducted that are best described as initial zero power level tests. Chemical and radiochemical tests are made in order to check the quality of the reactor water before and after fuel loading and to establish base and background levels that are required to facilitate later analysis and instrument calibrations.
Plant and site radiation surveys are made at specific locations for comparison with the values obtained, at the subsequent operating power levels. Shutdown margin verification is made for the fully loaded core. Criticality is achieved with each of the two prescribed rod sequences, during which data are recorded for each rod withdrawn. Each control rod drive (CRD) will have been scrammed during a previous vessel 1,000-lb hydrostatic test with selected drives timed at two intermediate reactor pressures and for different accumulator pressures, and will undergo additional performance testing. The initial'etting of the
'intermediate range monitors ( IRMs) is at maximum gain.
14.2.10 2 Initial Heatup to Rated Temperature and Pressure
~
Heatup follows the satisfactory completion of the fuel loading and zero power level tests (Sections 14.2.10.1.5 and 14.2.10.1.6) and further checks are made of coolant chemistry together with radiation surveys at the selected p'lant locations. Selected CRDs are scram- timed at rated temperatures and pressures. The process computer checkout continues as more process variables become available for input. The reactor core isolation cooling (RCIC) system will undergo controlled starts at low reactor pressure and 14.2-33
,Nine Mile Point Unit 2 FSAR at rated conditions, with testing in the quick-start mode at 1,000 psxg.'orrelations are obtaznea between reactor vessel temperatures at several locations and the values of other process variables as heatup continues. The movements of NSSS piping in the drywell, mainly as a function of x ansi.on are recorded for comparison with design data.
expans
].4.2.10.3 Power Testing from 25 to 100 Percent of Rated Output The power test phase comprises the following,tests, many of which are repeated several times at the different zest, l'evels. While a certain basic order of testing is maintained relative to power ascension, there is, nevertheless, considerable flexibility ia the test sequence at a particular power level which may be used whenever becomes operationally expedient. In no instance, however, it is nuclear safety compromised.
Coolant chemistry tests and radiation surveys are made at each principal test level to preserve a safe and efficient power increase.
Selected CRDs are scram-timed at various power levels to provide c= relation w'h the initial data.
- 3. The effect of control rod movement on other.
parameters (e. g., electrical output, steam flow, =
and neutron flux level) as examined for different power cond'ions.
- 5. At each major power level ( 5,. 50, 75 and 100 percent), the local power range monitors (f.PBNs) are calibrated.
The APRNS are calibrated 'nitially at each new power level'and .following LPRM ca'ibration.
Completion of the proces compute checkout, is made for all variables, and the various options a e compared with independent calculations as soon as significant power levels are available.
Nine Mile Point Unit 2 ESAR
.Collection of data from the system expansion tests xs completed for those piping systems that have not previously reached full operating temperatures.
The axial and radial power profiles are explored fully by means of the traversing incore probe (TIP) system at representative power levels during the power ascension.
Core performance evaluations are made at all test points above the 25-percent power level and for selected flow conditions; the work involves determination of the core thermal power, maximum linear heat generation rate, minimum critical power ration (MCPR), and other thermal parameters.
Overall plant stability in relation to minor perturbations is shown by the following group of tests,
- a. Core power-void mode response.
- b. Pressure regulator set point change,
- c. Water level setpo'nt change.
- d. Bypass valve opening.
- e. Recirculation flow setpoint change.
For the first. of these test-, neutron flux (power) response on LPRM chambers zs observed on control rod withdrawal. The next two tests require that the changes made approximate as closely as possible a step change zn demand, while for the next test the bypass valve zs opened quickly.. The remaining test is performed to properly adjust the control loop of the'ecirculation system. For all of these tests, plant performance is monitored by recording the transient behavior of numerous process variables, the one of principal interest being neutron flux. Other imposed transients are produced by'tep changes in demand core flow, simulating loss of a feedwater heater and failure of the operating. pressure regulator to permit takeover by the backup regulator.
The category of ma]or plant transients includes full closure of all MSIVs, fast closure of turbine generator control valves and stop valves, loss of 14.2-35
Nine Mile Point Unit 2 FSAR the main generator and offsite power, tripping of a eedw'at<r puaip, and several tr'ps Gf tne recirculation pumps. The plant transient behavior is recorded for each test and criteria andmay the the results be compared with the acceptance predicted design performance.
- 14. A test is made of the main steam s~Eety relieZ valves in which leaktightness and general operability are demonstrated.
The jet pump flow instrumentation is calibrated at 25 and 100Ã power.
- 16. The as-built characteristics of the recirculation system are determined as soon as operating conditions permit full core flow.
14.2.11 Test Program Schedule Preoperational and s=ar=up testing is planned to be condu" ted in accordance with the rollowxng schedule.
schedule is based on current information and is updated onsite to consider actual con truction and testing progress.
is included to provide general information and sequence but is not considered tn be identical to the schedules jn use during the startup and test program, The preoperational/acceptance test phase commences zn December 1984 and continues until fuel loading xn February 1986.
The startup test program commences with fuel load and continues through power ascension testing which is completed at the end of the 100-hr warranty run in September 1986.
In general, approved preoperational test proceaures will be available for NRC review at least 60 days prior to use and startup test procedures at least 60 days prior to fuel load.
- 14. 2-36
Nine Nile Point Unit 2 FSAR
>4."..12 Individual Test Descriptions 14.2. 12. 1 Preoperatxonal Tests Test abstracts for the preoperational tests are provided in Tables 14.2-2 through 14.2-132. The abstracts identify each test by system; specify the major prerequisites and operating conditions necessary for each (mode of operations of major control systems); provide general test objectives, a summary of the test method, and a summary of the acceptance criteria. Some abstracts may require more than one test depending on variables such as plant status and availability, optimization of resources, and schedule restraints. When additional tests are required they are approved by the JTG, numbered and included on the current vest Index in accordance with the Startup Administrative Procedures.
14.2.12.2 General Discussion of Initial Startup Tests All tests comprising the initial startup test phase are discussed in Table 14.2-201 through 14.2-244 and Table 14.2-301. A test objective, test prerequisites, test des-rxpticn, and t tement of test acceptance or~ter'a are pro:xded for each test where app'i-abl.e.
The 'perating and safety-oriented characteristics of the plant being explored are dercrxbed in the test objectives.
Where applicable, a definition of the relevant acceptance criteria for the test, xs given and designated either Level 1 or Level 2. A Level 1 criterion normally relates to the value of a process variable assigned in the design of the plant, component system or associated equipment.
Level 1 criterion is not satisfied, the plant is placed in a If a stable condition until resolution is obtained. Tests compatible with thxs stable condition may be continued.
Following resolution, applicable tests are repeated as necessary to verify that the requirements of the Level 1 criterion are now satisfied.
A Level " crzterxon zs associated with expe"tat ons relating tc the performance of systems. If a Level 2 criterion is not satisfied, operating and testing plans would not necessarily be altered. Investigations of the measurements and of the analytical techniques used for the predictions would be started.
For transients involving oscillatory response, "he criteria are specified in terms of decay ratio (defined as tne ratio 14.2-37
Nine Mile Point Unit 2 FSAR of successive maximum amplitudes of the same polarity) . The decay ratio must be less than unity to meet a Level 1 criterion and less than 0.25 to meet Level 2.
During the conduct of the initial startup test phase the technical specifications will be followed.
14.2-38
Nine Mile Point Unit 2 FSAR TABLE 14.2-1 PREOPERATIONAL TEST DESCRIPTIONS Table System Number Number Title A. Acceptance Tests 14.2-2 DELETED 14.2-3 DELETED 14.2-4 DELETED 14.2"5 DELETED 14.2-6 DELETED 14.2-7 DELETED 14.2-8 DELETED 14.2-9 DELETED 14.2-10 DELETED 14.2-11 DELETED 14.2-12 DELETED 14.2-13 DELETED 14.2-14 DELETED 14.2-15 DELETED 14.2-16 DELETED 14.2-17 DELETED 14.2-18 DELETED 14.2-19 DELETED 14.2-20 DELETED 14.2-21 DELETED 14.2-22 DELETED 14.2-23 DELETED 14.2-24 DELETED B. Preoperational Tests 14.2-25 Main and Auxiliary Steam 14.2-26 DELETED 14.2-27 Condensate System 14.2-28 Condensate Storage and Transfer 14.2-29 Condensate Demineralizer and Resin Regenerator 14.2-30 Feedwater System 14.2-31 Feedwater Control 14.2-32 Feedwater Heaters and Extraction Steam System 14.2-33 9 Condenser Air Removal 14.2-34 10A Cx rculating Water System 14.2-35 DELETED 14.2-36 Service Water 1 of 5
II Nine Nile Point Unit 2 FSAR TABL!': 14 ..". -1 (Cont )
Table System Number Number Title
,14. 2-37 DELETED
- 14. 2-38 13 Reactor Building Closed Loop Cooling Water
- 14. 2-39 14 Turbine suxiaxng Closed Loop Cooling Water 14 "-40 16 Nakeup Water Storage and Transfer 14 ~ 2-41 17 Process Sampling System 1 4 17 Post-Accident Sample System
- 14. 2-43 19 Instrument and Service Air System
- 14. 2-44 23 EHC System 45 DELETED
- 14. 2-46 28 Nuclear Boiler Instrumentation
- 14. 2-4 I 29 Reactor Recirculation System
>-48 30 CRD Hydraulics oiling 14.2-49 31 Residual Heat Removal System 14.2-50 34 Low-Pressure Core Spray 14.2-51 33 High-Pressure Core Spray sr < 5'> 34 *Uto,.;il.lc ..'~ p e.-.su '~t:or. ~" tern L'
35 Reactor ~oc e isoi ~tior 0 "'y' rr,
~i 30 Standb; ':guxd =ontrcl
- 14. -55 37 Reac tc r H~ te r Cigar>up System 14.2-56 38 Fuel Poo1 Cooling and Cleanup
- 14. >-57 39 Fuel Handling and Reactor Service Equi prrient 2-58 40 Lx -usa R adwas t e 9 ys tern
- 14. 41 Solid Raawaste System 14.2-60 4" Of[-Ga- System 14.2-61 43 Fire Protection Water
- 14. '-6" 44 Foam Fzre Protection
- 14. =-63 45 Fare Protection CO ~
- 14. "-64 46 Fxre Protection Halon 14.2-65 47 Smoke, Flame, and Temperature Derection 14.2-66 DELETED 14.2-67 Hot water and Glycol Heating Systems 14.2-68 52 Reactor Bus 1ding Ventilation-Rea "tor Bur id'g HVAC 14 2 09 53 Control Building Air Condztzonxng 14 ~ -70 DELETED 14.2-71 55 Turbine Building Ventilation 14."-72 56 Radwaste Building Ventilation 14.2"73 57 Diesel Generator HVAC 14.2-74 59A Electric Tunnel Ventilation System 2 of 5
Nine Nile Point Unit 2 FSAR TABLE 14.2-1 (Cont)
Table System Number Number Title
- 14. 2-75 60 Drywell Cooling System 14.2-76 61 Primary Containment Purge 14.2-77 61 Standby Gas Treatment 14.2-78 62 DBA Hydrogen Recombiner 14.2-79 63 Reactor. Building Drains 14.2-80 64 Turbine Building Drains 14.2-81 65 Radwaste Building Drains 14.2-82 66 Miscellaneous Drains - Diesel Generator Floor Drains, Auxiliary Service Building, Reactor Building MAT, Condensate Storage Building, and Main Stack Drains Systems 14.2-83 DELETED 14.2-84 DELETED 14.2-85 DELETED 14.2"86 67 Drywell Equipment and Floor Drains 14.2-87 DELETED 14.2-88 DELETED 14.2-89 DELETED 14.2-90 DELETED 14.2-91 DELETED 14.2-92 DELETED 14.2-93 DELETED 14.2-94 DELETED 14.2-95 71 Uninterruptible Power Supply 14.2-96 DELETED 14.2-97 'DELETED 14.2-98 DELETED 14.2-99 DELETED 14.2-100 73 Normal- DC Distribution (24/48-V DC Power)
- 14. 2.- 101 74 Emergency DC Distribution 14.2-102 75 Station and Emergency Lighting 14.2-103 76 Plant Communication System 14.2-104 78 Remote Shutdown 14.2-105 79,80A Area Process, Airborne, and Gaseous Radiation Monitoring System 14.2-106 80B Main Steam Line Radiation System 14.2-107 81 Containment Leakage Monitoring 14.2-108 82 Containment Atmosphere Monitoring System 14.2-109 83 Primary Containment Isolation 14.2-110 84 Reactor Building Crane (Polar Crane) 14.2-111 DELETED 14.2-112 85 Reactor Coolant and ECCS Leak Detection 3 of 5
Nine Mile Point, Unit 2 FSAR TABLE 14. 2-1 (Cont)
Table System Number Number Title 14.2-113 86 Loose Parts and Vibration Monitoring 14.2-114 88 Containment Inerting System 14.2-115 90 Seismic Monitoring System 14.2-116 91 Process Computer 14.2-117 92 Neutron Monitoring 14.2-118 93 Rod Block Monitoring 14.2-119 94 TIP System 14.2-120 95A Rod Worth Minimizer Control 14.2-121 14.2-122 '695B Rod Sequence Reactor Manual Control and Control Rod Position Indication 14.2-123 97 Reactor Protection 14.2-124 DELETED 14.2-125 100A Standby Diesel Generator 14.2-126 100B HPCS Diesel Generator 14.2-127 100 DELETED 14.2-128 106 Redundant Reactivity Control System 14.2-129 Loss of Power/'ECCS Functional 14.2-130 DELETED 14.2-131 Structural Integrity and Integrated Leak Rate Test 14.2-132 Secondary Containment Leak Rate Test C. Startup Tests Table Procedure Number Number Title 14.2-201 SUT-1 Chemical and Radiochemical 14.2-202 SUT-2 Radiation Measurement 14.2-203 SUT-3 Fuel Loading 14,.2-204 SUT-4A Full Core Shutdown Margin 14.2-205 UT-4B DELETED 14.2-206 SUT-5 Control Rod Drive System 14.2-207 SUT-6 Source Range Monitor Performance and Rod Control Sequence 14.2-208 SUT-8 Control Rod Sequence Exchange 14.2-209 SUT-10 Intermediate Range Monitor Performance 14.2-210 SUT-ll LPRM Calibration 14.2-211 SUT-12 APRM Calibration 14.2-212 SUT-13 NSSS Process Computer 14.2-213 SUT-14 RCIC System 14.2-214 SUT-16A Selected Process Temperatures 14.2-215 SUT-16B Water Level Reference Leg Temperature 4 of 5
Nine Nile Point Unit 2 FSAR TABf.E 14.2-1 (Cottt)
Table Procedure Number Numbe r Title 14.2-216 SUT-17 Svstem Expansion 14.2-317 SUT-18 Core Power Distribution 14 '~-"18 SUT-19 Core Performance 14.2-219 SUT-20 Steam Production 14.2-320 SUT-21 Core Power-Void Mode 14.2-221 SUT-22 Pressure Regulator 14.2-222 DELETED 14.2-223 SUT-23B Loss of Feedwater Heating 14.2-224 SUT-23C Feedwater Pump Trip 14.2-225 SUT-23D Max>mum Feedwater Runout. Capability 14.2-226 SUT-24 Turbine Valve Surveillance 14.2-227. SUT-25A Main Steam Isolation Valves 14.2-228 SUT- P~cB Full Reactor Isolation 14.2-"29 14."-"30 SVT-26 Rely ef Valves 14.".- 31 SUT-27 Turbine Tt lp aftcl Gerr tatot; LoaJ ReJect.son 14.2-232 SUT-28 Shutdown from Outside the Main Control Room 4o <<33 SUT<<29A Recerculat'~n Flow Control, galve 14.2<<234 <'UT- '9Q, Po<<ri tlote Oct:tro 1 Recur"ulatt.ott Flow L .-p C::ttrol 14.2-235 StJT-3vA Recur-ul~'zan System One Pump Trip
- 14. 2<<23r=. SUT<<30B kecirculation Sy- tern Two Pump Tri p e
7 SUT-30C Recxrculati'on Svstem Per ormance l4."- '3t" BUT-30D Hec1 rcui a c on r.ump ku>>r ~ k 1
i.'- .':1/T-30E kr=
1
'cul.rt tutt '..'y..Luttr ~.'~; t L.ar. t ott l~. '-240 SUT-31 Loss o f Turbine Gener a to r attd Of. t. - te Power 14.2-241 SUT-33 Drywell Piping Vibration 2 SUT-35 Recir".ul~tion ~y=tem Flow Calibration
- 14. '- 43 StJT-70 Reactor. Wet.er Cleanup @stem l 4. -244 SUT-71 Re idual Heat kernova I Sy:.tern
- 14. 2-301 SUT- Drywel1 Atmosphere Cooling (later) -"
ys tern 14.2-401 DELETED
- 14. 2'402 DELETED
- 14. "-403 r 'uali f lci Ion of CE:- r nc: pal Testing Personnel Dur.ng Startup Testing 5 of 5
~t 4 i ~
Nine Mile Point Unit 2 FSAR TABLE 14.2-25 MAIN AND AUXILIARY STEAM SYSTEM System 1 Test Ob'ectives
- 1. To demonstrate the operation of the main and auxiliary steam system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
J Prere uisites
- l. All applicable preliminary rests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control czrcuzts, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Auxiliary systems needed for this procedure are available for test support.
Test Procedure a
- 1. The test procedure will verify that va rious components of the main and auxiliary steam system operate within their design requirements.
- 2. The main steam isolation valves are ested for proper operation.
- 3. The instrumentation associated with the main steam flow restrictors will be tested.
- 4. Applicable control instrumentatxon and interlocks will be verified for proper response.
1 of 2
Nine Nile Point Unit 2 CESAR TABE,E 14.2-25 (Cont)
Acce tance Criteria
- 1. System controls, interlocks, and valves function within their design requirements..
- 2. The system functions as described in Section 10.3.
2 of 2
Nine Mile Point Unit 2 FSAR TABI E 14. 2-27 CONDENSATE SYSTEM System 3 Test Ob ectives
- 1. To demonstrate the operation of the condensate system )
and components.
- 2. To ensure the system is "properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- l. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. Al 1 applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Applicable support systems are available for test use.
Test Procedure The test procedure will verify logic and trip modes for the condensate and condensate booster pumps for different system configurations and transient conditions.
- 2. Annunciators, alarms, control instrumentation, and interlocks will be tested for proper response for each transient.
- 3. The condensate and condensate booster pump recirculation flow control valves will be verified to open when their associated pumps are running and to close when they are stopped.
1 of 2
Nine Mile Point Unit 2 CESAR TABj E 14.2-27 (Cont)
Acce tance Criteria
- 1. The condensate and condensate booster pumps operate within their design requirements.
- 2. The logic and trip modes of the pumps and automatic valves function according to applicable SWEC design drawings.
- 3. The system functions as described in Section 10.4.7.
2 of 2
t 0
Nine Mile Point Unit 2 FSAR TABT E 14. 2-28 CONDENSATE STORAGE AND TRANSFER SYSTEM System 4 Test Ob'ectives
- 1. To demonstrate the operation of the condensate storage and transfer systems and components.
2, To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Makeup water storage and transfer system is available to support the test.
Test Procedure
- 1. The capability of the makeup water storage system to supply water to the condensate storage tanks is veri fied.
- 2. Full flow tests of both condensate transfer pumps will be conducted to verify pump operability.
- 3. Pump autostart and trap features are verified for both pumps.
- 4. Condenser hotwell level control system is tested for proper operation of makeup and drawoff valves and alarms associated with hotwell level.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-28 (Cont)
Acce tance Criteria 1: Condensate transfer pumps auto-start on low discharge header pressure or high pump discharge header flow demand in accordance with Section 9.2.6.
- 2. The condenser hotwell can be maintained at the normal level automatically by the normal makeup and drawof f valves in accordance with Section 9.2 '.
- 3. The condensate emergency'akeup valve ,opens automatically on low hotwell level as described in Section 9.2.6.
- 4. The condensate transfer system is capable of supplying water to the appropriate plant systems as listed in Section 9.2.6.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-29 CONDENSATE DEMINERALIZATION AND RESIN REGENERATION System 5 Test Ob'ectives
- 1. To demonstrate the operation of the condensate demineralization and resin regeneration systems and components.
- 2. To ensure the system is properly designed and constructed.
S~afet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- l. All applicable preliminary system turned over to NMPC.
tests are completed and the
- 2. All applicable motor control centers to supply el,ectric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test procedure will verify the proper operation of automatic resin transfers and automatic regenerations. I
- 2. Proper operation of the ultrasonic resin cleaner will be verified.
- 3. All applicable system traps, logic, and xnstrumentatzon will be verified.
- 4. The waste recovery system will be tested to verify it can properly collect, treat, and transfer regenerant waste to the liguid radwaste system.
- 5. Re in transfers that can only be accomplished by remote manual means will be performed to verify proper system operation. I 1 of 2
Nine Mile Po'int Unit 2 FSAR TABLE 14.2-29 (Cont)
- 6. Sampling will be performed to verify water quality meets design specification.
- 7. System alarms and annunciators will be verified for proper response in conjunction with the tests performed.
Acce tance Criteria
- 1. System trips, logic, and instrumentation will operate within design requirements as illustrated in applicable SWEC drawings and vendor instruction manuals.
- 2. The system operates to properly transfer, regenerate, and ultrasonically clean the condensate demineralizers, as referenced in Section 10.4.6.
- 3. The waste recovery system operates to properly collect, treat, and transfer regenerant waste, as referenced in Section 10.4.6.
- 4. System water quality meets specifications, as outlined in Section 10.4.6 and Regulatory Guide 1.56.
2 of 2
Nine Mile Point Unit 2 FSAR TABI E 14. 2 "30 FEEDWATER SYSTEM System 6 Test Ob'ectives
- 1. To the extent practical, demonstrate the operation of the feedwater system and its components.
2 ~ To ensure the feedwater system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers that supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are complete.
- 4. The main condenser is available as a water source and discharge point for the reactor feed pumps.
- 5. The condensate system is available to provide a flow path and the required NPSH for the reactor feed pumps.
Test Procedure
- 1. All remotely operated valves are verified for proper manual and automatic operation.
- 2. The reactor feed pump auxiliary lubrication oil pumps are verified to operate both manually and in response to automatic signals.
- 3. Both high and low energy feedwater cycle cleanup control valves are demonstrated to be operable from their remote manual loading stations.
1 of 2
Nine Nile Point Unit 2 FSAR TABLE 14.2-30 (Cont)
- 4. The reactor feed pump minimum flow recirculation control valves are demonstrated to open and modulate to provide minimum flow for the reactor feed pumps.
- 5. The reactor feed pump logic and trip modes are demonstrated in various system configurations and transient conditions.
- 6. Associated annunciators, computer points, alarms, control instrumentation, and interlocks are demonstrated for proper response during the test.
Acce tance Criteria
- 1. The reactor feed pumps and their various logic modes operate according to specifications outlined in applicable SWEC design drawings.
Remotely operated feedwater valves, along with their associated permissives, interlocks, and controls, function according to applicable SWEC design drawings.
- 3. Auxiliary lubrication oil pumps and their various logic modes operate according to specifications outlined in applicable SWEC design drawings.
- 4. The feedwater system functions as described in Section 10.4.7.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-31 FEEDWATER CONTROL SYSTEM System 7 Test Ob'ectives
- 1. To demonstrate to the extent practical the operation of the feedwater control systems and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures'uring testing.
Prere uisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centersandto supply electric power'to motors, control circuits, ~ instrumentation are available..
- 3. Valve lineups are completed.
- 4. All applicable control equipment and instrumentation calibration has been completed.
Test Procedure
- 1. Proper operation of the motor driven pump discharge regulating valve will be verified with the pump tripped and with no feedwater flow.
- 2. Proper system response is verified as simulated signals for reactor level, f eedwater flow, and steam flow are injected into the feedwater control system.
3 Verification will be made that feedwater control level and flow indicator,
~
recorders, and computer inputs respond to sim'ulated signals and that associated annunciators function according to the system design.
1 of 2
Nine Mile Point Unit 2 FSAR TABZE 14.2-31 (Cont)
Acce tance Criteria All applicable system parameters are within requirements as detailed in GE design test specifications.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-32 FEEDWATER HEATERS AND EXTRACTION STEAM System 8 Test Ob ectives
- 1. To demonstrate to the extent the practical operation of the feedwater heaters and extraction systems and associated components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The heater drain pump permissives, interlocks, and control instrumentation will be tested.
- 2. The heater drain pumps will be tested for proper operation. I
- 3. The normal and emergency level control valves along with their control instrumentation will be verified for proper response to signals generated from level sensing devices.
Acce tance Criteria
- 1. The heater drain pumps and their various logic modes operate within their design requirements outlined in applicable SWEC design drawings.
1 of 2
Nine Mile Point Unit 2 FSAR TABf.E 14.2-32 (Cont)
The feedwater heater extraction isolation valves along with their associated permissives, interlocks, and control instrumentation function according to applicable SWEC design drawings and specifications.
The level control valves and associated instrumentation operate in accordance with applicable SWEC design drawings.
The system design functions as described in Section 10.4.10.
2 of 2"
Nine Mi le Point Unit 2 FSAR TABLE 14.2-33 CONDENSER AIR REMOVAL SYSTEM System 9 Test Ob'ectives
- 1. To demonstrate the operation of the condenser air removal system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable preliminary tests are completed and 0he system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. All valve lineups are completed.
Test Procedure
- 1. All applicable controls, interlocks, and valves are checked for proper operation to ensure performance is within system specifications.
- 2. Vacuum pump trips and automatic system isolations will be tested for proper operation.
- 3. System instrumentation is tested for proper response to simulated signals or actual parameter variation.
- 4. System performance is verified to ensure that air is evacuated from the mazn condenser.
Acce tance Criteria
- 1. System isolations and vacuum pump trips function in accordance with Section 10.4.2.5.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-33 (Cont)
- 2. The condenser air removal pumps evacuate the condenser to approximately 5 in Hg abs and deliver discharge gases to the main stack at atmospheric pressure.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-59 (Cont)
Acce tance Criteria
- 1. System parameters affecting the processing of solid radwaste meet design requirements.
2 ~ System interlocks, trips, and controls associated with the system function as designed.
- 3. The solidified product should be a homogeneous mixture with no freestanding water.
2 of 2
Nine Mile Point Unit 2 FSAR TAB? E 14. 2-60 OFF-GAS SYSTEM System 42 Test Ob'ectives
- 1. To demonstrate the operation of the off-gas system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test verifies system controls and interlocks to l ensure performance in accordance with specifications.
- 2. The operation of the off-gas vacuum pumps is verified. I
- 3. The off-gas control panel is tested to ensure all control functions and remote monitoring of the off-gas system are provided.
- 4. Applicable alarms are verified in conjunction with the tests performed.
Acce tance Criteria
- 1. Applicable system parameters, i.e., flows, temperatures, and pressures, fall within design requirements.
~"
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-60 (Cont)
- 2. System controls and interlocks function in accordance with design requirements.
- 3. The system functions as described in Section 11.3.2.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-34 CIRCULATING WATER SYSTEM System 10A Test Ob'ectives
- 1. To demonstrate the operation of the circulating water system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- l. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
1 The service water, instrument axr, turbine building closed loop cooling acid treatment, and hypochlorite systems are available as required to support this test.
Test Procedure 1.. The cooling tower is operated in its four modes of )
operation.
- 2. Applicable annunciators, trap signals, and interlocks are verified for proper operation.
- 3. The six circulating water pumps and associated equipment are tested to ensure they are capable of delivering water at the required system flows and pressures.
C 1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-34 (Cont)
Acce tance Criteria
- 1. The circulating water pumps operate in accordance with applicable SWEC design drawings and specifications.
- 2. The circulating water screen wash pumps operate as designed in accordance with applicable SWEC design drawings.
- 3. The cooling towers operate in accordance with applicable SWEC design drawings in all four modes of operation.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-36 SERVICE WATER SYSTEM System 11 Test Ob ectives
- 1. To demonstrate the operation of the service water systems and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- l. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available'.
Valve lineups are completed.
- 4. The circulating water system is capable of receiving water from this system during this test.
Test Procedure
- l. Intake and discharge equipment is tested for normal and reverse flow using appropriate logic controls.
- 2. All service water pumps are tested for proper operation of automatic starts and trips, flow rates, and appropriate interlocks.
- 3. All applicable motor- and air-operated valves are operated to verify that they open and close properly.
- 4. The service water flow path to the spent fuel pool is veri fied.
- 5. The system and its associated logic functions for supplying water to the emergency diesels, HPCS diesel, and RBCLC systems are verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-36 (Cont)
- 6. The system is run to verify that flows to systems that it it supports.
can supply appropriate
- 7. The capability of the service water system to supply adequate diesel cooling water flows.
Acce tance Criteria
- 1. The applicable instruments, controls, and interlocks
)
function as shown on the applicable design drawings.
- 2. Each service water pump and associated discharge strainer will provide its rated flow for all normal and emergency operating conditions.
- 3. The intake and discharge structures and associated gates and valves function as designed. The intake and discharge structures will supply and discharge lake water in accordance with Table 9.2-8.
- 4. Under normal operating conditions, the service water system supplies lake water to the components listed in Table 9.2-2 at the specified flow rates to meet the power generation design objectives of Section 9.2.1.1.2.
- 5. During a LOCA condition with a loss of offsite power or low service water pressure, the service water system will supply lake water to the components listed in Table 9.2-1 at the specified flow rates to meet, the safety design objectives of Section 9.2.1.1.1.
2 of 2
Nine Mile Point Unit 2 FSAR TABIE 14.2-38 REACTOR BUILDING CLOSED LOOP COOLING WATER SYSTEM System 13
- 1. To demonstrate the operation of the reactor building closed loop cooling water system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- l. Applicable preliminary tests are completed and the system turned over to NMPC.
- 2. Applicable motor control centers to supply. electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. The service water, instrument air, and makeup water transfer systems are available to support testing.
Test Procedure
- 1. All applicable controls, interlocks, and valves are checked for proper operation and performance in accordance with design requirements.
- 2. The autostart and trip features of the RBCLC main and booster pumps will be verified.
- 3. The system temperature control valves are modulated to verify proper operation.
- 4. The expansion tank level control valve operation is )
verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-38 (Cont)
- 5. Motor-operated isolation valves will be verified.
Acce tance Criteria
- 1. All applicable controls, interlocks, and trips function as designed.
- 2. The autostart and trip features of the RBCLC main and booster pumps function in accordance with Section 9.2.2.5.
- 3. The expansion tank level control valve maintains level in accordance with Section 9.2.2.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-39 TURBINE BUILDING CLOSED LOOP COOLING WATER SYSTEM System 14 Test Ob ectives
- 1. To demonstrate the operation of the turbine building closed loop cooling water system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. The instrument air, service water, and makeup water transfer systems are available to support this test.
- 5. The TBCLCW system is operating in a two-pump, two-heat exchanger mode with the third pump and heat exchanger vented and in standby.
Test Procedure
- 1. System controls and interlocks are verified for the three sy-tern pumps in the various mode of operation. !
- 2. System urge and makeup tank level zs monitored and verified for proper operation.
3-. System control valves are modulated to verify proper operation.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-39 (Cont)
- 4. The automatic response for the off-gas condenser outlet valves is checked for proper response.
- 5. With the TBCLCW system in a two-pump mode, the baseline operating data is collected and recorded.
Acce tance Criteria The automatic trip and start features for the TBCLCW pumps operate according to Section 9.2.7.
2 ~ Temperature control valves operate in accordance with Section 9.2.7.
The system supplies water to the required plant components in accordance with Table 9.2-9.
In a two-pump mode, the TBCLCW system is capable of meeting the maximum design flow rate (16,000 gpm) in accordance with Sectxoh 9.2.7.
2 of 2
Nine Mile Point Unit 2 FSAR TABf.E 14.2-40 MAKEUP WATER TRANSFER AND STORAGE SYSTEM System 16 Test Ob'ectives
- 1. To demonstrate the operation of the makeup water transfer and storage system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Water treatment system is available to support this test.
Test Procedure
- l. All controls, interlocks, and valves are verified for
=
proper operation to ensure performance with system specifications.
- 2. Applicable set points are verified.
3 Pump autostart, trip features, and associated alarms and annunciators will be verified for proper operation by
~
varying several parameters including: tank level, pump suction and discharge pressure, and system flow.
1 of 2
0 Nine Mile Point Unit 2 FSAR TABT.E 14.2-40 (Cont)
Acce tance Criteria Each transfer pump will deliver at least 200 gpm in accordance with Equipment Specification No. NMP2-P222W.
I
- 2. The system functions as described in Section 9.2.3.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2"41 PROCESS SAMPLING SYSTEM System 17 Test Ob'ectives
- 1. To demonstrate the operation of the turbine, reactor, and radwaste buildings sampling systems and components.
2 ~ To ensure the systems are properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere ui sites
- 1. All applicable preliminary tests are completed and the system turned over:to NMPC
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. The turbine and reactor building closed loop cooling systems are available to support testing.
Test Procedure
- 1. The test procedure verifies proper system instrumentation response by simulated signals or actual parameter variation.
- 2. All applicable controls, interlocks, and valves are verified for proper operation to ensure performance within system specifications.
- 3. All applicable alarms and annunciators are verified for proper operation in conjunction with the tests performed.
1 of 2
Nine Mile Point Unit 2 FSAR TABlE 14.2-41 (Cont)
- 1. All air-operated sample sy tern isolation valves operate correctly f'rom their respective sample panels.
- 2. All applicable system instrumentation, interlocks, and trips function as designed in accordance with Section 9.3.2.
- 3. The system functions a described in Section 9.3.2.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-42 POST-ACCIDENT SAMPLE SYSTEM System 17 Test Ob'ectives
- 1. To demonstrate to the extent practical the operation of the post-accident sample system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- l. All applicable preliminary tests are completed the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The sample line solenoid valves are verified for proper operation.
- 2. The sample line solenoid valve permissive switch is verified for proper operation.
- 3. The control logic of the sample panel is verified.
- 4. Where required simulated signals are used to verify that valves re"pond properly and sample panel functions according to design.
- 5. Heat tracing operation will be verified.
Acce tance Criteria
- l. All applicable system parameters meet design specifications in accordance with GE design specifications.
1 of 2
Nine Mile Point Unit 2 FSAR TABf.E 14.2-42 (Cont)
- 2. The system meets its design functions by delivering representative samples at the designated sample points.
2 of 2
Nine Mile Point Unit 2 FSAR TABIE 14. 2-43 SERVICE AND INSTRUMENT AIR SYSTEM System 19 Test Ob'ectives
- 1. To demonstrate the operation of the service and instrument air systems and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during )
testing.
Prere uisites
- 1. All applicable preliminary tests are completed the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test procedure will verify that the instrument and service air system is capable of supplying the plant's compressed air requirements during normal operation.
- 2. The autostart feature of the compressors will be verified.
- 3. The air compressor trip modes will be verified for various transients, simulated during testing.
- 4. Air compressor capacity and load time will be verified.
- 5. The test will ensure that the instrument air dryers and associated instrumentation operate according to design.
- 6. System controls and interlocks will be verified for correct response.
l of 2
Nine Nile Point Unit 2 FSAR TABLE 14.2-43 (Cont)
- 7. A loss-of-air-supply test (Regulatory Guide 1.68i3) will be conducted on those portions of the instrument air system which interface with safety-related systems to verify that the air-controlled components supplied directly from the instrument air system will respond as designed. A listing of all air- and nitrogen-operated safety-related valves is in Table 14.2-43A. This testing may be performed in the individual system preoperational tests.
8, The test procedure will verify there are no crossties between the service air and instrument air systems which will degrade system operation.
- 9. Alarms and annunciators will be verified for proper response in conjunction with the various tests performed.
Acce tance Criteria
- 1. The air compressors operate within design requirements as outlined in Equipment Specification No. NNP2-P261C.
- 2. The trip and autostart modes for the air compressors function as outlined in applicable SWEC design drawings.
- 3. Applicable system controls and interlocks operate as specified in applicable SWEC design drawings.
- 4. The system functions a described in Section 9.3.1.
- 5. The air- and nitrogen-operated safety-related valves listed in Table 14.2-43A fail in their fail-safe positions on a loss of air/nitrogen.
2 of 2
Nine Mile Point Unit 2 FSAR TABIE 14.2"44 EIECTROHYDRAUIIC CONTROI (EHC) SYSTEM System 23 Test Ob ectives
- 1. To demonstrate 'he operation of the turbine electrohydraulic control system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rule and proper procedures during testing.
Prereauisites
- l. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control,circuit', and inst.rument.vt.aon are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The hydraulic control subsystem is verified to ensure that, hydraulic fluid is supplied at appropriate pressure to control operating and trip devices for turbine stop valves, control valves, bypass valves, and CIVs.
- 2. Control switches, appropriate alarms, and annunciators are verified for proper operation.
- 3. Remote-operated valves with appropriate interlocks and set points are verified.
- 4. The electro-control subsystem is tested to verify that simulated control signals, generated hydraulically, modulate turbine control valves to control turbine generator speed, load, and reactor pressure.
- 5. System alarms and annunciators are verif ed.
1 of 2
Nine Mile Point Unit 2 FSAR TABE,E 14.2-44 (Cont)
Acce tance Criteria
- 1. The hydraulic fluid pumps and associated equipment operate in acordance with system design drawings.
- 2. The system functions as designed in accordance with Section 10.2.2.
- 3. All applicable alarms and annunciators function as designed.
Turbine control valves, bypass valves, and combined intermediate valves respond correctly to simulated signals 'elated to turbine speed, load, and reactor pressure.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-46 NUCLEAR BOILER INSTRUMENTATION System 28 Test Ob'ectives
- 1. To demonstrate to the extent practical the operation of the nuclear boiler instrumentation system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure Reactor water level instruments shall be verified over the full range for response to actual reactor " vessel water level changes and, where practical, the level instruments should be checked against known physical levels in the vessel.
- 2. All applicable alarms and annunciators will be verified for proper operation in conjunction with the tests performed.
Acce tance Criteria
- 1. Instruments provide proper control room indication of the parameter being measured.
- 2. Applicable interlocks and trips function as designed.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-46 (Cont)
THE INFORMATION ON THIS PACE HAS BEEN DELETED.
2 of 2
Nine Mile Point Unit 2 FSAR TABT E 14. 2-47 REACTOR RECIRCULATION SYSTEM System 29
- 1. To demonstrate to the extent practical the operation of I the reactor recirculation system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during I testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NNPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Ualve lineups are completed.
- 4. All applicable water quality standards should be met and maintained throughout testing.
Test Procedure
- 1. The test will verify proper operability of the reactor recirculation system during slow speed pump conditions under normal and transient operating conditions.
- 2. Motor-operated and flow control valves, along with their corresponding controls and instrumentation, will be verified for proper response.
- 3. The recirculation pumps will demonstrate required hydraulic performance at different reactor conditions and flow control valve settings.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-47 (Cont)
- 4. Proper operation of the hydraulic power units and their associated equipment will be verified.
Acce tance Criteria
- 1. All applicable parameters, i.e., flows, temperatures, and pressures, fall within syst: em design requirements as stated in the GE Design Specification.
- 2. All applicable interlocks and trips function as designed.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14. 2-48 CONTROL ROD DRIVE HYDRAULIC SYSTEM System 30 Test ob'ectives
- 1. To demonstrate the operation of the control rod drive hydraulic system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC. I
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. The reactor manual control and rod position indication system is available to support this test.
- 5. The CRD vessel internals have been installed.
Test Procedure 1., The test will verify proper operation of sensors, recording devices, and other controls.
- 2. Valve operability will be confirmed.
- 3. All pumps and filters will be tested to confirm performance in accordance with design specifications.
- 4. The capacity of the system to deliver a sufficient steady water supply through normal and alternate routes will be verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-48 (Cont)
- 5. Each HCU, CRD, and any applicable annunciators will be
! verified for proper functioning using normal insert/withdrawal modes and by scram testing.
Acce tance Criteria
- 1. The applicable parameters, i.e., response times, flows, temperatures, and pressures, are within their design requirements as detailed in GE design specifications.
2 ~ The applicable interlocks and trips function in accordance with the design documents.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-49 RESIDUAL HEAT REMOVAL SYSTEM System 31 Test Objectives
- 1. To demonstrate to the extent practical the operation of the residual heat removal system and components in all modes except steam condensing.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- l. All applicable preliminary tests .are completed and the system turned over to NMPC.
2 All applicable motor control centers to supply electric circuits,
~
power to motors, control and instrumentation are available.
- 3. The suppression pool suction strainer is 50-percent hooded.
- 4. Valve lineups are completed.
Test Procedure
- 1. All applicable valves, sensors, and logic are verified.
2 ~ Water,leg pumps are checked to verify their ability to pressurize the RHR system piping.
- 3. Tests of each RHR operation mode (low pressure coolant injection, containment spray cooling, shutdowndemonstrate cooling, suppression pool cooling) are performed to satisfactory operability.
- 4. Air-flow tests will be conducted using test paths that overlap the water-flow te t paths of the pumps to verify that there is no blockage in the containment spray flow paths.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-49 (Cont)
Acce tance Criteria
- 1. System parameters are within the design requirements detailed in the GE Design Specifications.
- 2. System interlocks and trip functions operate in accordance with applicable design reguirements.
2 of 2
Nine Nile Point Unit 2 FSAR TABLE 14.2-50 joW-PRESSURE CORE SPRAY SYSTEM System 32 Test Ob ectives
- 1. To demonstrate the operation of the low-pressure core I spray system and components.
- 2. To ensure the system is properly designed and constructed.
Saf et Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable preliminary tests are completed and the system turned over to NNPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. The suppression pool suction strainer is 50-percent hooded.
Test Procedure
- 1. Proper. operation of motor and air-operated valves will be verified.
- 2. System logic will be tested to verify its proper performance.
- 3. Operation of the core spray pump and motor assembly will be verified. 3 4: Flow and hydraulic characteristics of the system will be determined.
5 ~ The system's capability of performing its intended function under emergency conditions upon automatic initiation will be demonstrated. I 1 of 2
Nine Mile Point Unit 2 FSAR I
TABLE 14.2-50 (Cont)
- 6. The operability of the water leg pump, including its ability to pressurize the LPCS system piping, will be verified.
Acce tance Criteria
- 1. System parameters fall within design requirements detailed in GE design specifications.
- 2. System interlocks and 'rips function as specified in applicable design drawings.
2 of 2
Nzne Ni'le Point Unit 2 FSAR TABLE 14.2-51 HIGH-PRESSURE CORE SPRAY SYSTEM System 33 Test Ob 'ectives
- 1. To demonstrate the operation of the high-pressure core spray system and components.
- 2. To ensure the system is properly designed and constructed.
Safest Precaution Follow NNPC safety rules and proper procedures during I testing.
- 1. All applicable preliminary tests are completed and the system turned over to NNPC.
- 2. All applicable motor control center to supply electric power to motors, control circuits, and instrumentation are available.
- 3. All applicable sensors, pres ure switches, gauges, instruments, and protective relays have been calibrated.
- 4. The suppression pool suction strainer is 50-percent hooded.
- 5. Valve lineups are complete.
Test Procedure
- 1. Proper operation of motor- and air-operated valves will be verified.
System logic will be tested to verify proper operation.
3.. Pump and motor operation is verified.
- 4. System performance characteristics are obtained and verified to meet design requirements.
- 5. System initiation on low water level and high drywell pressure is checked to verify ability of system pump to 1 of 2
0 Nine Nile Point Unit 2 FSAR TABLE 14.2-51 (Cont) start, the injection valve to open, and the system's ability to deliver rated flow to the vessel in the required time interval.
- 6. The operability of the water leg pump, including the ability of the pump to pressurize the HPCS system piping, will be verified.
Acce tance Criteria
- 1. System parameters fall within design requirements as detailed in GE design specifications.
- 2. System interlocks and trips function as specified in applicable design documents.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-52 AUTOMATIC DEPRESSURIZATION SYSTEM System 34 Test Ob'ectives
- 1. To demonstrate the operation of the automatic depressurization system and components.
- 2. To ensure the system is properly designed ,and constructed.
Safet Precaution Follow all NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable prelim>nary te ts are completed and the system turned over to NMPC.
- 2. supply electric All applicable motor control centers to instrumentation power to motors, control circuits, and are available.
- 3. Valve lineups are completed.
4, Instrument and service air, ADS, Nz system, RPS, and nuclear boiler instrumentation systems are avai lable to support testing.
Test Procedure The test verifies controls, interlocks, and valves for proper operation.
- 2. Nitrogen supply is verified along with the volume of the tanks that their capacity is adequate to meet the troke requirements of valves.
- 3. ADS air compressor and dryers are checked to verify. that pressurized air can be provided to the valves'neumatic actuators.
- 4. ADS logic is verified including auto initiation signals, time delay relay and reset functions, core spray and RHR permissives. !
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-52 (Cont)
- 5. The operation of the safety relief valves in the relief (pneumatic) mode is verified.
- 6. The reactor vessel overpressure penetration logic of the ADS system is verified.
7., The safety relief valve solenoid valves will be verified to open when the solenoid coil is energized.
- 8. ADS accumulator leak rates will be measured to verify that the ADS safety relief valves remain operable if their source of air or nitrogen is lost.
Acce tance Criteria
- 1. The system logic operates per SHEC logic drawings and GE design specifications.
- 2. Accumulator capacity meets design requirements per GE design. specifications.
- 3. ADS accumulator leak rates are within design requirements in accordance with GE design specifications.
- 4. The safety relief valves operate properly in the relief (pneumatic) mode.
- 5. The accumulators for the ADS relief valves maintain pressure for at least the relief cycle after a loss of nitrogen supply.
2 of 2
Nine Mile Point Unit 2 FSAR TABI E 14. 2-53 REACTOR CORE ISOI ATION COOI ING SYSTEM System 35 Test Ob ectives
- 1. To demonstrate to the extent practical the operation of the reactor core isolation cooling system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- l. All applicable preliminary tests are completed and the sy tern turned over to NMPC.
All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. The suppression pool suction strainer is 50-percent hooded.
Test Procedure
- 1. Proper operation of air- and motor-operated valves will be verified.
- 2. The system sensors and interlocks will be verified to control logic circuitry.
- 3. The flow controller adjustments and calibrations will be verified.
- 4. The various flow paths for the system will be verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-53 (Cont)
Acce tance Criteria System parameters fall within the design requirements detailed in GE design specifications.
2 of 2
Nine. Mile Point. Unit 2 FSAR TABf E 14. 2-54 STANDBY LIQUID CONTROI SYSTEM System 36 Test Ob ectives
- 1. To demonstrate the operation of the standby liquid I control system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prereguisites
- 1. All applicable prt:liminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are complete.
4., The system is filled with demineralized water.
- 5. Sufficient quantities of reactor grade boric acid and borax are available at the storage tank location when required to support neutron absorber mixing and loading.
Test Procedure Valve, sensor, heat tracing, and logic tests are performed to verify proper operation.
The performance of applicable system pumps, motors, I instrumentation, motor-operated outlet valves, check globe valves, and relief valves is verified.
A system injection test, using deminerali ed water, is performed prior to fuel loading with the reactor vessel at atmospheric or hydro-pressure, firing one of the squib valves while observing all of the components operate properly.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-54 (Cont)
- 4. Neutron'bsorber is prepared, analyses performed, and demineralized water introduced into the system according to specifications.
Acce tance Criteria
- 1. System parameters fall within the design requirements detailed in GE design specifications.
- 2. The system functions as described in Section 15.8.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-55 REACTOR WATER CLEANUP SYSTEM System 37 T~est Ols 'ectives
- 1. To demonstrate the operation of the reactor water cleanup system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow all NMPC safety rules and proper procedures during testing.
Prerequi ites
- 1. All applicable preliminary tests are completed and the system turned over to NNPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The various system flow paths will be verified.
- 2. The proper functioning of interldcks and instrumentation is verified.
- 3. The test will verify isolation and cleanup pump trip logic under transient condign,sons.
- 4. Performance of all valves, heat exchangers, and various operating sequences of the filter/demzneralizer will be verified.
- 5. Alarms and communicators will be verified for proper operation in conjunction with the tests performed.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-55 (Cont)
Acce tance Criteria System parameters fall within design requirements detailed in GE design specifications.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-56 FUEL POOL COOLING AND CLEANUP System 38 Test Ob'ectives
- 1. To demonstrate the operation of the fuel pool cooling and cleanup system.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the I system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Electrical lineups are completed.
5 ~ The static head pressure test of the reactor head cavity, fuel pool, and reactor internals storage pools has been completed satisfactorily verifying. the integrity of sectionalizing devices, drains, and gasket leak tests.
Test Procedure
.1. The test verifies that the system is capable of maintaining, during normal and abnormal conditions, design flow and water chemistry requirements. I
- 2. Anti-siphon devices will be verified.
- 3. Filter online, on-hold, backwash, and precoat functions will be verified.
1 of 2
Nine Nile Point Unit 2 FSAR TAgt.E 14. 2-56 ( ont)
System backup~ from RHR and service water will be verified.
- 5. Applicable system controls, instrumentation, and interlocks will be verified for correct response.
Alarms and annunciators are verified for proper response in conjunction with the tests performed.
Ancetance Criteria Autotrips for SFP cooling pumps functions according to applicable SWEC logic diagrams.
Filter operation and sequencing function according to Delaval Nanual Inst. 16.550-5000A.
- 3. System functions as described in Sect'on 9.],.3.
2 of 2
Nine Mile Point Unit 2 FSAR TABlE 14.2-57 FUEL HANDLING AND REACTOR SERVICE EQUIPMENT SySTEM System 39 Test Ob ectives
- 1. To demonstrate the operation of the fuel handling and reactor service equipment system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Dynamic testing using a dummy fuel bundle and static load tests at 125 percent of that load will be performed on the refueling grapple and platform auxiliary hoists.
Test Procedure
- 1. All applicable interlocks and logic associated with the refueling platform and service platform are verified.
- 2. The refueling equipment is checked for proper operation and installation.
The in-vessel servicing equipment, such as peripheral orifice servicing, control rod assembly servicing, instrument servicing, and in-vessel fuel assembly servicing, is checked for correct assembly and operation.
- 4. The reactor vessel servicing equipment is checked for )
proper assembly and operation.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-57 (Cont)
- 5. The fuel service equipment is checked for proper installation and operation.
- 6. The servicing aids are checked for proper assembly and operation.
The under reactor vessel servicing equipment, including control rod drive servicing equipment and in-core 1nstrumentatlon servic1ng equipment, is tested for correct installation and operation.
Acce tance Criteria System parameters fall within the manuals.
design requirements detailed in GE test specifications and 1
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-58 LIQUID RADWASTE SYSTEM System 40 Test Ob ectives
- 1. To demonstrate the operation of the liquid radwaste I system (LWS) and components.
- 2. To ensure the system is properly designed and constructed.
I Saf et Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites 1 ~ All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The LWS program is checked to verify that it controls the mechanical process sequence.
- 2. All applicable interlocks, alarms, set points, and annunciators are verified.
- 3. The test verifies alarms associated with LWS chemistry, in conjunction with the tests performed.
- 4. The test verifies the auxiliary steam supply is adequately controlled to maintain and operate the necessary equipment.
- 5. The radwaste computer functions are verified.
- 6. Radiation detector and monitor control functions will be verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-58 (Cont)
Acce tance Criteria
- 1. All applicable interlocks and trips function according to SWEC and manufacturer design drawings.
- 2. The liquid radwaste system collects, monitors, and processes liquid waste as described in Section 11.2.
- 3. Radiation detection device support functions and associated alarms and trips function according to SWEC logic drawings.
- 4. The radwaste computer performs within the design requirements outlined in Specification C062V.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-59 SOLID RADWASTE HANDLING SYSTEM System 41 Test Ob ectives
- 1. To demonstrate the operati'on of the'olid radwaste handling system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure 1 ~ The WSS program is verified to ensure it controls mechanical process sequence.
.2. Applicable system valves, interlocks, and controls are verified.
- 3. The capability of the system to transfer waste to and from desired destinations is verified using simulated waste variation.
- 4. The steam supply from the WSS electric boiler is veri fi ed.
- 5. Using a simulated waste stream, waste will be processed via the extruder evaporator to ensure proper mixing and no freestanding water.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-59 (Cont)
Acce tance Criteria
- 1. System parameters affecting the processing of solid radwaste meet design requirements.
- 2. System interlocks, trips, and controls associated with the system function as designed.
- 3. The solidified product should be a homogeneous mixture with no freestanding water.
2 of 2
Nine Mile Point Unit 2 FSAR TABjE 14.2-60 OFF-GAS SYSTEM System 42 Test Ob ectives
- 1. To demonstrate the operation of the off-gas system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test verifies system controls and-interlocks to I ensure performance in accordance with specifications.
- 2. The operation of the off-gas vacuum pumps is verified.
- 3. The off-gas control panel is tested to ensure all control functions and remote monitoring of the off-gas system are provided.
- 4. Applicable alarms are verified in conjunction with the tests performed.
Acce tance Criteria 1, Applicable system parameters, i.e., flows, temperatures, and pressures, fall within design requirements.
1 of 2
0 Nine Mile Point Unit 2 FSAR TABI.E 14.2-60 (Cont)
- 2. System controls and interlocks function in accordance
~
with design requirements'.
The system functions as described in Section 11.3.2.
2 of 2
Nine Mile Point Unit 2 FSAR TABI.E 14.2-61 FIRE PROTECTION (WATER) SYSTEM System 43 Test Ob ectives
- 1. To demonstrate the operation of the fire protection (water) system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the J system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test will verify the operation o'f the electric and diesel fire pumps and the pressure maintenance pumps for all modes of operation.
- 2. The high-low level switches and their associated instrumentation for the pressure maintenance pump supply tank will be tested for proper response.
- 3. Motor-operated deluge valves, including those in the transformer zone, will be tested for automatic operation.
- 4. The remote-manual operation of these valves from associated fire panels will be verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABt'E 14.2-61 (Cont)
- 5. All motor-operated pre-action valves will be tested for automatic operation in conjunction with a fire detector trip.
- 6. Corresponding annunciators, alarms, control instrumentation, and system interlocks will be tested for proper response in conjunction with the various tests conducted.
Acce tance Criteria
- 1. The electric and diesel fire pumps operate according to applicable SWEC design drawings.
- 2. Motor-operated deluge and pre-action valves function according to applicable SWEC design drawings.
- 3. System pressure'an be maintained between 125 and 135 psig by the fire jockey pumps.
2 of 2
Nine Mile Point Unit '2 FSAR TABf E 14. 2" 62 FOAM FIRE PROTECTION SYSTEM System 44 Test Ob ectives
- 1. To demonstrate the operation of the foam fire protection system and components.
- 2. To ensure the . system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. The foam concentrate tanks are filled to 5 half normal level.-
Test Procedure
- 1. The test verifies system controls, 'nterlocks, and valves for proper operation to ensure performance is within specifications.
- 2. The test will veri fy the auto start and trip features of the foam pumps and the actuation of automatic valves ~
upon receipt of a sxgnal from the fire detection system or a control swatch.
Corresponding computer , alarms and annunciators associated with the roam fire protection system will be tested for proper response in conjunction with the various tests performed.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-62 (Cont)
.Acce tance Criteria
- 1. The auto start and trip features of fixed ha ard foam pumps and hose reel foam function in accordance with SWEC design drawings.
- 2. Automatic valves function in accordance with SWEC design drawings.
- 3. Foam concentrate utilized is acceptable per NFPA requirements.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-63 FIRE PROTECTION COp System 45 Test Ob'ectives
- 1. To demonstrate the operation of the fire protection COz )
system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution !
'Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation.
3 ~ Valve lineups are completed.
- 4. The fire computer, fire detection, and ventilation systems are available to support testing.
Test Procedure
- 1. The CO< storage tanks are filled.
- 2. The CO< hose reels are veri fied for proper operation.
The CO< hazard valves are puff tested, with the CO< zone piping isolated and its bypass open, from the local fire panel, main fire panel, and associated detection zones in both manual and automatic modes of operation.
Concentration tests are performed on total flooding systems.
- 4. The generator hydrogen and CO: subsystems are tested for CO< flow.
1 o~
Nine Nile Point Unit 2 FSAR TABI.E 14.2-63 (Cont)
- 5. Alarms and annunciators are verified for proper response in conjunction with the various tests performed.
Acce tance Criteria
- 1. Applicable valves and controls operate according to SWEC design drawings.
- 3. CO~ concentrations for total flooding systems are in accordance with NFPA Codes - Volume I, Code 12: Carbon Dioxide Systems'.
System design and operation is as described in "
Section 9.5.1.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14. 2-64 FIRE PROTECTION (HALON) SYSTEM System 46
- 1. To demonstrate the operation of the fire protection )
(Halon) system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Frere uisites
- 1. All applicable preliminary te ts are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control. circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. All auxiliary system needed for this procedure are operable and available for test use.
Test Procedure
- 1. The test will verify proper operation of the Halon fire protection system for various operating conditions.
- 2. The autostart/stop modes of the Halon fire protection sy tern upon a detector trip will be verified. I
- 3. For each fire one the test verifies that the proper concentration of Halon is reached in a specified time period.
- 4. Manual operation of the Halon system will be verified f rom corresponding control panels.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-64 (Cont)
- 5. Corresponding alarms, annunciators, and computer points will be verified for proper response in conjunction with the various tests conducted.
Acce tance Criteria
- 1. The Halon 1301 system functions as designed and provides the required concentration as specified in the National Fire Codes.
- 2. System interlocks and trips function in accordance with applicable SWEC design drawings.
3, The system functions as described in Section 9.5.1.
Amendment 21 2 of 2 September 1985
Nine Mile Point Unit 2 FSAR TABLE 14.2-65 SMOKE, FLAME, AND TEMPERATURE'ETECTION System 47
- 1. To demonstrate the operation of the smoke, flame, and I temperature system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during I testing.
Prere uisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test will verify that the fire detection system is capable of interacting with the fire protection systems in accordance to station specifications.
- 2. The automatic functions of the local fire panels for each zone will be verified for a detector trip.
- 3. The manual remote functions of the local fire panels will be verified.
- 4. Corresponding annuncxations, alarms, and computer points will be verified in conjunction with the various tests conducted,
- 5. The supervision modes for the various components of the fire detection system'will be verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-65 (Cont)
Acce tance Criteria
- 1. Fire detectors and associated instrumentation function according to design criteria as documented in associated vendor diagrams, CMEB Section 9.5-1, and NFPA Codes and Standards.
- 2. The automatic functions of the local fire panels perform in accordance with applicable SWEC design drawings.
- 3. The supervision modes operate according to applicable SWEC design drawings.
2 of 2
0 Nine Rile Point Unit 2 FSAR TABLE 14.2-67 HOT WATER AND GLYCOL HEATING SYSTEMS System 49 Test Ob'ectives
- 1. To demonstrate we operation of the hot water and glycol heatin= systems and components.
- 2. To ensure the systems are properly cosigned and constructed.
Safet Precaution Foll'ow NMPC sa=ety rules and proper proce=ures during testing.
Prere isites
- 1. All applicable =eliminary tests are ccmpleted and the system turned over to NMPC.
2 . Applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test procedure will veri fy that the reactor building, turbine building, and radwaste bu= ding 'glycol heating system=- operate according to design specifications.
Mechanical equipnent such as the glycol :- ating pumps 2.
and valves per formance.
wil'e tested to demonstrate proper 1 of 2
Nin Mile Point Unit I
2 FSAR JOULE 14.2<<67 (Cont).
4- The test ensures applicable controls, interlocks, and valves are checked for proper operation.
Annunciators and computer alarms are verified in conjunction with the 'tests performed.
Acce tance Criteria All annunciator=-, control instrumentation, interlocks, and the various ogic modes for the system function as illustrated in design drawings.
- 2. System flows an= pressures are within desi'imits for all modes of ope=ation.
- 3. The system mee== its design functions as described in Sections 9.4."1 ~ d 9.4. 12.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-68 REACTOR BUILDING HVAC System 52 Test Ob ectives
- 1. To demonstrate the operation of the reactor building I systems and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- l. All applicable preliminary tests are completed and the system turned over to NMPC.
2 ~ All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. Controls, interlocks, and trips for dampers, fans, unit heaters, and coolers are verified.
- 2. The emergency recirculation ventilation is tested to verify that cooling is provided during LOCA conditions.
1 of 2
Nine Mile Point Unit 2'SAR TABLE 14.2-68 (Cont)
- 3. The reactor head exhaust ventilation system is tested to ensure that air from beneath the vessel head is exhausted.
Acce tance Criteria
- 1. The building pressures meet design specifications.
- 2. The system parameters meet design requirements as described in Section 9.4.2.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14. 2-69 CONTROL BUILDING AIR CONDITIONING System 53 Test Ob'ectives To demonstrate the operation of the control building air conditioning system.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- 1. All applicable preliminary tests have been completed and the system turned over to NMPC.
- 2. Applicable motor control, centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Applicable lineups have been completed.
Test Procedure
- 1. The test verifies system controls and interlocks.
- 2. The system will be started and test data taken to veri fy performance is within design specifications.
Acce tance Criterion All applicable system trips, interlocks, and control func-tions operate in accordance with applicable SWEC drawings.
Nine Nile Point Unit 2 FSAR TABLE 14.2-71 TURBINE BUIjDING HVAC SYSTEM System 55 Test Ob ectives
- 1. To demonstrate the operation of the turbine building HVAC system and components.
- 2. To 'nsure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures dura.ng testing. h Prereauisites All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. The glycol heating system is available to support testing.
Test Procedure
- 1. The elevator machine room ventilation fans and their interlocks with the inlet and outlet dampers are verified for proper operation.
The main stack substructure ventilation fans and exhaust dampers and associated interlocks are verified.
- 3. The turbine building main ventilation exhaust and supply fans and dampers are verified for proper operation.
- 4. The turbine building ventilation system' capability to maintain a negative pressure inside the turbine building is verified.'
of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-71 (Cont)
Acce tance Criteria
- 1. The turbine building HVAC system can, -
under normal building and operating conditions, maintain the turbine building at a slightly negative pressure in accordance with Section 9.4.4.
- 2. The turbine building supply fans, exhaust fans, dampers, and their associated interlocks function in accordance with SWEC design drawings.
- 3. System parameters fall within design requirements, as described in Section 9.4.4.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-72 RADWASTE BUILDING VENTILATION System 56 Test Ob ectives
- 1. To demonstrate the operation of the radwaste building ventilation system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prereceuisites
- 1. All applicable preliminary tests are completed and the system turned over to NNPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. An in-place DOP penetration test per Regulatory Guide 1.140 has been performed on the HEPA filters to confirm a satisfactory particulate removal efficiency.
Tes't Procedure
- 1. The test verifies system controls, interlocks, and fans are checked for proper operation in accordance with specifications.
- 2. The equipment exhaust subsystem fans and filter trains are veri f i ed.
- 3. Corresponding alarms and annunciators are verified for proper response in conjunction with various tests conducted.
All ductwork under positive pressure will be tested in accordance with procedures of the Associated Air Balance Council.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-72 (Cont)
Acce tance Criteria I
- 1. System controls, trips, and interlocks function according to SWEC design drawings.
- 2. Environmental conditions are maintained within design limits according to Table 9. 4-1.
- 3. System air flows are balanced in a way to maintain building pressure's within design requirements in accordance with Table 9.4-1.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-73.
DIESEL GENERATOR BUILDING HUAC SYSTEM System 57 Test Ob'ectives
- 1. To demonstrate the operation of the diesel generator I building HUAC system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere uisites
- l. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The remote manual controls for all fans, heaters, and dampers are verified.
- 2. The controls for the makeup air subsystem fan, damper, and heater are verified.
- 3. The controls of the normal supply subsystem fans and associated interlocks and dampers are verified.
- 4. The automatic and manual controls of the standby subsystem fans and associated interlocks and dampers are verified. I Acce tance Criteria
- 1. Temperature is controlled within the requirements of Table 9.4-1.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-73 (Cont)
- 2. The system parameters meet design requirements as described in Section 9.4.6.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-74 ELECTRIC TUNNELS VENTILATION SYSTEM System 59A Test Ob ectives
- 1. To demonstrate the operation of the electric tunnel ventilation system.
- 2. To ensure that the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during )
testing.
Prere uisites
- l. All applicable preliminary tests are completed.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve and damper lineups are completed.
Test, Procedure
- l. Interlock and control functions of fans and dampers will be verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-74 (Cont)
Acce tance Criteria
- 1. All protective functions operate in accordance with applicable SWEC documents.
- 2. System parameters fall within design requirements in accordance with applicable SWEC documents.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-75 DRYWELL COOLING SYSTEM System 60 Test Ob ectives
- 1. To demonstrate the operation of the drywell cooling I system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable prelxmxnary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Reactor building closed loop cooling system is available to support this test.
Test Procedure
- 1. The test will verify that the drywell unit coolers are capable of performing within design specifications.
- 2. Temperature sensors, system controls, and interlocks will be verified.
- 3. The system logic will be verified.
- 4. Alarms and annunciators are verified for response in conjunction with various tests performed.
1 of 2
Nine Nile Point Unit 2 FSAR TABLE 14.2-75 (Cont)
Acce tance Criteria
- 1. The system parameters meet design requirements, as described in Section 9.4.2.
- 2. System controls operate in accordance with applicable SWEC design drawings.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-76 PRIMARY CONTAINMENT PURGE SYSTEM System 61 Test Ob'ectives
- 1. To demonstrate the operation of the primary containment I purge system-and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during )
testing.
Prereauisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. $ 11 applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. The drywell must be able to be cl'osed.
- 5. The reactor building ventilation and standby gas treatment systems are available to support this test.
Test Procedure
- 1. The purge fan and its associated valves are verified.
- 2. System isolation controls and responses are verified.
- 3. Corresponding annunciators and computer alarms are verified in conjunction with various tests.
1 of 2
Nine Mile Point Unit 2 FSAR TAB"E 14.2-76 ( ont)
Acce tance Criteria
- 1. The system parameters meet design requirements as described in Section 9.4.2.
- 2. System controls and interlocks function to isolate in accordance with applicable SWEC design drawings.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-77 STANDBY GAS TREATMENT SYSTEM System 61 Test Ob'ectives 1.. To demonstrate the operation of the standby gas I treatment system and components.
- 2. To verify that the standby gas treatment system can maintain the proper reactor building pressure. I Safet Precaution Follow NMPC saf ety rules and proper procedures during I testing.
Prere isites
- l. All applicable preliminary tes'ts are completed and the system turned over to NMPC.
2 ~ All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Reactor building ventilation system is available, and all reactor building doors and hatches can be closed.
Test Procedure
- 1. The test procedure will verify that the two gas treatment filter trains operate according to design specifications under normal and transient conditions.
- 2. System auto initiations will be verified.
- 3. System controls and interlocks will be verified.
- 4. Standby gas treatment fan operation will be verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-77 (Cont)
- 5. The test will verify that the standby gas treatment system will accomplish its design objective of establishing the reactor building pressure equal to or below -0.25 in WG within the required time interval.
Acce tance Criteria
- 1. Applicable 'nterlocks and controls function in accordance with applicable design drawings.
- 2. Reactor building ventilation system isolation features operate in accordance with applicable design drawings.
- 3. Each standby gas treatment system train can maintain reactor building pressure equal to or below -0.25 in W.G. (see Section 6.5).
- 4. The secondary containment drawdown time to -0.25 in W.G.
is less than 90 sec, at a maximum of 3,600 cfm (see Technical Specification Section 3/4.6.5).
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-78 DBA HYDROGEN RECOMBiNER SYSTEM Svs"em 62 Tes" Ob ec ives
- 1. To d mons+rate the operation o the DBA hy" ogen recomb ner system and components.
- 2. To ensure the system is p operly designed and construe ed.
Safet Precaution Follow NMPC safety rules and prope" procedures during testing.
Prerecu'ites
- l. All applicable prelimina y tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply elec ric powe to motors, control circuits, and instrumentation are avai lable.
- 3. Valve lineups are completed.
Test Procedure
- 1. The recombiner unit logic and trips will be verif'ed.'
- 2. Sensors and associated instrumentation will be verified.
- 3. Corresponding alarms will be verified in conjunction with various tests per ormed.
- 4. The opera ion of solenoid and motor-operated valves will be verified.
1 of 2
Nine Mile Po'nt Unit 2 FSAR TABE.E 14.2-78 (Cont)
Acceptance Criteria
- 1. Tne hyd og .". recombiner units function in accordance with applicable SWEC design drawings.
- 2. System remote-controlled valves operate as described in applicable SWEC design drawings.
- 3. The hydroge.. recombiner unit blowers function to deliver design flow rates within'he requirements of Equipment, Specification No. NMP2-P282K.
2 of 2
N'ne Mile Po'nt Unit 2 FSAR TABL" 14.2-79 R"ACTOR BUILDING DRAINS System 63 Test Ob ectives
- 1. To 'emonst ate the operation of the reactor building l drain systems and components.
'2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prerecuisites
- 1. All applicable prelim'nary tests are completed and the system turned over to PC.
NMi
- 2. All applicable motor control centers to supply electric
.power to moto s, control ci cuits, and instrumentation are available.
- 3. Valve lineups a e completed.
- 4. Makeup water storage or another clean water system is available to support tes"ing.
Test Procedure
- 1. Demineralized water will be used for testing the equipment drain tanks and service water or fire protection water will be used for testing of the floor drain sumps.
- 2. The capacity of all of the reactor building floor drain sumps will be verified and compared to sump design volumes.
- 3. The auto start/stop and lead/lag features of the applicable system pumps are verified.
1 of 2
Nine Yiile Point Unit 2 FSAR TABlE 14.2-79 (Cont)
- 4. The ability of the system to transfer collecte" water to the liquid radwaste svstem will be verified.
Accentance Criteria
- 1. Pump auto and sequencing controls operate in accordance with the applicable SNEC design drawings.
- 2. The system is capable of trans err'ng collecte" liquids to the liquid radwaste system.
2 of 2
N'ne Mil Point Unit 2 FSAR TABI E 14. 2-80 TURBINE BUIIDING DRAINS System 64 Test Ob ectives
- 1. To demonstrate the operation of the turbine building drains system and components.
- 2. To ensure tne system is properly de'signed and constructed.
Safet Precaution Follow NMPC safetv rules and prope procedures during testing.
Prereauisites
- 1. All applicable preliminary tests are completed and the system i s turne' ove to NMPC.
I
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. An appropriate clean water system is available to support testing.
Test Procedure K
- 1. Clean water will be used to supply water for testing.
- 2. The autostart/autostop features of the sump pumps will be verified.
- 3. The test will verify the ability of the system to collect and process water to the liauid radwaste system.
- 4. Corresponding annunciators and alarms are verified in conjunction with the various tests performed.
S. The capacity of the sumps is verified and compared to sump design volumes.
1 of 2
Nine Mile Point Unit 2 E'SAR TABE,E 14.2-80 (Cont)
Acceptance Criteria
- 1. Pump auto and seauencing controls operate in accordance with applicable SWEC design drawings.
- 2. The system is capable of transferring collected liauids to the liauid radwaste system.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-81 RADWASTE BUILDING DRAINS System 65 Test Ob'ectives
- 1. To demonstrate the operation of the radwaste building I drains system and components.
- 2. To ensure the system is prope"ly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during I testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. A clean water system is available to support testing.
Test Procedure
- 1. Clean water will be used to supply water for testing.
- 2. The autostart/stop features of the sump pumps will be verified.
- 3. The test will verify the ability of the system to collect and process water to the liquid radwaste system.
4 Corresponding annunciators and alarms are verified in conjunction with the various tests.
~
of 2
Nine Mile Point Unit 2 FSAR TABLE 14;2-81 (Con )
Acce tance Criteria
- 1. Pump auto and sequencing controls operate in accordance with the applicable SWEC design drawings.
- 2. The system is capable of transferring collected liquids to the liquid radwaste system.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-S2 MISCELLANEOUS DRAINS DIESEL GENERATOR BUILDING FLOOR DRAINS, AUXILIARY SERVICE BUILDING, REACTOR BUILDING MAT, CONDENSATE STORAGE BUILDING, AND MAIN STACK DRAIN SYSTEM System 66 Test Ob ectives
- 1. To demonstrate the operation of the various miscellaneous drain systems and their components.
- 2. To ensure the systems are .properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are satisfactorily
~
completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. A clean water source is available to supply water for this test.
Test Procedure
- 1. The oil holding compartment is filled.
- 2. The diesel generator oil separator is verified so that it can handle flow from the three sumps and applicable monitors respond in accordance with design requirements.
- 3. The ability of the drain systems to transfer water for further processing and/or disposal will be verified.
- 4. Sump capacities are verified.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-82 {Cont)
- 4. Sump capacities are verified.
- 5. System automatic controls and associated alarm functions are verified.
Acce tance Criteria
- 1. The oil holding compartment will hold approximately 300 gallons of oil in accordance with Purchase Specification No. NNP2-N014S.
- 2. The oil separator 2DFM-SPl can handle hydraulic fluid
! flow from all three sumps individually, and applicable monitors respond as designed.
- 3. Level switches function in accordance with applicable
! LSKs.
, 4. The diesel generator building drain system meets its design requirements in accordance with Section 9.3'.3.
- 5. Sump capacities meet app'icable design specifications.
- 6. System controls function in accordance with applicable design drawings.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-86 DRYNELL FLOOR AND EQUIPMENT DRAIN SYSTEM System 67 Test Ob'ectives
- 1. To demonstrate the operation of the drywell floor and l equipment drain system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during I testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. All auxiliary systems needed for this test are available for support.
Test Procedure
- 1. The test will verify that, the drywell equipment and floor drains operate within system design specifications.
- 2. The auto controls and associated alarm functions for the floor and equipment drain pumps will be verified.
- 3. Operation of remote-controlled equipment will be verified.
- 4. The ability of the system to transfer water for further processing and/or disposal will be verified.
- 5. Sump capacities will be verified.
1 of 2
Nine Mile Point. Unit 2 FSAR TABZiE 14.2-86 (Cont)
Acce tance Criteria
- 1. The system functions as described in Section'.3.3.
- 2. Sump capacities meet design specifications.
- 3. System automatic controls function as designed.
Nine Mile Point Unit 2 FSAR TABLE 14.2-95 UNINTERRUPTEBLE POWER SUPPLY System 71 Test Ob ectives
- 1. To demonstrate the operation of the uninterruptible power supply system (UPS) and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centersinstrumentationto supply electric power to control circuits and are available.
- 3. All auxiliary systems needed for the preoperational test are available for use.
Test Procedure
/
- 1. The test procedure will demonstrate that the UPS performs as designed using normal and alternate ac supplies.
- 2. Proper voltage regulation of the UPS will be verified.
- 3. The ability of the UPS to carry and transfer full load will be demonstrated ( from the UPS to the alternate ac automatically and manually).
source and vice versa
- 4. The UPS will be tested to verify its capability to carry load on battery power.
- 5. Simulating an inverter loss, the static switch will be tested to alternate show that ac source it can transfer without loss of load.
load to the 1 of 2
Nine Mile Point Unit 2 CESAR TABLE 14.2-95 (Cont)
- 6. Alarms and control instrumentation will be verified for proper operation in conjunction with the various tests conducted.
Acce tance Criteria
- 1. The UPS performs its intended function using both normal and alternate power supplies'.
The system functions as described in Section 8.3.1.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-100 NORMAL DC SYSTEMS (24/48V)
System 73 Test Ob ectives
- 1. To demonstate the operation of the 24/4S-V dc systems I and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution
- 1. Follow NMPC safety rules and proper procedures during testing.
- 2. Protective apron, gloves, and face shield shall be worn when measuring specific gravities.
- 3. Fresh water should be available in case acid is splashed on skin or eyes.
Prere isites 1 ~ All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to control circuits and instrumentation are available.
- 3. Control building ventilation or portable ventilation is available to exhaust the battery rooms. I Test Procedure
- 1. A load bank system will be used to establish desired loads during discharge test.
- 2. The test verifies that the batteries will function as designed by conducting a capacity test.
- 3. The battery chargers will be tested to demonstrate their ability to recharge the batteries with steady-state load connected.
1 of 2
Nine Mile Point Unit, 2 FSAR TABLE 14.2-100 (Con )
Acce tance Criteria
- 1. Each battery set will demonstrate a capacity greater than that required for a 4-hr discharge at design load, as evidenced by the battery capacity, corrected to 77 F, equal to or greater than 90 percent of the manufacturer's rating at the 4-hr rate.
- 2. Batteries 3A, 3B, 3C, and 3D can be fully recharged in a 24-hr period from minimum charge condition, utilizing the battery chargers with the calculated steady-state load connected in accordance with Section 8.3.2.
- 3. Undervoltage alarms to PGCC will alarm with loss of voltage in accordance with Section 8..3.2.1.3.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14. 2- 101 EMERGENCY DC SYSTEMS System 74 Test Ob ectives
- 1. To demonstrate the operation of the emergency dc systems )
and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution
- 1. Follow NMPC safety rules and proper procedures during )
testing.
- 2. Protective apron, gloves, and face shield shall be worn when measuring specific gravities ~
- 3. Fresh water shall be available in case acid is splashed on skin or eyes.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Control building ventilation or portable ventilation is available to exhaust the battery rooms.
Test Procedure 1.
load bank system and/or normal dc system will be used to establish desired loads during discharge test, as available.
- 2. The batteries will be subjected to a 2-hr service test discharge in accordance with a precalculated load profile.
3.'he battery chargers will be, tested to demonstrate their ability to recharge the batteries with a simulated 1 of 2
Nine Mile Point Unit 2 PSAR TABKE 14. 2-101 ( ont) steady-state load connected from their minimum charge state.
- 4. The batteries will be subjected to a capacity test.
- 5. Ni th the batteri es in a low voltage condition, as defined by technical specifications, the test will verify that the voltage applied to designated Class 1E loads is within the required operating range for that equipment. This verification will be performed on equipment that has been identified by an engineering review as potential voltage-drop problem cases.
Acce tance Criteria 1 ~ Each . battery will demonstrate a capacity equal to or greater than that required during the 2-hr service discharge test evidenced by the terminal voltage remaining above 105-V in accordance with Section 8.3.2.
2 ~ Each battery charger is 'capable of supplying the combined demands of steady state loads while recharging its associated battery to a full-charge condition within 24 hr from the minimum charge state.
- 3. Ground detection indication and annunciation for Batteries 2A, 2B, and 2C function as designed.
- 4. Dc bus undervoltage 'relays and associated alarms function as designed.
- 5. Battery capacities are 290 percent of the manufacturer's rated capacity.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-102 STATION EMERGENCY LIGHTING SYSTEM System 75 Test Ob'ectives
- 1. To demonstrate the operation of the station and I emergency lighting system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable distribution panels to supply electric power are available.
Test Procedure
- 1. The emergency lighting system is verified to provide adequate illumination in areas required for operating safety-related equipment during emergency conditions.
- 2. The essential lighting system is checked to ensure adequate illumination is provided for certain critical areas of the station such as the control .room.
- 3. The egress lighting system is verified to provide adequate illumination for all egress signs and egress routes.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 3.4.2-102 (Cont)
Acce tance Criteria
- 1. All station emergency lighting systems vill be shown to provide adequate lighting in accordance vith Table 9.5-2.
I 2. The system functions as described in Section 9.5.3.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-103 PLANT COMMUNICATION SYSTEM System 76 Test Ob'ectives
- 1. To demonstrate the operation of the plant communication systems and components.
- 2. To ensure the system is properly designed and constructed.
- 3. To verify that the plant communication systems can provide proper intraplant and plant-to-off site communications.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prereauisites
- 1. All applicable preliminary tests are completed and the system is turned over to NMPC ~
- 2. All applicable distribution panels to supply electric power are available.
Test Procedure
- 1. The test will verify the proper operation of the plant page party/public address communication system.
- 2. The system' emergency evacuation alarm and other emergency alarms will be verified.
- 3. The test will verify that plant communication systems provide communications indoors, outdoors, and off- site.
- 4. Verification of power supplies for communication equipment will be performed.
Acce tance Criteria The system's emergency evacuation alarm and other emergency alarms function and provide audible alarm signals throughout the plant.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-103 (Cont)
- 2. The intraplant and plant-to-offsite communications operate as designed.
- 3. The plant communication systems function in accordance
! with Section 9.5.2.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14. 2- 104 REMOTE SHUTDOWN System 78 Test Ob ectives
- 1. To demonstrate the operation of remote shutdown system.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- l. All applicable pxeliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentat'on are available.
- 3. All support systems needed for this preoperational test are available for test use.
Test Procedure
- 1. The test procedure will verify that the remote shutdown system is capable of properly operating the required shutdown systems and their components. I
- 2. System interlocks, controls, and instrumentation will be verified for proper response.
- 3. It will beremote from the demonstrated that no systems can be shutdown panel unless the operated specific transfer switch is placed in. the emergency position.
- 4. Control functions transferred to the remote shutdown panel from the normal control panel in the control room can only be operated from the remote shutdown panel.
- 5. All applicable alarms will be verified for proper operation in conjunction with various tests performed.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14. 2- 104 ( Cont )
Acce tance Criteria
- 1. The remote shutdown system transfer switches override controls from the main control room and transfer controls to the remote shutdown panel.
- 2. All shutdown panel control switches demonstrate proper control over appropriate equipment.
- 3. All shutdown panel instrumentation functions as designed.
- 4. The system functions as described in Section 7.4.1.4.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-105
~
AREA, PROCESS AIRBORNE, AND GASEOUS RADIATION MONITORING SYSTEMS Systems 79, 80A I
Test Ob ectives
- 1. To demonstrate the operations of the digital and nondigital radiation monitoring systems and components.
- 2. To ensure the systems are properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
'1. All apylicable preliminary tests are completed and the systems are turned over to the NMPC.
- 2. All applicable motor control centers to supply electric power to control circuits and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Calibration of detectors and monitors using spec'ific samples and/or sources has been completed.
Test Procedure Annunciators, alarms, and trip functions for the digital radiation monitoring and nondigital radiation monitoring systems are verified to ensure that monitors provide warning of increasing radiation levels, power failures, or component malfunctions.
- 2. Alarms, set points, and indicators are verified by simulated signals or parameter variation ( samples or sources).
- 3. System isolations which are initiated by the process radiation monitoring system will be demonstrated in those systems'pplicable preoperational tests.
1 of 2
Nine Nile Point Unit 2 FSAR TABLE 14.2-1CS (Cont)
Acce tance Criteria
- 1. The process radiation systems provide continuous indication of selected radiation levels.
- 2. Alarms function on increasing radiation levels.
- 3. All automatic actions initiated by the process radiation monitoring systems function as designed.
- 4. The systems function as described in Section 11.5.
2 of 2
Nine Mile Point Unit, 2 FSAR TABLE 14.2-106 MAIN STEAM LINE RADIATION MONITORING SYSTEM System SOB Test Ob'ectives
- 1. To demonstrate the operation of the main steam line radiation monitoring system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system is turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to control circuits and instrumentation are available.
Test Procedure
- 1. System alarms, detectors, indicators, and annunciators are checked to ensure they detect and measure gamma radiation levels at the main steam lines.
- 2. Alarms and set points are initiated to verify that the system provides indication and annunciation in the main control room of main steam line zadiation levels.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-106 (Cont)
Acce tance Criteria .
- 1. The system functions as designed in accordance with Section 11.5.2.2.1.
- 2. All applicable alarms and annunciators function as designed.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-107 CONTAINMENT LEAKAGE MONITORING System 81 Test Ob'ectives
- 1. To demonstrate the operation of the containment leakage monitoring system and components.
- 2. To ensure the systems are properly designed and constructed.
Safet Precaution testing.'ules Follow NMPC safety and proper procedures during )
Prere isites '.
All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All appli'cable distribution panels to supply electric power to control circuits and instrumentation are available.
- 3. No primary containment isolation signals present.
Test Procedure
- 1. The drywell and suppression chamber manometer isolation valves are tested. l
- 2. All drywell electrical penetrations are pressure tested.
- 3. Associated annunciators and computer alarms will be ve ified by simulated signals or actual parameter variation in conjunction with tests pe formed.
Acce tance Criteria
- 1. Each leakage monitoring valve must be operable from the individual switches and isolated in pairs from their respective isolation switches. Proper. valve and off normal status display indication function as required in accordance with the LSKs. I 1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-107 (Cont) 2.. The isolation valves must isolate on a containment isolation signal. The'. isolation valves must provide proper computer response as to their respective positions in accordance with applicable SWEC design drawings.
- 3. All electrical penetrations must maintain pressure and associate annunciators and computer alarms function when a low pressure condition exists.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-108 CONTAINMENT ATMOSPHERE MONITORING System 82 Test Ob'ectives
- 1. To demonstrate the operation of the containment atmosphere monitoring systems and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- l. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to control circuits, and instrumentation are )
available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test procedure will ensure that the containment monitoring system will provide indication of atmospheric conditions in the drywell and suppression chamber.
- 2. Hydrogen, oxygen, and humidity analyzers; drywell radiation monitors, suppression pool water level elements, and drywell and suppression pool temperature and pressure elements will be checked for proper operation.
- 3. Alarms, annunciators, control instrumentation, and interlocks will be tested for correct response for each test condition.
- 4. The test will simulate abnormal operating conditions to test the isolation features of the system.
1 of 2
Nine Mile Point Unit 2 CESAR Table 14.2-108 (Cont)
Acce tance Criteria
- 1. The containment monitoring system measures the containment atmospheric conditions and provides the information to the main control room.
- 2. Control room instrumentation responds correctly to parameter variations.
3 . All applicable 'alarms and annunci ators function in accordance with Section 6.2.1.7.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-109 PRIMARY CONTAINMENT ISOLATION SYSTEM (NSSS)
System 83 Test Ob ectives
- 1. To demonstxate the operation of the primary containment isolation system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC saf ety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test procedure ensures that the system automatically isolates appropriate lines penetrating the primary containment when predetermined plant limits are reached.
- 2. The drywell-to-suppression pool and containment vacuum I breakers will be vexified for proper operation.
- 3. All applicahble set points, alarms, and annunciators related to this system will be tested in conjunction with tests performed.
Acce tance Criteria
- 1. The system functions in accordance with Section 6.2.4.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-109 (Cont)
- 2. All primary containment isolation functions operate in accordance with applicable design drawings.
2 of 2
0 Nine Mile Point Unit 2 FSAR TABLE 14.2-110 REACTOR BUILDING - POLAR CRANE System 84 Test Ob ectives
- 1. To demonstrate the operation of the reactor building-polar crane and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules end proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Dynamic and static load tests, at 100 percent and 125 percent of rated load, have been performed satisfactorily.
Test Procedure
- 1. All pendant and radio controls are verified for proper operation.
- 2. The operation of all locking and safety devices is veri fi ed.
- 3. The restrictive path operation is verified.
- 4. Nondestructive and functional testing of the special lifting devices for reactor vessels internals will be performed.
Acce tance Criteria
- 1. All limit switches, interlocks, and locking and safety devices function as designed.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-110 (Cont)
- 2. The polar crane responds correctly to all pendant and remote control functions.
- 3. The testing of the special lifting devices has been sati sf actorily completed in accordance with ANSI N14.6-1978.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-112 REACTOR COOLANT AND ECCS LEAK DETECTION SYSTEM System 85 Test Ob'ectives
- 1. To demonstrate the operation of the reactor coolant and ECCS leak detection system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Alarm set points are set according to design requirements.
Test Procedure Valve, sensor, and logic tests are performed to determine proper operation on the following systems:
- 1. Area leak detection systems and equipment.
- 2. Leak detection for drywell floor and equipment drain sumps.
,3. Drywell coolers condensate monitoring.
- 4. Leak detection for reactor building equipment and floor drain sumps.
- 5. Flow leak detection for RWCU system.
- 6. Safety system for RCIC turbine exhaust.
1 of 2
Nine Mile Point Unit 2 FSAR TABKE 14.2-112 (Cont)
- 7. Head seal leak detection.
- 8. Drywell and reactor vessel head vent line leak detection.
- 9. Drywell air cooler temperature monitoring.
- 10. Main steam line relief and safety valve leakoff.
- 11. RCIC and main steam line high flow detection and RCIC low pressure detection.
- 12. RHR/RCIC steam line high flow detection.
- 13. Fission products monitoring subsystem.
Acceptance Criteria All applicable system parameters are within the design requirements, as detailed in GE design specifications.
2 of 2
Nine Mile Point Unit 2 FSAR LOOSE PARTS MONITORING AND VIBRATION MONITORING SYSTEM System 86
.Test Ob ectives
- 1. To demonstrate the system's ability to monitor structural stability of the reactor vessel internal components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prereauisites
- l. All applicable preliminary tests are completed and the system turned over to NHPC.
- 2. All applicable motor control centers to supply electric power to control circuits and instrumentation are available.
I Test Procedure
- 1. The RPV will be drained to allow a complete vessel internal inspection.
- 2. The loose parts monitoring s'stem wi,ll be tested to ensure proper response to induced vibration signals.
Acce tance Criteria All design parameters are within design limits in accordance with GE design specifications.
0 Nine Mile Point Unit 2 FSAR TABLE l4.2-li3 (Cont.)
THE INFORMATION ON THIS PAGE HAS BEEN DELETED.
2 of 2
Nine Mile Point Unit 2 FSAR TAD4Cs 14.2-114 CONTAINMENT INERTING SYSTEM System 88 Test Ob ectives
- 1. To demonstrate the operation of the containment inerting system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned ove to NMPC.
- 2. A11 applicable motor control centers to supply elec" ic power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- l. The test procedure ensures system controls, interlocks, and valves are verified for proper operation.
- 2. Alarms and instrumentation are verifie4 in conjunction with tests performed.
- 3. The test procedure will verify the system's abili'ty to inert the containment and maintain the oxygen concentration at or below 4 percent.
Acce tance Criteria
- 1. All applicable parameters are within design specif ications.
- 2. Applicable interlocks, controls, and remote-operated equipment operate in accordance with design.
1 of 2
Nine Mile Point Unit 2 CESAR TABLE l4.2-iii ~Cont,)
- 3. The system is capable of supplying nitrogen gas for inerting the primary containment when required and maintaining an inert atmosphere in the containment during normal operations in accordance with Section 9.3.
2 of 2
0 Nine Mile Point. Unit 2 FSAR SEISMIC MONITORING SYSTEM System 90 Test Ob ectives
- l. To demonstrate the operation of the seismic monitoring system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prereauisites
- l. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to control circuits and instrumentation are available.
I Test Procedure
- 1. The test verifies proper operation of the system and instrumentation and alarms.
- 2. The test verifies the seismic monitoring system's ability to monitor and record seismic motion.
Acce tance Criteria
- l. All applicable alarms and annunciators function as designed.
- 2. The system detects, records, and provides immediate information for seismic events at the plant site.
- 3. The system functions as described in Section 3.7.4A.
1 of 2
Nine Mile Point Unit 2 FSAR t /A anua r xv. c.-ai3 A 4
(~one j Tir INFORMATION ON THIS PACE HAS BEEN DELETED.
2 of 2
Nine Mile Point Unit 2 ESAR J.llDLCi 4
J4 c i '
PROCESS COMPUTER System 91 Test Ob'ectives
- 1. To demonstrate the operation of the process computer and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NYP
- 2. All app'cable moto control centers to supply elec"'c power are availab e.
Test Procedure The test will verify that the process computer can properly p ocess analog input signals from various sensors, initiate annun 'tors when =ransients occur, and generate a printout of system parameters of the monitored event.
- 2. The test will ve ify that all sen ors o signal device digital input signals initiate annunciators and generate printouts of monitored events.
- 3. The test will verify proper operation of system features provided for display/printout of plant parameters.
- 4. The test will verify by use of -est cases proper operation of nuclear steam supply system calculations and balance of plant performance calculat'ns.
The system and all app'icable parameters function in accordance with design specifications.
1 of 1
Nine Mile Point Unit 2 FSAR TAiiE 14. 2-117 NEUTRON MONITORING System 92 Test Ob'ective
- 1. To demonstrate the operation of the neutron monitoring I systems and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- i. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable moto" con" ol centers to supply electric power to motors, con" ro1 circuits, and instrumentation are available.
Test Procedure Ve ification of the neutzon monitoring system capability will be demonstrated by the proper integrated operation of the following:
SRN and IRM detectors and their respective insert and retract. mechanisms and cables.
- 2. SRN and IRM channels, including zecordezs, trip logic, I bypass logic, system interlocks, power supplies, and annunciators.
All LPBM detectors and their respective input signals to corresponding APRMs.
All APRM channels, including trips, bypasses, recorders, interlocks, and annunciators.
Recirculation flow bias signals input to the neutron monitoring system.
1 of 2
Nine Nile Point Unit 2 CESAR TAua E L4. 2-ll I (Cont j Acce tance Criteria All applicable parameters are within design specifications in accordance with GE design specifications.
2 of 2
r Nine Mile Point Unit 2 FSAR inDuC, 4 O J.'X ~
8 C
1 \
iiD ROD BLOCK MONITORING System 93 Test Ob 'ectives
- 1. To demonstrate the operation of the rod block monitoring system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control cente s to supply electric power to motors, cont ol circuits, and instrumentation are available.
Test Procedure
- 1. The test will verify that each LPRM input signal for a selected control rod will be displayed in the correct meter group.
- 2. Verification will be made for the various trip modes using simulated. signals for different operating conditions.
- 3. The test will verify independent Bus A and B power supplies to corresponding RBM channels.
4, All associated annunciators', recorders, control I instrumentation, and system interlocks will be tested for proper operation according to design specifications for the RBM system.
Acce tance Criteria All applicable system parameters are within design specifications in accordance with GE design specifi'cations.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE l4.2-118 (Cont)
THE INFORMATION ON THIS PAGE HAS BEEN DELETED 2 of 2
Nine Mile Point Unit 2 FSAR We e e A
~
xnDaeC I 'S ~ C JLV TRAVERSING INCORE PROBE SYSTEM System 94 Test Ob'ectives
- 1. To demonstrate the operation of the traversing incore probe system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during )
testing.
Prere isites
- l. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor con" rol centers to supply electric power to motors, 'control circuits, and instrumentation are available.
I'
~ Drive mechanism and indexer purge system is operating.
- 4. Flux probing monitors are calibrated and amplifiers. have correct setting.
Test Procedure
- 1. ~
Cross calibration interlocks are verified.
- 2. All shear valve monitor lamps function correctly and squib current is monitored accurately.
- 3. The manual opera ion mode is verified.
- 4. The automatic operation mode is verified.
S. The manual override is checked for proper operation.
- 6. The automatic stop is checked f'r proper. operation.
1 of 2
Nine Nile Point Unit 2 FSAR Tha)us 148 s0 1wig6 vvss i~
I p1
' ' 'I g f
- 7. The'utomatic detector . withdrawal is verified on containment isolation, loss of 125 V dc, or loss of the shear valve monitor signal.
- 8. The containment secure lamp circuits are checked for correct operation.
- 9. The manual scan, manual ball valve, and low speed control operations are verified.
Acceptance Criteria All applicable parameters are within design specifications in accordance with GE design specifications.
2 of 2
Nine Mile Point Unit 2 FSAR A
A.EDUC>
4 >
'I'S IA 4 J.CV ROD WORTH MINIMIZER SYSTEM System 95A Test Ob ectives
- 1. To demonstrate the operation of the rod worth minimizer I system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. .All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor cont"ol centers to supply elect ic power to control circuits and instrumentation are I available.
I
- 3. All auxiliary systems required for the test will be available for test use. I Test Procedure
- 1. The test will verify for power ascension and normal operating modes, the ability for the RWM to restrict, monitor, and initiate error signals for rod movement and selection.
- 2. Proper operation will be verified for all computer inputs, associated annunciators, control instrumentation, and system interlocks of the RWM system.
Acceptance Criteria The system parameters are within design specifications in accordance with GE design specifications.
1 of 2
Nine Mile Point Unit 2 FSAR awe>>
TnDuc xs. c.-Lcrv ('vvll4 f THE INFORMATION ON THIS PACE HAS BEEN DEiETED.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14. 2-121 ROD SEQUENCE CONTROL SYSTEM System 95B I
Test Ob'ectives
- 1. To demonstrate the operation of the rod sequence control system and components.
- 2. To ensure the 'system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during I testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned ove" to NMPC.
- 2. All applicable motor con rol centers to supply electric power to control circuits and instrumentation are I avai 1 able.
3 ~ The rod position indication system, reactor manual control system (RNCS), and the CRD system are, available to support this test.
Test Procedure
- 1. The logic for each RSCS status and resultant displays, annunciators, and set points is verified..
- 2. The performance of the rod pattern controller is verified.
- 3. Supply of continuously updated rod position data from the rod position indication system to the RSCS is verified.
- 4. Provision for single rod bypass is checked.
- 5. Rod sequences are verified with respective control rod group assignments.
- 6. Constraints of rod movement are verified.
1 of 2
Nine Mile Point Unit, 2 FSAR TABi E ii.c-l2l jConi )
Acceptance Criteria All applicable parameters are within design specifications in accordance w'ith GE design specifications.
2 of 2
Nine Mile Point Unit 2 FSAR LADMs L 0 4 l4 4 REACTOR MANUAL CONTROL AND ROD POSITION INDICATION System 96 Test Ob'ectives
- 1. To demonstrate the operation of the reactor manual control and rod position indication system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prereauisites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All. applicable motor control centers to supply electric power to control circuits and instrumentation are available.
- 3. The cooling fans in the control room 'panel for rod display are operable.
Test Procedure
- 1. All rod blocks, alarms, and interlocks for all modes of the reactor mode switch are verified.
- 2. A test simulator will supply rod position information to verify the proper operation of the displays and alarms associated with the RPIs.
- 3. The rod drift alarm is tested for proper operation.
- 4. All control modes are utilized to verify the proper functioning of the manual control system, the proper energization seauence, and the proper timing of the CRD directional control valves and stabilizing valves.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-122 (Cont)
Acce tance Criteria All applicable parameters are within design specifications in accordance with GE design specifications.
2 of 2
0 Nine Mile Point Unit 2 FSAR JaDuC JC C 440 REACTOR PROTECTION SYSTEM System 97 Test Ob'ectives
- 1. To demonstrate the operation of the reactor protection system and components.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor control centers to supply elec ic power to motors, control c'cuits, and instrumentation are available.
- 3. The following control rod drive hydraulic system components are installed and available: backup scram valves, scram pilot valves, the discharge volume isolation pilot. valves, the scram valves, and discharge header drain and vent valves, and scram valve position lights.
- 5. RPS motor-generator set performance and full load testing is completed.
Test Procedure
- 1. All valve, sensor, and logic tests are performed to demonstrate system operability.
- 2. The sensor to actuator relay test is performed to verify system interconnections and proper actuation of relay logic associated with system sensors.
1 of 2
Nine Mile Point Unit 2 FSAR TALC J.4 o C LAD (Cont )
Response time testing will be performed for all RPS equipment requi red to be tested by the Technical Specifications and will be measured from the process sensor through the final actuating device.
- 4. The mode switch is checked in each of its modes of operation to verify that all functions are operating properly.
- 5. The scram trip system is tested to demonstrate its operability.
- 6. Associated annunciator and computer alarms are checked for proper response in conjunction with the tests performed.
- 7. The trip system power independence and fail-safe feature is verified.
Acceptance Criteria
- 1. All applicable paramete s are w'thin design specifications in accordance with GE design specifications.'
- 2. Response times shall be within parameters specified in technical speci fications.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-125 STANDBY DIESEL GENERATORS System 100A Test Ob'ectives
- 1. To demonstrate the operation of the standby diesel generators and supporting fuel and starting air system.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable moto" control centers to supply electric power to motors, control circuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Service water system is available to'upport testing.
.5. No. 2 diesel fuel oil is available from the diesel oil change tanks.
Test Procedure
- 1. The air compressors are checked to verify that they deliver air at design pressure to the air receivers, and all controls are tested to verify that air receiver pressure is maintained within design limits.
- 2. The engine-driven and motor-driven circulating water pumps are verified to function as designed and verified that the jacket water system can maintain engine temperature within design limits.
- 3. The diesel generator lubrication oil system is tested to demonstrate its ability to deliver lubrication oil to required engine components and maintain the oil temperature within design limits.
1 of 3
Nine Nile Point Unit 2 FSAR TABLE 14.2-125 (Cont)
- 4. The test will demonstrate proper operation of the diesel generators during loading, including a complete loss of load, with verification of voltage requirements and overspeed limits.
- 5. The ability to synchronize the diesel generator, while under load, with offsite power sources will be demonstrated.
- 6. Applicable alarms and annunciators will be verified for proper operatio'n in conjunction with the various tests performed.
- 7. Full load-carrying capability will be demonstrated during a 24-hr test run, 22 hr of which will be at the load equivalent of the continuous rating and 2 hr at the 2-hr rating of the diesel generator.
- 8. The manual and automatic features for each standby diesel generator fuel oil transfer pump are tested for proper operation.
Acceptance Cr'teria
- 1. Each diesel generator starts, accelerates to rated spec/, voltage, and frequency, and is ready for loading sequence within 10 sec of receipt of the start signal.
- 2. Diesel generator voltage requirements are maintained, and overspeed limits are not exceeded during a complete loss of load.
- 3. With the generator connected to the emergency or equivalent larger load, it can be synchronized and the load transferred to the offsite power source.
- 4. The engine jacket water system functions to maintain engine temperatures within design limits in both standby and operating conditions.
l 5. The d'esel generator lubrication oil system functions to lubricate engine bearings and other moving parts with the generator in operation and maintains oil temperature within design limits when engine i s in a standby condition.
2 of 3
Nine Mile Point Unit 2 FSAR TABLE 14.2-125 (Cont)
- 6. The diesel generator fuel oil transfer pumps start automatically when a day tank low level occurs and stop automatically when a day tank high level occurs.
- 7. Each air compressor is capable of recharging the air receivers from minimum to maximum operating pressure in 45 min or less.
- 8. The starting air supply i s capable o f starting the diesel" generators five times from maximum operating pressure without recharging.
- 9. The diesel generators can maintain full rated load at normal operating voltage and frequency without exceeding any operational limits.
- 10. The diesel generators can maintain operating voltage and frequency during an overload condition equivalent to its 2-hr rating for 2 hr.
3 of 3
Nine Mile Point Unit 2 FSAR HPCS DIESEL GENERATOR System 100B Test Ob ectives
- 1. To demonstrate the operation of the HPCS diesel generator and supporting fuel and starting oil systems.
- 2. To ensure the system is properly designed and constructed.
Saf et Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- 1. All applicable preliminary tests are completed and the system turned over to NMPC.
- 2. All applicable motor con ol centers to supply electric power to motors, control c'cuits, and instrumentation are available.
- 3. Valve lineups are completed.
- 4. Service water system is available to support testing..
- 5. No. 2 fuel oil is available from the diesel oil storage tanks.
Test Procedure
- 1. The air compressors are checked to verify that they deliver air at design pressure to the air receivers and all controls are tested to verify that air receiver pressure is maintained within design limits.
- 2. The engine jacket water system is verified to function as designed and verified that it maintains engine temperature within design limits.
- 3. The HPCS diesel generator lubrication oil systems will be tested to verify their ability to supply oil to necessary engine components and maintain the engine in a warm prelubricated standby condition.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-126 (Cont)
- 4. The test will demonstrate the operation of the diesel generator during loading, .including complete loss of load, with verification of voltage requirements and overspeed limits.
- 5. The load,
'bility with to synchronize the generator, while under offsite power sources will be demonstrated.
- 6. The test will demonstrate proper operation of the diesel generator under full rated load and overload conditions.
- 7. All applicable alarms and annunciators will be verified for proper operation in conjunction with the tests performed.
- 8. The manual and automatic features for each standby diesel generator fuel oil transfer pump are tested for proper operation.
Acceptance Criteria
- 1. The HPCS diesel generato starts, accelerates to rated speed, voltage, and frequency within 13 sec of receipt of a start signal.
- 2. Diesel generator voltage requirements are maintained, and overspeed limits are not exceeded during a complete I loss of load.
- 3. With the generator connected to the emergency or
! equivalent load, it can be synchronized transferred to the offsite power source.
and load
- 4. The engine jacket water system functions as designed to maintain engine temperature within design limits in both standby and operating conditions.
- 5. The diesel generator lubrication oil system functions to lubricate engine bearings and other moving parts and maintain the engine in a warm prelubricated standby condition.
- 6. The diesel generator fuel oil transfer pumps start automatically when a day tank low level occurs and stop automatical'ly when a day tank high level occurs.
2 of 2
Nine Nile Point Unit 2 FSAR LZ$DLE 14 2 12 D '{ Cont )
- 7. Each air compressor is capable of recharging the receivers from minimum to maximum operating pressure in 30 min or less.
- 8. The starting air supply is capable of starting the diesel generators five times from maximum operating pressure without recharging.
- 9. The diesel generator can maintain full rated load at normal operating voltage and frequency without exceeding any operational limits.
- 10. The diesel generator can maintain operating voltage and frequency during an overload condition equivalent to its 2-hr rating for 2 hr.
2a c~ 2
Nine Mile Point Unit 2 FSAR TADLE 1 t ~ 2 leo REDUNDANT REACTIVITY CONTROL SYSTEM System 106 Test Ob'ectives
- 1. To demonstrate the operation of the redundant reactivity control system (RRCS), its components, and interconnecting systems that perform the RRCS function.
- 2. To ensure the system is properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prereauisites
- 1. All applicable preliminary tests are completed for the RRCS and all interconnect'ng systems, i.e., control rod drive, reactor recircuia"ion, =eedwaze , standby licruid control, nuclear boiler, RNCU, and neutron monitoring,
- 2. The system is turned over to NMPC.
- 3. Applicable portions of interconnect'ng systems are available for testing, as needed.
Test Procedure test procedures ensures that all components, 1 ~ The controls, logic, and interlocks are checked operation.
'or proper
- 2. All applicable alarms are verified in conjunction with the tests performed.
- 3. All automatic signals and actuations are verified by simulated signal or actual parameter variation.
- 4. All system interfaces and interactions are verified.
Acce tance Criteria
- 1. All applicable interlocks and trips function as designed.
1 of 2
Nine Mile Point Unit 2 - FSAR PWDtg ss 4 gIP Tc1vsaa s1)I4 s9 150 vvsa Ia
- 2. All automatic actuations function as designed.
- 3. The system functions as described in Section 15.8.
2 of 2
Nine Mile Point Unit 2 FSAR M% Me a C10 au@ j 'Z ~
A Ce
% AA LOSS OF POWER/ECCS FUNCTIONAL TEST Test Ob'ectives To demonstrate the onsite electrical distribution systems in conjunction with the QCCS system during simulated emergency.
- 2. To ensure the systems are properly designed and constructed.
Safet Precaution Follow NMPC safety rules and proper procedures during testing.
Prere isites
- l. All aPPlicable preliminary tests of distribution system are complete and the the electrical system turned over to NHPC.
- 2. Valve lineups are completed.
- 3. The following systems must be available in a normal operati onal mode to support testing: service water, diesel generators, diesel generator HVAC, RHR, RCIC, HPCS, LPCS, process computer, control building HVAC, RPS, reactor recirculation, reactor building HVAC, standby gas treatment, and thei r preoperational tests complete.
Test Procedure
- 1. The test will demonstrate proper Power System response to a loss of the 115 Kv Distri'bution System, independently and simultane-ously, both with and without LOCA/containment isolation signals.
- 2. The test will verify that there is no voltage present at selected nonenergized buses.
- 3. Redundancy and independence of the emergency distribution systems will be demonstrated by simulating losses of redundant divisions and verifying the correct operation of the operable division and nonoperation of the deenergized buses/equipment.
1 of 2
Nine Mile Point Unit 2 FSAR 0 ~ Ch tacAA
%Ear 1 J A LhDvC 0 (4on>
~ ~
J J The test will verify the capability of the diesel generators to:
- a. Start. and assume the design loads for LOCA/containment isolation and/or loss .of offsite power in the specific sequential loading times.
- b. Maintain voltage and frequency during loading.
- c. Reject the largest single load any time after the design loading sequence is complete.
- 5. The test. will verify that 'the emergency loads can operate with the minimum and maximum design ac voltages available.
- 6. Temperature rise on all large power transformers will be verified under maximum available load.*
- 7. Voltage drops will be verified between load centers and MCCs at max'mum available load" and ex-rapolated to rated load condi 'ons.
- 8. Voltage drops between MCCs and selected motor loads, representative of the most severe set of load and cable sizes and cable length, will be verified to be within acceptable limits.
- g. The test will demonstrate that the normal AC Power System can provide sufficient power to start, accelerate and run the ECCS and selected normal plant loads during simulated LOCA conditions.
Acceptance Criteria
- 1. Systems required to operate during LOCA and/or loss of offsite power conditions operate within time and load requirements of their design in accordance with Section 8.3.
In the event one diesel generator becomes unavailable, the remaining two diesels will be capable of feeding the loads necessary for safe plant shutdown in accordance with Section 8.3.
- Maximum loads available inplant not exceeding the rating of the equipment.
2 of 2
Nine Nile Point Unit 2 PSAR TAB4Z l4 ~ 2 l29 (Cocii )
- 3. The failure of any one electrical division does not af fect. the operation of the others or their LOCA/containment isolation functions.
- 4. The diesel generators can start and assume their LOCA/containment isolation and/or loss of power loads in the specified times and sequence while maintaining voltage and frequency within specified limits, from both cold (normal standby) and hot (operating) temperatures.
- 5. On a loss of the largest single load the diesel generator does not, overspeed or exceed 75 percent of the overspeed setting, whichever is greater.
- 6. The design emergency loads can start, and run properly under minimum and maximum ac voltage conditions.
- 7. The temperatures on the large power transformers do not exceed the transformer' maximum rated temperature while ca"rying max'mum available load.
- 8. Voltage drops from load centers "o MCCs and MCCs to motor loads shall be w="hin des'gn requi ements.
- 9. The ECCS loads can be started, accelerated and run whHe being suPplied from normal offsite or standby AC Power Systems.
2a of 2
Nine Mile Point Unit 2 FSAR STRUCTURAL INTEGRITY INTEGRATED LEAK RATE TEST Test Ob'ectives
- 1. To verify the overall structural integrity of the primary containment.
2 ~ To determine primary containment leakage rates with the containment at test pressure.
Safet Precaution Follow .NMPC safety rules and proper procedures during testing.
Prereauisites
- 1. All applicable preliminary tests are completed and the primary containment turned over to NMPC.
- 2. All applicable motor con"rol centers to supply electric power to control circuits and ins"rumentation are available.
- 3. Valve lineups are completed.
Test Procedure
- 1. The test verifies the primary containment integrity by pressurizing it to test pressure and conducting integrated leak rate measurements on the primary containment.
- 2. The primary containment leakage monitoring system will be used to monitor containment, pressure during the test.
Acceptance Criteria
- 1. All leak rates from penetrations, valves, and overall containment are demonstrated to be within design limits.
- 2. Test pressures and allowable leakage rates .are within limits of Table 6.2.60.
1 of 1
Nine Mile Point Unit 2 FSAR lAD45 L i ~ 4 J.4d SECONDARY CONTAiNMENT ?EAKAGE TEST Test Ob ectives To verify overall secondary containment integrity by subjecting the reactor building to a specified negative pressure and ensuring that the inleakage is within design limits.
Safet Precautions Fol3.ow all NMPC safety rules and proper procedures during testing.
Prerecruisites
- 1. All applicable preliminary tests are complete and the structures turned over to NMPC.
- 2. All applicable motor control centers to supply electric power to motors, control circu's, and ins rumentation are ava'lable.
- 3. Va3.ve lineups are complete.
- 4. Reactor building ventilation and standby gas treatment systems are available.
- 5. Reactor building airlocks are installed and can be operated to support the test.
- 6. Reactor building conduit, pipe, and other structural penetrations are sealed.
Test Procedure With the standby gas treatment system operating at a specific capacity to maintain the reactor building internal structure at a specified negative pressure the resultant inleakage will be verified.
Acceptance Criteria The reactor building leakage rate is not greater than 3,160 scfm.
1 of 1
Nine Mile Plaint Unit 2 KP".R TABLE 14.2-201 C~:":"1ICAi. P~V3 RADiGC~:"MICA'tartu Test SUT-1 es~ Al 4 t4s
- 1. Tc secure in=or .ation on the chemistry and radioc'.". mis v o= -..e reactor coolant.
To ve v ha" "he sampling ecuipment, procedures, and techn'ues are ad quate to. demonstrate that the chem s="y of =- parts o =he entire reactor system meets specificat'ons and process requirements.
Specific'bjectives of the test program include evaluation of fuel performance, evaluations of deminer~lizer 'operations by direct and indirect methods, measurements of filter perf ormance, conf i rmation of condenser integri ty, demonstra"'on of proper steam separator-dryer operation, measu emend and calibration o the off-gas system, and calibration of certain process instrgnentation. Data for these purposes are secured from a vari'ety of sources: plant operating records, regular routine coolant analysis, radiochemical measurements .of specific nuclides,. and special chemical tests.
Prereaui si tes The preoperational tests have been completed, the SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or cal'brated as appropriate.
Test Procedure Prior to fuel loading, a complete set of chemical and radiochemical samples are taken to ensure that stations are func ioning properly and to determine initial
'll sample concentrat'ns. Subsequent to fuel loading during reactor heatup and at each maj or power level change, samples a e taken and measurements are made to determine the chemical and radiochemical quality of react~ r water and reactor feedwater, amount of radiolytic gas in the steam, gaseous activities leaving the air ejectors, decay times in the off-gas lines, and performance of filters and demineralizers.
Amendment 8 1 of 2 January 3.984
Nine Mile Point Unit 2 FSAR TABLE 14.2-201 {Cont)
Calibrations are made of monitors in the stack, .liquid waste system, and liquid process lines.
The following tests are performed:
Action Test Conditions
- 1. Reactor water chemistry a. Prior to fuel and radiochemistry. loading
- 2. Gaseous and liquid b. During heatup e ffluents ac tivi ty c. Subsequent to monitor. major changes in power level Acceptance Criteria Level 1:
- 1. Chemical factors defined '.". the technical specificat'ons and fuel warranty are main"a'ned within the limits specified.
2'. The activity of gaseous and liquid effluents conforms to license lim'tations.
- 3. Water quality is known at all times and remains within the guidelines of the water quality specifications.
Level 2:
Not applicable 2 of 2
r Nine Mile Point Unit 2. FSAR TADLac Ls z 4vz
~
RADIATION MEASUREMENT Startu Test SUT-2 Test Ob ectives
- 1. To determine the background radiation levels in the plant environs prior to operation for base data on activity buildup.
- 2. To monitor radiation at selected power levels to assure the protection of personnel during plant operation.
Prereauisites The appropriate preoperat'nal tests have been completed; the SORC has reviewed and approved the test procedures and initiation of testing. Ins"rumentation has been checked or calibrated as appropria=e.
Test Procedure A survey of natural backaround radiation throughout the plant site is made p ior zo ue'oading. Subsecuent to.
fuel loading, during reactor heatup and at power levels of 25, 60, and 100 percent of razed power, gamma radiation level measurements, and where appropriate, neutron dose..rate measurements are made az specifi" locations throughout the plant. All potentially high radiation areas are surveyed.
The following tests are performed:
Action Test conditions
- 1. Background radiation a. Prior to fuel level survey. loading.
- 2. Monitor radiation level b. Fuel loading.
periodically during the c. Reactor heatup.
startup. d. Steady- state operation at 25, 60, and 100 percent of rated power.,
1 of 2
Nine Mile Point Unit 2 FSAR 1 g %p lib ~
VV Ih
&V~~4
~ 4 /
Acceptance Criteria Level 1:
The radiation doses of plant origin and the occupancy times of personnel in radiation zones are controlled consistent with the guidelines of the standards for protection against radiation outlined in 10CFR20.
Level 2:
Not applicable.
2 of 2
Nine Mile Point Unit 2 CESAR TAB[ E 14. 2-203
- -4:"L EOADiNG Startu Test SUT-3 Test Cb ective To load fuel safely and efficiently =o ='".e = ':'or size.
Pre eauisi"os Prerequisites to fuel loading are =-st=-'=-:-='". -- =- '" Section 14.2.10 and the tests acquired there' a" those prerequisites. Also, the SORC has approved fuel loading and the following additional prerequisites have been met to assure that fuel loading is performed in a safe manner:
- 1. All systems required for fuel loading have undergone preoperational testing.
- 2. Fuel and cont ol rod inspect'ns are complete. Control rods are installed and tested.
- 3. SRMs are calibrated and operable.. IRMs -and APRMs have been preoperationally tested and are operable.
- 4. SRMs are source checked with a neutron source prior to loading and periodically will be functionally checked and source checked.
- 5. The status of the reactor building is specified and established.
- 6. Reactor vessel status is specified relative to internal component placement and this placement established to make the vessel ready to receive fuel.
- 7. Reactor vessel water level is established and minimum level prescribed.
- 8. The standby liquid control system is operable.
Amendment 8 1 of 2 January 1984
Nine Mile Point Unit 2 FSAR ironic x~. c,-c.va (eront j Test Procedure
- 1. Prior to fuel loading, control rods and neutron sources and detectors are installed and tested. Fuel loading begins at the center of the core and proceeds radially to the fully loaded configuration.
- 2. Control rod functional tests and subcriticality check demonstrations are performed periodically during the loading. A shutdown margin test is performed for the fully loaded core in accordance with SUT 70-4.
The following tests are performed:
Action Test Conditions
- 1. Subcritical check a. During fuel loading
- 2. Shutdown margin b. Control rods, demonstration ( full loaded cor'e) neutron sources
- 3. Control rod functional and detectors test 'nstalled.and tested Acceptance Criteria Level 1:
The partially loaded core is subcritical by at least
- 0. 38-percent gk/k with the analytically determined highest-worth rod fully withdrawn.
level 2:
Not applicable.
2 of 2
4 ~ 0 ~ P ~
Nine Mile Point Unit 2 FSAR Lt 1 A
~ Cs Jhh IsVS 1
FULL CORE SHUTDOWN MARGIN Startu Test SUT-4 Test Ob 'ectives The purpose of this test is to demonstrate that the reactor can be made subcritical with the required margin at any point throughout the fuel cycle with the strongest worth control rod fully withdrawn and all other control rods fully inserted.
The appropriate Preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of testing.
Test Procedure This test will be performed in the fully loaded core in the xenon-free condition. The shutdown margin test will be pe formed by w'thdrawing -he control rods from the all-rods-in conf'gurat'on unt'1 to criticality will cra be pe" ity is reached. The approach ormed cautiously to prevent achieving criticality within a period shorter than 30 sec.
If the highest worth rod will not be withdrawn in sequence, other rods may be withdrawn providing the reactivity worth is equivalent. The difference between the measured K ff and the calculated Keff for the in-sequence critical will be
.applied to the calculated value to obtain the true shutdown margin.
Acce tance Criteria Level l:
The shutdown margin of the fully loaded, cold (68 F or 20 C), xenon-free core occurring at the most reactive time during the cycle must be at least 0.38 percent hk/k with the analytically strongest rod (or its reactivity equivalent) withdrawn. If the shutdown margin is measured at some time during the cycle other than the most reactive time, comp liance wi th the above cri teri on i s shown by demonstrating that the shutdown margin is 0.38 percent. 5)c+
plus an exposure-dependent increment whi ch ad j usts the shutdown margin at that time to the minimum shutdown margin.
1 of 2
Nine /file Paint Unit 2 FSAR
~ 8%%%<<%jl uoNQL<< ' 'hAAJI
<<<<w I
<<C i y
Level 2:
Criticalitv should occu I<<<<si' Mi thi n s1 Q ~<>r ent h lg/lc o f pro
& <<+pe Qe ~<<a<<
'4 te I Q,/4 c zlca V ~~
late~).
Amendment 12 2 oX'2 June 1984
0 P
Nine Nile Point Unit 2 CESAR TABIc 14.2-206 f<i+lb. 5 a 4leS p+ ~ + <ae>>
'vesaalelv4 AvlJ ~ e e ev eeao Startu Test SUT-5 Test Ob'.ec=ives
- 1. To Qemonstrate clat ~le ~ RD Vw v <<~c w vane ~v ~ ~
ove r t e
~ ~
ange of pr mary coolant \ CE caoew es " to era='."g.
ul'su Vm ..l o
'o determine t..e e ~
znitzal o ="==in> chara""er. =-- cs ueee ers ire CRD system.
eood Prere isites The appropriate preoperational tests have beer. completed.
The SORC has reviewed and approved the test procedures and initiation of testing. The CRD ,manua'on" "'ystem preoperational testing must be comple ed on C.=.D being tested. The reactor vessel, c osed 'oop '..g wate system, condensate supply system, and instrument. a' system must be operational to the extent required to conduct the test.
Test Procedure The CRD tests performed during the startup te~t .program are designed as an extension of the tests perfor;,"d during the preoperational CRD system tests. Thus, after that all CRDs operate properly when installed, they are it is verified tested periodically during heatup to assure that there is no significant binding caused by thermal expansion of the core f components. A list of all CRD tests to be performed during startup testing is as'ollows:
CONTROL ROD DRIVE SYSTEM TESTS Test Cond'ions Reactor P essure with Core t'oaded Accumulator psi g (Leg/cm~ )
Action P essure 0 600 42.2 800 56.2 Rated Position Indication Amendment 12 1 of 4 June 1984
Nine Mile Point Unit 2 FSAR rseoul' smr m r a rer o
. c-c.vo ~
( ~one f CONTROL ROD DRIVE SYSTEM TESTS Test Conditions Reactor Pressure with Core Loaded
. Accumulator psig (kg/cm~)
Action Pressure 0 600 42.2 800 56.2 Rated Normal Stroke All Times Insert/
Withdraw Coupling All***
Friction All All Scram Normal All Scram Minimum Scram Zero Scram Normal
- Refers to four CRDs selected for continuous monitoring based on slow normal accumulator pressure scram times or unusual operating characteristics, at zero reactor pressure or rated reactor pressure when this data is available. The four selected CRDs must be compatible with the rod worth minimi"er, RSCS system, and CRD sequence requirements.
+* Scram times of the four slowest CRDs (based on scram data at rated pressure) will be determined at test conditions 2, 3, and 6 during planned reactor scrams.
- +* Establish that this check is normal operating procedure.
NOTE: Single CRD scrams should be performed with the charging valve closed. (Do not ride tne charging pump nead.)
2 of 4
Nine Mile Point Unit 2 FSAR TABLE 14.2-206 (Cont)
Criteria Level 1:
a) Each CRD must have a normal withdraw speed less than or equal to 3.6 inches per second (9.14 cm/sec), indicated by a full 12-foot stroke in greater than or equal to 40 seconds.
b) The mean scram time of all operable CRDs must not exceed the following times: (Scram time is measured from the time the pilot scram valve solenoids are deenergized.)
Position Inserted from Ful'ly Withdrawn Scram Time (Seconds) 45 0.43 39 0.86 25 1.93 05 3.49 c) The mean scram time of the three fastest CRDs in a two-
,by-two array must not exceed the following times: (Scram time is measured from the time the pilot scram valve solenoids are deenergized.)
Position Inserted from Fully Withdrawn Scram Time (Seconds) 45 0.45 39 0.92 25 2.05 05 3.70 Level 2:
a) Each CRD must have a normal insert or withdraw speed of 3.0 + 0.6 ips (7.62 + 1.52 cm/sec), indicated by a full 12- ft stroke in 40 to 60 sec.
b) With respect to the CRD friction tests, variation if the psid differential pressure exceeds 15 (1.1 kg/cm~) for a continuous drive in, a settling test must be performed, in which case the differential settling pressure should not be less than 30 psid (2.1 kg/cm~) nor over should full it vary stroke.
by more than 10 psid (0.7 kg/cm~) a Amendment 12 3 of 4 June 1984
Nine Mile Point Unit 2 FSAR TABLE 14.2-206 (Cont)
THE ENFORMATIQN ON THiS PAGE HAS BEEN DELETED.
Amendment 16 4 of 4 December 1984
0 I
Nine Mile Point Unit 2 FSAR
~a we'ADuCr J f ~ 4 l Vt SOURCE RANGE MONITOR PERFORl'1ANCE AND ROD CONTROL SEQUENCE Startu Test SUT-6 Test Ob'ective To demohstrate that the operational sources, SRM instrumentation, and rod withdrawal sequences provide adequate information to achieve criticality and increase power in a safe and efficient manner.
Prereauisites The preoperational tests have been completed, and the SORC has reviewed and approved the test procedure and the initiation of testing. The CRD system must be operational.
Test Procedure The operational neu"ron sources are installed, and source range monitor count-rate data are taken during rod withdrawals to critical and compared with stated criteria on signal and signal-to-noise coun- ratio.
A withdrawal sequence has been calculated that completely specifies control rod withdrawals from all-rods-in condition to the rated power configuration. Critical rod patterns are recorded periodically as the reactor is heated to rated temperature.
The following test is performed:
Action Test Conditions Rod withdrawal a. After fuel loading.
in prescribed b. Operational neutron sequence sources installed.
- c. SRM minimum signal-to-noise count, ratio and minimum count rate criteria satisfied.
1 of 2
Nxne Mile Point Unit 2 FSAR JCLOQa k 5 o
~
m h hh 4oV I
~ IA (MUJJV)
Acce tance Criteria Level':
- 1. There is a neutron signal-to-noise count ratio of least 2 to 1 on the required operable S~s or fuel loading chambers.
- 2. Minimum count rate is in accordance with the technical specifications.
2 of 2
e Nine Mile Point Unit 2 5'SAR
'ABI E 14. 2-208 mwqiwq~t
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Startu Test SUT-8 eagre
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~ V ~ \g th reviewed and approved t.'-.e -es- procedure arc'. Ql m%J ~ 4 of testing. All system instrumentation is ins-ai'ed and calibrated. All system controls and interlocks have been checked.
Test Proces'e Rod patterns w ll be period'a y adjus"ed during piant operations to more nearly equal'ze fuel assembly exposures.
This test is perfo med as an, example of the adjustments that will be made throughout plant life and is provided to illus-trate the principies involved. The control rod sequence ad-justment begins on the 100 percent load line by reducing core ,.flowi'nd reducing thermal power to between "he low power set point of the rod worth minimizer {or the rod sequence control system) and the thermal power necessary to keep nodal powers below the precond'tioning cladding in"crim operaCing management recommendation (PCIOMR) threshold.
Also, in reducing thermal power, care should be taken to avoid exceeding the design limits of the core total peak'ng factor. The ensuing steps involve utilizing the system process ccmputer and TEP machines. The adjustment is made by withdrawing or i:nserting control rods until target is achieved.
Amendment 8 1 of 2 January 1984
Nine Mile Point Unit 2 FSAR TABLE> lt ~ 2 2vo ( Cont )
The following test is performed:
Action Test Conditions Demonstrate the rod se- a. Reduce recirculation flow.
quence adjustment pro- b. Sufficient margin availa-cedure ble to PCIOMR envelope and core operating limits.
Acce tance Criteria Level 1:
Completion of the adjustment of one rod pattern for the complementary pattern with continual satisfaction of all licensed core limits constitutes satisfaction of the requirements of this procedure.
Level 2:
All noaal powers will remain below their PCIOMR threshold limit during this test.
2 of 2
Nine Mile Poi" Unit'2 FSAR TABLE 14.2-209 INTER'::E .-.== .>>-':G MONITOR PERFORw~NCE Startu Test SUT~10
- s" Ob~ec=ir o adjust =he ..=". s,~=em to obtain an optimum overlap with
vpw9t 1 Ds
=as=a have been completed. The SORC has
- vie~ ed and a"p=";.e 'he test procedures and the initiation of testing. All SRNs and pulse preamplifiers, IRN" and voltage er a...= ~iers, a.".d APRNs have been cal'ibrated in ac-cordance with vend="'s instruction'~.
Test Procedure Initially the IRN svstem is set to maximum gain. After the APRN calibration, the IRN gains are adjusted to optimize the IRM overlap with the SRNs and APRMs.
The following tests are performed:
Action Test Conditions
- 1. Verify IRM-SRM overlap. Flux level sufficient for IRM response.
- 2. Verify IRN response to neutron flux.
- 3. Adjust IRM necessary; gain, if for proper During bration first APRM cali-based on a heat IRM-APRN overlap. balance.
Acceptance Cri "er' Level 1:
a) Each IRN channel must be on scale before the SRNs exceed their rod block setpoint.
b) Each APRM must be on scale before the IRNs exceed their rod block setpoint.
Amendment 12 1 of 2 June 1984
Nine gi)e Point Unit Z FSAR
~ALE 14.2-209 (Cont) c) The IRMs produce a scram at 120/125% scale in the startup lllode ~
aie co~
1>>m ~ 0 ~
~
c..an..e'us- he adjusted so a half-decade overlap h I%M decade'v
\pa assured.
2 of 2
Nine Mile Point Unit, 2 FSAR
'TABLE 14.2-210 LPRM CALIBRATION Startu Test SUT-11 Test Ob'ective To calibrate the IPRM system.
Prere isites The appropriate preoperational tests have been completed, the SORC has reviewed and approved the test procedures and the initiation of testing. Instrumentation for calibration has been checked and installed.
Test Procedure The LPRM channels are calibrated to make the LPRM readings propor"ional to tne neu" on 'ux in the LPRM water gap at the chamber eie':a"ion. Cabra"'on fac=ors are obtained through he use of either an c =l'..e or a process computer calculation that rela-es tne LPRM reading to average fuel assembly power at the chamber he'ght.
The following tests are pe fo med:
Action "Test Conditions
- 1. Verify LPRY. flux response. a. Hot standby or This test may be done TCI.
in conjunction with rated pressure scram testing (SUT-S).
- 2. Take data and calibrate a. TC-2 and TC-6.
LPRM system. b. All systems in NORM mode.
Nine Mile Point Unit 2 FSAR TABLE 14. 2-210 (Cont)
Acceptance Cr'teria Level 1:
Yoz applicable Level 2:
Each va'ue.
LPRN eadin= vitain 10 oercent of 's ca'culated Amendment, 8 2 of 2 January 3.984
Nine Mile Point Unit 2 ESAR TABLE 14.2-211 APRM CA :3:> ..ON Startu Tes" SUT-12 Test Object'vo T~o cal'brate he APRN system.
prerecuis "es The preoperational tests have been completed,, and the testings'nstrumenta has reviewed a.".d approved the test procedures and the initiation of ion for calibration has been checked and installed.
Test, Procedure A heat balance is generally made each shift and after each major power level charge. Each APRN channel reading is ad-justed to be cors'tent with the core thermal power as determined from the . heat balance. During heatup a preliminary .calibration is made by adjusting the APRM am- i plifier gains a soconstant tha the APRB readings agree witH the results of heatup rate heat balance. The Apts are recalibrated in the power range by a heat balance as soon as adequate feedwater indication is available.
Recalibration of the APRM system 'is in accordance with the technical specifications.
The following tests a e performed:
Action Test Conditions
- 1. Calibrate APRY. system Constant rate of heatup based on heat balance below rated prcssure.
dat.'a.
- 2. Calibrate A?RY. system Approximately 25 percent based on steady-state power at TC-2, 3, 5, heat balance data. 6 and repeated as necessary.
1 of 2
Nine Mile Point Unit 2 CESAR TABLE 14.2-211 (Cont) i v ia..~= ~ v Jie4V La ace ~~@
Level 1:
channels are calibra"ed to read equal to o" g-ea-er than the ac ual core thermal power.
2 .. Technical block are specification not exceeded.
- 3. n t.'".e startup mode, a APR!41 channels produce a .scram
'ess than or equal to 1S percent of rated t}:er..a'd Level 2:
"he above cr'ter'a are. satisfied, then the APRM channels wi11 be considered to be reading accurately if wi"".. ""e heat balance or the m'nimum value required based on they agree peaking actor, MSGR, and fraction of rated power to within
(+7, -0) percen o rated power.
Amendment. 12 2 of 2 June 1984
Nine Mile Point Unit 2 CESAR
~ I A A9 A xtiO+C J'S ~ C leJC NSSS PROCESS COMPUTER Startu Test SUT-13 Test Ob'ective To verify the performance of the NSSS process computer under plant operating conditions.
Prereauisites The preoperational tests have been completed and the SORC has reviewed and approved the test procedures and initiation of testing. Computer diagnostic test is completed. Con-struction and construction testing on each input instrument and its cabling are completed.
Test Procedure Computer system program verification and calculational pro-gram validations at sta" ic and a simu'ted dynamic input cond'ions are preoperat1onaliv tes-ed at the computer supplier's site anc following de'ivery to the plant site.
Following fuel loading, dur'nc plant heatup and the ascen-sion to rated power, the NSSS and the balance-of-plant sys-tem process variables sensed by the computer as digital or analog signals become available. Verify that the computer is receiving correct values of sensed process variables and that the results o performance calculations of the NSSS and the balance-of-plan- are correct. At steady-state power conditions the dynamic system test case is performed.
As discussed in Core Performance Tests (SUT-19), the BUCLE offline computation system will be used to evaluate core performance until the process computer performance is verified. A manual computation method is available at the site if available.
either the process computer or BUCLE is not The following tests are performed:
Action Test Conditions
- 1. Computer/TIP interface. Etems 1 and 2 do not require reactor operation.
- 2. Simulated dynamic input test.
1 of 3
Nine Mile Point Unit 2 FSAR TABLE 14.2-"12 (Con )
Action Test Conditions
- 3. Dynamic system test To be completed between case. TC-1 and TC-3.
- 4. Obtain data for trans- a ~ Reactor power greater mittal to San Jose. than 80% of rated.
- b. Core flow at 100%
of rated.
C. A full core LPRM cali-bration (OD1) must be completed immediately prior to data taking.
- d. Scheduled control rod pattern.
Acceptance Criteria Level 1:
Not applicable.
Level 2:
Programs OD-l, Pl, and OD-6 are considered operational when:
- 1. The MCPR calculated by BUCLE and the process computer either.-
- a. Are in the same fuel assembly and do not di fer in value by more than 2 percent, or
- b. For the case in which the MCPR calculated by the process computer is in a different assembly than that calculated by BUCLE, for each assembly, the MCPR and CPR calculated by the two methods agree within 2 percent.
- 2. The maximum linear heat generation rates (LHGRs) cal-culated by BUCLE and the process computer either:
a ~ Are in the same fuel assembly and do not differ in value by more than 2 percent, or
- b. For the case in which the maximum .LHGR calculated by the process computer is in a different assembly 2 of 3
Nine Wile Point Unit '2 FSAR TM!LE 14. 2-212 (Cont) than that calculated by BUC E, ==" a"h assemb y, the maximum LHC-'R and LHGR cal.culatea by the two methods agree within 2 percent.
/
T'".e;,a i.-.,'m average planar Lh~..s (: .= =~~)
~
BUCLE and the process compute" e'the a ~ Are in the same fuel assembly and do not "'"= = in value by more than 2 percent, o
- b. For "he case 'n which the NAPLHGR calculated '"y process rcmputer 's in a d'f erent assembly ":.a..
"hat calculated by BUCLE, for each assembly, the NAPLHGR and APLHGR calculated by the two methods agree within 2 percent.
- 4. The LPRN gain adjustment factors calculated by BUCLE and the process computer agree within 2 percent.
NOTE: The'emaining programs are considered operational upon successful cc...p'etion of the stat'c and dynamic. testing.
i Amendment, 12 3 of 3 June 1984
Nine Mile Point Unit 2 CESAR TASIE 14.2-213 RCIC SYST:-M Startu 'Test SUT-1C L~ 0 v=--'; =': "=="e" operation of the RCIC sys" em over
-e= "= ra-i.".g a essu e and flow rances.
- 2. o -'.,".".s""a= reliability in automa ic s" ar 'ng from reactor is at powe" conditions.
Prereauisites The appropriate preoperational tests have been completed and the SORC has o;.'e;:ed and approved the test procedure and the initiation of testing. Initial turbine operation (uncoupled), must be performed to verify sati- i:actory ope"ation and overspeed trip. The auxiliary steam system is available to sup ly "urbine steam. Instrumentation has been installed and calibrated, and suf ficient water is available to meet specified purity requirements. The following sys-tems must. be operational to the extent necessary to conduct the test: reactor vessel, suppression pool, condensate sup-ply system, and instrument air.
Test Procedure The RCIC system is designed to be tested in two ways:. flow injection into a test line leading to the condensate storage tank (CST) and flow injection directly into, the reactor vessel. The first set of CST injections consists of manual and automatic starts at 1SO psig and near rated reactor pressure. The pump discharge pressure during these tests is throttled to 100 psi above reactor pressure to simulate the largest expected pipeline pressure drop. This CST testing is done 'to demonst ate general sys" em operability and for making most controller adjustmen" s.
Reactor vessel injection .tests follow to complete the con-troller adjustments and to demonstrate automatic starting from a cold (ambient temperature for RCIC operatior ) standby condition. Cold is defined as a minimum 72 hrs without any kind of RCIC operation.
Amendment 12 1 of 4 June 1984
Nine Mile Point Unit 2 FSAR
'P5c3t '2 ld, ~~')1 3 (Coat )
After all final con="ol'er and sys= m acijustaents have be determined, a defined set of demonstration tests must be performed with that one
~ a set of
~
adjustments. Two'onsecutive d ~~ons~~-~~
ons of- CST
~ ~$ . e'7. ~~ 'D ' ~ ~
' ':z i..jections a"e cor. to p"ovid a " .c;..ar< c-
~
'et ac compa son with future =u"'e a."."e tests.
After the auto..'start "o"-ion o= ce"tain of the above tests is cc...deleted, and wh 'e =.".o s istem '- sti o=e"a='rg, ~sma ~
step dis"urbances '.-. speed r.d = ow co.-.~a.".= a=e:nput ~
manual and automatic mode respectively) to demonstrate satisfactory stability. This .is done at .both low (above minimum turbine speed) and. near rated flow initial con-ditions to span the RCIC operating range.
A demonstration of expanded operat'cn of up to 2 hr (or un-til pump and turbine oil tempe"atu"e are stabilized) of con-tinuous running a- ra-ed =lo's sc'.".e 'uled at a conven'ent time during the test program.
Differential pressures measured during rated steam flow will be used to establish appropriate high steam flow setpoints.
The following tests are performed:
Action Test Conditions
- 1. CST injection first, a ~ For all RCIC testing; phase manual start. recirculation in POS mode and all other controllers in NORM mode.
Demonstration prior to controller adjustments at 150 psig reactor pressure.
Rated reactor'pressure RCIC discharge 100 psi above RPV.
- 2. CST inj ection, step Immediately after lc with changes in flow for RCIC discharge to condensate controller storage tank. Manual and adjustments. automatic control modes.
Amendment 12 2 of 4 June 3.984
Nine Mile Point unit 2 CESAR TABLE. 14.2-213,(Cont)
Zest
- 3. CST injection, ex- In conjunc;cion with 2.
tended operation
- 4. ac- 'wgswuw+ I 1
RC:C a'cha ge 100 s-art s"a-bi'tyfollowed ae-...cnstr by
'... above RPV..
a1 scna ps'ce RC ' 00 pqi
='"ov '- ~V
- 5. Reactor vessel injec- Rated reactor pressure, tion, manual s tar t, manual and automatic modes.
'tep changes for con-troller adj us m'ents.
Reactor vessel inj ec'- Ra~ed reactor pr ssure, "ion hot cui "k automat c ...Qae, start.
- 7. React'.or vessel inj ec- 150 psig tion, hot or cold reactor'ressure, manual and quick start followed automat'c modes by stability demon-stration.
- 8. Confirmatory reactor Ra" d. reactor pressure, vessel injection, final RCIC controller cold quick start. settings.
- 9. Second consecutive Same as 8.
confirmatory reactor vessel inj ection, cold quick start.
- 10. Condensate storage a. Rated reactor p es-tank injection for sure, final control'"
surveillance test settings, RCIC dis-base data, cold ch'arge approximately quick start. '100 psi above RPV.
150 psig reactor pres-sure, final controller settings, RCIC dis-charge approximately 100 psi above RPV.
Amendment 12 3 of 4 June 1984
~ 8 Nine Nile iPoint Unit 2 WAR
~pat 1 4 '7<<21 3 (t o~+ i
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Se <<Atlh v<< ~ Q~ ~ <<e <<1 P'o<<4 iation at a.-.y <<2actcr o es
- \ <<IQ ~ ~ DOtl a 0%0 a- Q th
~ ~
4+4 +Vent aov i c <<laa u a If any Level 1 cr'eria are not met, -.'". reactor ' only al-lo d to operate up to a restricted power level defined
- 14. 2-215-1 until thebY'igure pro em esolved. Also, consult the Pl nt Technical Specifications for actions to be taken E,eve 2:
In order -o provide an overspeed and 'olat'on t"ip avoidance margin, the transient start firs- and sub-sequent speed peaks must, not exceed 5 percent above the rated- RCIC turbine speed.
- 2. The speed and flow control loops are adjusted so the decaY ratio of any RCIC system-related variable not greater than 0.25.
- 3. The .turbine gland seal condenser system is. capable preventing steam leakage to the atmosphere The -' switch f'r the RCIC s-earn supply I'>> high fl isolation trip is calibrated to actuate at 3pp percent of the maximum required steady-state flow.
4 of 4
Nine Mile Point Unit 2 FSAR TQPTL'4 2 Sit FACT" D PROCESS TZ i:"RA'v~=S Startu Test, SUT-16A s- Ci ~ ective he purposes of this test are:
o ensure %4 ~ ~
temperatu e correspoa ds to bctYAm ':ad coo temperat Aoovi nc ..aa o ~a~s cL ~s vaas
~we ~
- 2. To identi y any rea-tor opera=ing modes that cause temperature stratification.
- 3. To determine the proper sett'ng of the low low control limiter fo'r the recirculation pumps to avoid coolant temperature stratification in the reac"or pressure vesse'ot om head region.
- 4. To f ami liarize plant personnel with tempera ure differential lim'itations of the reactor system.
Prereauisites The preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of testing. System and test instrumentation have been calibrated.
Test Procedure The adequacy of bottom drain line temperature sensors will be determined by comparison with recirculation loop coolant temperature when core flow is 100 percent of rated.
During initial heatup while at hot standby cond'ions, the bottom drain line temperature, recirculation loop suction temperature, and applicable reactor para.-..eters are monitored as the recirculation flow is slowly lowered to either minimum stable'low or the low rec'rculation pump speed minimum valve position, whichever is the greater. The effects of cleanup flow on vessel temperatu e stratificat'on will be investigated as operational limits allow. Utilizing this data, it can be determined whethe" coolant temperature stratification occurs when the recirculation pumps are on and, if so, what minimum recirculation flow will prevent it.
Amendment, 12 1 of 2 June 1984
Nine Mile Point Unit 2 FSAR TABLE 14.2-2' { ant)
Monitoring the preceding information during planned pump tri'ps will determine if temperature stratification occurs in the idle recirculation loops or in the lower plenum when one or more loops are inactive.
All data will be analyzed to determine ope ating procedures are required.
if changes in The following test is performed:
Action Test Conditions Monitor vessel 1. During heatup.
temperatures.
- 2. At 100 percent. core flow (TC-3).
- 3. After recirculation pump trips (natural circulation).
Ac'centance Criteria.
Level 1:
Tne reactor rec'rculation pumps shall not be started, flow increased, nor power increased unless the coolant temperatures between the steam dome and bottom head drain are within 145 F.
- 2. The recirculation pump in an idle loop must not be started, active loop flow must not be raised, and power must not be increased unless tne idle loop suction temperature is within 50 E'f the active loop suction temperature and the active loop flow rate is less tnan or equal to 50 percent of rated loop flow. If two pumps are idle, the loop suction temperature must be within 50 F of the steam dome temperature before pump startup.
Level 2:
During two-pump operation at rated core flow, the bottom head coolant temperature as measured by the bottom drain line thermocouple is within 30 F of the recirculation loop temperature.
2 of 2
Nine Mile Point, Unit 2 FSAR TABLE 14. 2-215 WATER- LEVEL R"F"RENCE LEG TEMPERATURE Startu Test SUT-16B Test Ob'ective To measure the reference leg temperature and recalibrate the instruments if the measured temperature is different from the value assumed during the initial calibration.
Prere isites The preoperational tests have been completed, the SORC has reviewed and approved, the test procedures and initiation of testing. System and test instrumentation have been calibrated.
Test Procedures To monitor the reactor vessel wate leve, 'ive level I instrument systems are pro'ided. These sys:ems and their functions are:
- 1. Shutdown range water level measurement in cold, shutdown cond'tion.
- 2. Narrow range - feedwater low and water level control functions.
'3. Wide range - safety functions.
- 4. Fuel range - post accident indication.
S. Upset range - water level measurement during transient conditions.
The test, is done at rated temperature and pressure and under steady-state conditions and verifies tha the reference leg temperature of the ins"rument is the value assumed during initial calibration. If not, the instruments are recalibrated using tne measured value.
Action Test Conditions Monitor drywell Hot standby with steady temperature. drywell temperatures.
1 of 2
0 Nine Mile Point Unit 2.FSAR a '~ ~ter1a Bevel 1:
4
'7 eve
.he di c=e~e~c etween the actual re= ence "empera iu re(s) and tne value(s) assured dur'g '..iti 1 cal-'rati cn shall he ess than -n~ ~-...o~n "...". w .
e~
in a sca 'end point error of 1 . e cen o the i-.s ume..t span for each range.
Amendment 12 2 of 2 June 1984
~ ~ ~ ~ ~ 04- ~ a Nine Mile Point Unit 2 FSAR TABM 14.2-216 SYSTEM EXPANSION Startu Test SUT-17 Test Ob ectives To demonstrate that:
The piping system during system heatup and cooldown is free to expand and move without unplanned obstruction or restraint.
- 2. The piping does shake down after a few thermal expansion cycles.
- 3. The measured values of displacement are within the limits specified by the responsible piping design engineer.
Prere isites The aPProPriate preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of testing.
Test Procedure Hanger positions of reactor recirculation piping are recorded after each major thermal cycle until a shakedown has. taken place (normally about three cycles). During initial heatup, a visual inspection is made at an intermediate reactor water temperature to ensure that components are free to move as designed. Corrections are made as necessary. Devices for con-tinuously measuring pipe displacement are mounted on the recirculation lines, and motion during heatup is compared with calculated values. Final sensor locations are determined at the site and based on generic recommenda-tions. After receipt of the installed transducer locations, the plant piping design subsection will supply to the startup engineer the expected thermal displacements (Level 2 limits) and the allowable thermal displace-ments (Level 1 limits) for the above piping and related conditions. These displacements will be specific to each transducer for each coordinate direction.
1 of 2
0 Nine Mile Point Unit 2 FSAR TABLE ii.2-216 j Cont)
Action Test Conditions
- 1. Visual inspection and a. All control systems in hanger readings. NORM mode.
- b. Approximately 2SO F at accessible locations.
C. At ambient and rated temperature.
- d. After 3 to 5 complete heatup and cooldown cycles.
- 2. Record displacement a ~ At approximately 250'F.
sensor readings. b. At rated recirculation temperature.
C ~ At rated feedwater temperature.
AcceD anc Cz 'eri a (As described in response to question F210.37) .
Level i:
There shall be no obstructions which will interfere with the thermal expansion of the recirculation piping system.
The displacements at the established transducer locations shall not exceed the allowable values as provided later by the plant piping design subsection.
The allowable values of displacement shall be based on not, exceeding ASME Section III Code stress allowables.
Level 2:
The displacements at the established transducer locations shall not exceed the expected values as provided later by plant piping design subsection.
2 of 2
Nine Mile Point Unit 2 PSAR TABLE 14.2-217 TRAVERSING INCORE PROBE UNCERTAINTY CALCULATIONS Startu Test SUT-18 Test Ob ective To determine the reproduceb'ity of the TIP system readings.
Prereauisites System installation has been completed and preoperational tests completed and verified. The SORC has reviewed and approved the test procedure and initiation of testing. The TIP detector ball valve time delay, core top and bottom limits, clutch, x-y recorder, and purge system are operational. Instrumentation has been calibrated and 'nstalled.
Test Procedure TIP reproduc'bi ty consists of a random noise componen and a geometric component. The geometric component is due to a variation in the -wate gap geometry and TIP tube orientation from TIP location to location. Measurement of these components is obtained by taking repetitive TIP readings at a single TIP location, and by analyzing pairs of .. TIP readings taken at TIP loca ions that are symmetrical about the core diagonal of fuel loading symmetry.
TIP data is taken at TC-3 and again at near rated power. ]
The TIP data are taken with the reactor operating with an oc ant symmetric rod patte n and at steady-state conditions.
The total TIP reproducibility is obtained by dividing the standard deviation of the symmetric TIP pair nodal ratios by g2. The nodal TIP ratio is defined as the nodal BASE value of the TIP in the lower right half of the core div'ded by its symmet ic counterpart in the upper left half. The total TIP reproducibility value that is compared with the test criterion is the average value of the data sets taken.
The random noise uncertainty is obtained from successive TIP runs made at the common hole, with each of the TIP machines making six runs. The standard deviation of the random noise is de ived by taking the square root of the average of the 1 of 2
Nine Nilee Point Unit. 2 CESAR TABLE 14.2-217 (Cont) variances ac nodal levels 5 through 22, she e ".e .". dal variance is obtained from the fractional deviations 'of the successive TIP values about their nodal mean value.
he gecmet ic compone..t of TIP reproducibility is obtained bv statis-ically subtracting the random noise component ~rom "4e total TIP reproducibility.
The ollowing test is performed:
Test Condi ti ons TIP overall uncertainty. a. Octant symmetric control rod pattern.
- b. At steady state.
- c. TC-3 and 6.
Acceatance Criteria Level 1:
Not applicable.
Level 2; The total TIp uncertainty (including random noise and geometrical uncertainties) obtained by averaging the uncertainties for all da'ta sets shall be'ess than 6.0 percent.
Amendment, 12 2 of 2 June 1984
Nine Mile Point Unit 2 FSAR l454C 1'i C 8 JO CORE PERFORMANCE Startu Test SUT-19 Test Ob 'ectives
- 1. To evaluate the core thermal power and flow.
- 2. To evaluate whether the following core performance parameters are within limits:
- a. MLHGR ~
- b. MCPR.
- c. MAPLHGR.
Prerecuisites The preoperat'ona'es=s have been completed and the SORC has reviewed anc approved the "est procedure and 'n'tiation of testing. Svstem ins=rumen-a=ion has been installed and calibrated and test instrumentation calibrated.
Test Procedure Core performance evaluation is employed to determine the principal thermal and hydraulic parameters associated with core behavior. These parameters are:
- 1. Core flow rate.
- 2. Core thermal power level.
- 3. MLHGR.
- 4. MAPLHGR.
- 5. MCPR.
These core performance parameters are evaluated by manual calculation techniaues or may be obtained from the process computer. If. the process computer is used as a primary means to obtain these parameters, it must be proven that it agrees with BUCLE within 2 percent on all thermal parameters
{SUT-13). I 1 of 2
I~ ~
0
Nine Mile Point Unit 2 FSAR TABLE 14. -2 la {Cont)
If neither BUCLE nor the process computer is available the manual calculation techniques can be used for the core performance evaluation.
'he following test is performed:
Action Test Conditions Evaluate core thermal power a. TC 1, 2, 3, 4, 5, flow and compute the thermal and 6 are necessary and hydraulic parameter for documentation.
associated with core behavior. b. Additional points Use plant process computer, as necessary to as-offline computer system, or sure compliance with manu a 1 c al cul at i ons technical specifica-tions.
Acceptance Criteria Level 1:
- 1. The MLHGR of anv rod c ring steady-s"ate condit'ns does not exceed the 'imit spec'ied by the plant technical specifications.
- 2. The steady-state MCPR does not exceed the limits specified by the technical specifications.
- 3. The MAPLHGR does not exceed the limits specified by the technical specifications.
- 4. Steady-state reactor power is limited to rated core thermal power and values on or below the rated power flow control line. Core flow does not exceed its rated value.
Level 2:
Not applicable.
2 of 2
Nine Male Porno Unzt 2 CESAR TABLZ 14.2-219
- -RODU TEON Startu Test SUT-20 To cemo lstraYe NSSS provides steam su icient to es Procedure Warranty demonstration consists of recording sufficient data unde s eady-state con"" ".c.".s to determine "he reactor power level the pressu=e =-."." = .- ' tv of the steam, and t..e steam f'ow ate from the reac"cr.
These measurements include the tempe,'rature, pressure, and flow rate of feedwate ente ing the reactor, the energy added to the reac or water by the rec'cu'a -'on r-ve pumps, the flow rate through and temperature entering and leaving the reactor cleanup system, the flow rate and temperature of the CRD cooling water, the carryover of reactor water into the steam lines, and the steam pressure outside the drywell near the MSIVs.
Each set of measurements is taken at frequent intervals, every 5 or 10 min as appropriate, for a total test run duration of 4 hr. The average measured quantity, suitably corrected for all'calibration factors, is used to determine the NSSS output during the test run. Where the contract requires a 100-h demonstrat'on, two test runs are made, one in the first 50 hr and one in the second 50 hr. The demonst ated outpu" 's the average of the values f om the two test runs. Dur'ng the balance of the 100-hr demonstration, the NSSS output is held constant within
+5 percent of the nominal steam flow rate as ind'cated by the installed plant feedwater instrumentation.
Should the 100-hr warranty run be interrupted once for any reason and a subsequent time for any reason not due to the fault of the customer, subject to the provisions of the Amendment 8 1 of 2 January 1984
Nine Ni3.e Point Unit 2 CESAR TABLE 14.2-219 (Cont) contract, it will be repeated. If the test is interrupted a second or subsequent time for any reason due to the fault of the customer or the power grid to which the station is connected, it will be resumed upon coming to full power and continued until the desired test period is accumulated, provided that the minimum continuous period full-power operation has been 24 hr.
The following test is performed:
Action Test Conditions Demonstrate steam quality a. At conditions prescribed and flow under steady in the nuclear steam sys-conditions. tem warranty (TC-6).
- b. Operate continuously for 100 hr.
Acceptance C iter-'a Level 1:
- 1. The NSSS paramete s as determined by using no mal operating procedu es are within th'e appropriate license restrictions.
The NSSS is capable of supplying steam in an amount and 1
2.
quality corresponding to the final feedwater temperature and other conditions, shown on the rated steam output curve in the NSSS technical description. The razed steam output curve provides the warrantable reactor vessel steam output as a function of feedwater temperature, as well as warrantable steam conditions at the outboard MSIVs. Thermodynamic parameters are consistent with the 1967 ASME steam tables. Correction techniques for conditions that differ from the contracted conditions will be mutually agreed to prior to the performance of the test.
Ievel 2:
Not applicable.
2 of 2
Nine Mile Point Unit 2 FSAR iABLE 14.2-220 CORE POWER-VOID NODE Startu Test SUT-21 Test Ob ective To measure the stability of the core power-void dynamic response and to demonstrate that its behavior is within specified limits ~
P re r equi si te s The appropriate preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of testing. System and test instrumentation have been installed and calibrated.
Test Procedure Tne core powex-void loop mode that results rom a com-dvnamics is leas stable near ¹ bznaiion o= the neutron kineiics anc core thermal-hydraulic natural c'rcula-ion end of the rated 100-percen" power zod line. A fast change in ivity balance is obtained by a pressuxe regulator step the'eac change (see Test 22) and by moving a very high worth rod one or two notches. Both local flux and total core response will be evaluated by monitoring selected LPRNs during the transients.
The following test is per ormed:
Action Test Conditions
- 1. Move hi gh wo rth a. TC-4'natural circulation.
control rod 1 to b. Low power region of TC-S 2 notches. with recirculation flow control valve at minimum valve position.
- c. Low power region of TC-5 with LFMG power and mini-mum valve position.
- d. High power region of TC-S.
- 2. In conjunction with a. TC-4 and TC-S.
pressure regular step changes (Test 22).
1 of 2
Nine Mil.e Point Unit 2 FSAR TABLE 14.2-220 (Cont) calli 4 4 y,~1 c1 level 1:
AV V ~ rS V VaV ~
~ ~ V ~ I~ V a A
S C .
i ~
Level 2:
Sys e.-. C 1 I s ma I gontp~n os'. 11 ot A Vi1 yraAA
~ 1 ~
Ci C v+5&A hs 8 ~
CA D g Qrhp Aer2v V Vk 4 A
CVi i AV ~iaOAve O- response must Be less \h vsea Q as ov 0."-C.
~ ~
Amendment. 12 2 of 2 June 1984
Nine Mile Point Unit 2 FSAR TABLE 14.2-221 PRESSURE REGULATOR S tartu Test SUT-22 Test Ob ectives
- 1. To determine the optimum settings for the pressure control loop by analysis of the transients induced in the reactor pressure control system by means of the pressure regulators.
- 2. To demonstrate the takeover capability of the backup pressure regulator upon failure of the controlling pressure regulator and to set spacing between the set points at an appropriate value.
- 3. To demonstrate smooth pressure control transition between the control valves and bypass valves'hen reactor steam generation exceeds steam used -by the turbine.
- 4. To 'demonstrate that other affected parameters are within acceptable limits during pressure-regulator-induced transient maneuvers.
Prere isites The preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of testing. instrumentation has been checked or calibrated as appropriate.
Test Procedure The pressure set point is decreased rapidly and then increased rapidly by about 10 psi, and the response of the system is measured in each case.
accomplish the set point change in less lt is desirable "o
.".an 1 sec. At specified test conditions the 'oad 'mit set point 's set so that the transient is handled by control valves, bypass valves, or both. The backup regulator is tested by simulating a failure of the operating pressure regulator so that the backup regulator takes over control. The response of the system is measured and evaluated, and regulator settings are optimized. At certain conditions the test results will be included with the test report in Core Amendment 12 1 of 3 June 1984
1" Nine Mile Point Unit 2 FSAR TABLE 14.2-221 (Cont)
Power - Void Mode Response (Test 21) . This testing yields valuable core stability data in the midfrequency range (i.e., 0.1 to 3.0 Hz).
The following test is performed:
Action Test Condi tion Operating Mode ~In ut 5 6 CV Set point No Yes Yes Yes Yes Yes CV Fail to backup No Yes Yes Yes Yes Yes BPV Set point Yes Yes No Yes Yes Yes BPV Fail to backup Yes Yes No Yes No Yes Recirculation modes* MAN MAN MAN MAN MAN MAN Acceptance Criteria Level The transient response of any pressure control system-related variable to any test input must not diverge.
Level 2:
- 1. Pressure control system-related variables may contain oscillatory modes of response. In these cases, the
~
decay ratio for each controlled mode of response must be less than or equal to 0.25. (This criterion does not apply o tests involving simulated failure of one regulator with the backup regulator taking over.)
- 2. The pressure response time from initiation of pressure se po't cna..ge to the turbine inlet pressure peak i s 510 sec.
- 3. Pressure control system deadband, delay, etc, is small enough that steady-state limit cycles (if any) produce steam flow variations no larger than +0.5 percent o=
ra ed .steam flow.
- Either POS or FLO Amendment 12 2 of 3 June 19S4
0 Nine Mile Point Unit 2 FSAR
'ZA~LF 14.2-221 .(Cont)
- 2. The pressure response time from initiation of pressure set point change to the turbine inlet pressure peak is 510 sec.
- 3. Pressure control system deadband, delay, etc, is small enough that steady-state limit cycles (if any) produce steam flow variations no larger than +0.5 percent of rated steam flow.
- 4. For all pressure regulator transients the peak neutron flux and/or peak vessel pressure shall remain below the scram settings by 7.5 percent and 10 psi, respectively.
(Maintain a plot of power versus the peak variable values along the 100-percent rod line.)
- 5. The variation in incremental regulation (ratio of the maximum to the minimum value of the quanti ty, "incremental change in pressure control signal/incremental change in steam flow," for each flow range) shall meet the following:
Stean: Flow Obtained With Valves Wide Open Percent Varia ion 0 to 85 54.1 85 to 97 52:1 85 to 99 55.1 3 of 3
Nine Mile Point Unit 2 FSAR TABLE 14.2-223 LOSS OF FEEDWATER HEATING Startu Test SUT-23B Test Ob'ective To demonstrate adequate response to a feedwater temperature loss.
Prere isites The appropriate preoperational tests have been completed; the SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.
Test Procedure The condensate/feedwater system is studied to determine the single failure'hat causes the largest loss in feedwater heating. This event is then performed at between 80- and 90-percent power with the recirculation flow near its rated value.
The following test is performed:
Action Test Condition Single event that causes During TC-6 reduce power to largest decrease in feed- between about 80- and 90-per-water temprature. cent thermal power, and near 100-percent core flow.
Acce tance Criteria Level 1:
- 1. For the feedwater heater loss test, the maximum feedwater temperature, decrease due to a single-failure case must be 5100 F. The resultant MCPR must be greater than the fuel thermal safety limit.
- 2. The increase in simulated heat flux does not exceed the predicted Level 2 value by more than 2 percent. The predicted value is based on the actual test values of feedwater temperature change and initial power level.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-223 (Cont)
Level 2:
The increase in simulated heat flux does not exceed the predicted value referenced to the actual feedwater temperature change and initial power level.
2 of 2
Nine Mile Point Unit 2 FSAR TABLE l4.2-224 FEEDWATER PUMP TRIP Startu Test SUT-23C Test Ob ective To demonstrate the capability of the automatic co e flow runback feature to prevent low water level scram following the trip of one feedwater pump.
Prere i sites The preope ational tests have been completed and the SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.
Test Procedure One of the two operatinc feedwater pumps is tr'ped and the automatic rec'culation runba k circuit acts to drop the power to within the capacity of the rema'ning feedwater pump. P ior to the tes , a simulat'on of the feedwater pump trip is done to ver-'fy the runback capability of the recirculation system.
The recirculation unback is in'tiated by the pump trip detection ecruipment and the low water level signal.
The ollowing test is performed:
1 of 2
Nine Mile Point Unit 2 F~~R TABLE 14.2-224 (Cont) c Test Condi ions Trip feedwater pump to a. TC6
<<pm'r u ja>> b ~~
~g 1 sy -=ms ' %%@
a.QX'i moce .
~s~c CoC art
~0 Cl ~
(::-. i!=-;:='..:., Feedwate Runou= Ca-abilitv test, vt ~ i S 0 ~
~ Vk % ~ JN
- ~s", SLT-30D, Cvl' Acceptance Criteria Level 1:
Not, appl'ca-le.
Level 2:,
The reactor shall avond. low-water-level scram by a 3-in margin from an initial water level halfway between the high and low level alarm setpoints.
Amendment 12 2 of 2 June 1984
0 Nine Mile Point Unit 2 FSAR TABLE 14.2-244 (Cont)
- 3. The time to place the RHR heat exchangers in the steam condensing mode with the RCIC using the heat exchanger condensate flow for suction must be 1/2 hr or less.
NOTE: If decay heat is not sufficient to demonstrate shutdown cooling mode heat rejection capacity, then heat exchanger capacity may be inferred from data taken in the suppression pool cooling mode, provided that the data were taken with the system as close as possible to the process diagram flows and temperatures.
3 of 3
Nine Mile Point Unit 2'FSAR TABLE 14.2-225 YM '~":-:":- "";.TER R.PCOU CAPAB ':Y
>ta tuv 'st SLJ 23D Test Objective o determ'ne that t.".e ...ax'mum feedwater runout capability '
=o.bat'b'e " -'". '-'"~"s'"= assump 'ions and to ca ibrate "he eedwater low.
acu~ s es
'P'4 e. cope a-ional tests have been completed; a-broved the tes procedures a;.d a .o. o s==.-.g. lns" umentation has been checked or calibrated as abprop 1 ate .
Tes= P ocedure The test is d'vided into two parts: . 1) the initial ca'ibration o "'.".e s-eed control'ers and 2) verificat'on o" calibration by .-.. as"red da a, wh'ch includes a verificat'o.".
tha the maximum eedwate flovs do not exceed the flows (different flows at different vessel pressures) i..
Section 10.4.7.2
- 1. The speed controller calibration is done hy obtaining vendor pump performance curves.
fi The pump st performance curves are then used to determine the turbine speed corresponding to the maximum allovab' flow at rated vessel pressure specified by the CESAR and the minimum speed which corresponds to 0 percent flow at 865 psia. Additionally, for good level control sys" em performance, 115 percent it is desirable to be able to reach NBR flow at 1/075 psia and 68 percent NBR flow at 1,025 psia in the one-pump-tripped condition.
Adjustable eauipment (i.e., feed pump turbine speed cont ol loops, mechanical 1'miters, feedvater con o sys"em func on generators, etc) are set. to prevent he feedwater pumps from exceeding their maximum alloved output, and yet allow the desirable performance.
2..During the data collection and verification o f calibration portion of the test, pressure, flew, and controller data will be collected between 60 and 00 percen" power. Measured data vill be comparec against expected values to ensure proper calibration.
The measured maximum flow will be adjusted to the 2'SAR Amendment 16 1 of 3 December 1984
~ 5 Nine Nile Point Unit 2 FSAR TAoLi 14.2-225 {Cont)
The measured maximum flow will be adjusted to the FSAR pressures using the measured data. The maximum flows stated in the FSAR are used as licensing assumptions; therefore, the FSAR maximum flows should not be exceeded. If, however, the FSAR maximum flows are exceeded, there exists two options. The system can be adjusted so that the licensing assumption is not exceeded, or an additional penalty can - be applied to the CPR. This penalty will be calculated by the appropriate engineering component, and operating limits modified, where necessary.
Action Test Conditions
suction, discharge and This can be done at reactor pressures, feed- TC-3 or any high-water flow rate, flow power point achieved control valve positions, prior to commercial and actual locations of operation.
valve position limiting b. All systems in NORM stops. mode.
- c. Naximum number of con-densate and feedwater
.pumps normally operated at 100 percent power shall be running.
- 2. Determine sensitivity of a. Reactor power between feedwater flow to reactor 80 and 90 percent rated.
pressure over a 30-psi b. All systems in NORM range in 5-psi increments. mode.
- c. Maximum number of con-densate and feedwater pumps normally operated at 100 percent power shall be running.
Acceptance Criteria Level 1:
Maximum valve position attained shall xaot exceed the position which will give the following flows with the normal complement of pumps operating.
2 of 3
0 ~ ~
Nine Mile Point, Unit 2 FSAR TABLE 14.2-225 {Cont) aM e >~i v ~4 cs <<i 0 Sk Level 1:
speed a="a .".ed s.".a '..ot ex=ee" the sp ecs
"'e the following flows with the normal complemen" o=
= s'pera"ina.
pe cen HBR a P ps'.
percent + A(P-P rate'd)j percent N3R at P ated p$ 1a ~
- =.e maximum flow, F, the pressure, P, and the slope of the flow variation with pressure, A, should be specified in the Ef any q" estions rema'n, contact NSSS Transient Ana'sis Engineering.
Level 2:
The eedwater flow runou" capability must not exceed the assumed value in Section 10.4.7.2.
- 2. With the flow control valve position limiters set, the feedwater system should Will meet the fol'owing controllability requirements:
a ~ 115 percent NBR transient flow capacity a" 1,075 psia vessel pressure with the normal pumping configuration.
~ b. 68 percent NBR flow. capacity at 1,025 psia vessel pressure with no feed pump tripped.
Amendmen- 16 3 of 3 December 1984
Nine Mile Point Unit 2 FSAR TABLE 14.2-226 TURBINE VALVE SURVEILLANCE Startu Test SUT-24 Test Ob'ective To demonstrate the acceptable procedures and maximum power levels for surveillance testing of the main turbine control, stop, and bypass valves without producing a reactor scram.
Prere isites The appropriate preoperational tests have been completed; the SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.
Test Procedure Individual main "urb'ne control, stop, and bypass valves a e tested rou 'e y during plant ope"ation turbine surve'l ance r, s-ing.
as equi red fo A" seve al tes- points the response of the reactor is observed, and although required, l is recommended tha" the maximum possible power it is no level for performance of these tests along the 100-percent load line be established. First actuation should be between 45 and 65 percent power, and used to extrapolate to the next test point between 75 and 90 percen power and ultimately to the maximum power test condit'on with ample margin to scram. Note the proximity to APRM flow bias scram point and preconditioning cladding interim operating management recommendation (PCIOMR) envelope. The turbine valves are tested 'manually and reset. The rate of valve stroking and timing of the close-open sequence are such tha" the minimum practical disturbance is introduced and that PCIOMR limits are not exceeded.
The following tests are performed:
Action Tes" Conditions
- 1. Individually close a. Between 45 and 65 percent turbine stop valves. power,. and again between 75 and 90 percent power, per-form third test at chosen maximum power level for all subsequent surveillance 1 of 2
Nine Mile'Point Unit 2 FSAR TABLE 14.2-226 (Cont) c ion Aa&4 4 1 A&2 ee 2 tests along the 100 percent (non cuilibrium
~ AA t%
- b. ~1od of eci culati on s rstem to a dete ~illned by test '
(to minimize flux peak it ecommended that :<<LX mode u-zed); all others in be
.'JCK i mode.
an~ v-~~-
turbine con-rol
vs same po"er optimization pro-3-s<ep valves. cedure as in the above stop valve test
- 3. Individually open Verify that special turbine bypass considerations are not salves. nec ssary by testing at maximum power determined in la and 2 above.
Acce tance Criteria Level 1:
Not appllaabla.
Level 2:
- 1. Peak - neutron flux is at least 7.5 percent below the scram trip setting. Peak vessel pressure remains at least 10 psi below the high-pressure scram setting.
Peak heat flux must remain at least 5 percent below its scram trip point.
- 2. Peak steam flow in each line remains 10 pe cent be'ow the high flow isolation trip setting.
Amendment 12 2 of 2 June 1984
Nine Mile Point Unit 2 FSAR TAB E 14.2-2"7 MAIN STEAM ISOLATION VALVES FUNCTIONAL TESTS Startu Test SUT-25A Test Ob ectives
- 1. To - functionally check the MSIVs for proper operation at selected power levels.
- 2. To determine isolation valve closure time at rated conditions.
- 3. To determine maximum power at which a single valve closure can be made without scram.
Prere i sites The preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of tes ing. Ins"rumentation has been checked or calibrated as appropriate.
Test Procedure At 5 percent and greater power levels, individual fast closure of each MSIV will be performed to verify their functional performance and to determine closure times. The times to be determined are a) the time from deenergizing the solenoids until the valve stroke from open to closed is complete (tsol), and b) the valve stroke time (ts ). Time ts equals the interval from when the valve starts to move from full open until it. 0- is 100 percent closed {valve stroke complete, i. e., from to 90-degree positions) to determine the maximum power level at which full individual closures can be performed without a scram, first actuation will be performed between 40 percent and 55 percent power, and used to extrapolate to the next, test point between 60- and 85-degree power, and ultimately to the maximum power test condition with ample margin to scram.
1 of 3
Nine Mile Point Unit 2 FSAR TABLE l4. 2-227 ( Cont )
The following tests are performed:
Action Test Conditions
- l. Individually close each a. Heatup and between TC-1 MSIV, fast mode. and 3, close each MSIV to measure valve timing only.
- b. Recirculation system in POS mode; other systems in NORM mode.
- 2. Close fastest MSIV, a. Close one valve fast mode. between 40 and 55 per-cent power (TC-2 or 3) and'gain between 60 and 85 percent power (TC-3 or 5). Perform third test at chosen maximum power condi-tion for all subse-auent surveillance tests.
- b. Recirculation system in POS mode at TC-2 and 3 and FLX mode at, TC-5.
Other systems in NORM mode.
Acce tance Criteria Level 1:
The MSIV stroke time (ts) shall be no faster than 3.0 seconds (average of the fastest valve in each steam line), and for any individual valve 2.5 seconds its s5 seconds. Total effective closure time for any individual MSIV shall be tsol plus the maximum instrumentation delay time as determined in preoperational test GE-4 and shall be 55.5 seconds.
2'of 3
Nine Mile Point Unit 2 FSAR TABLE 14."-22 (u'Qnt)
Level 2:
- 1. The reactor shall not scram. The peak neutron flux must be at least 7.5 percent below the trip setting. The
'peak vessel'ressure must remain at least 10 percent psi below the high-pressure scam setting. The peak simulated heat flux must be 5 percent less than its trip point.
- 2. The reactor shall not isolate. The peak steam flow on each line must, remain 10 percent below the high steam flow isolation trip setting.
3 of 3
0
.',~ne Mile Point Unit 2 FSAR
~ASLZ 14. 2-228 FULL R:"ACTOR I SOrMT I ON To from P e d" zmne ".".
the s'ultaneous eauisites
'l'losure "ac o trans ' st 0 of all a v MS o
IVs.
The p eoperationa' s"s nave been co...pl ed; t..e QRC has r'eviewed and approved the test procedures and initiation of testing. Instrumentation .has been checked or calibrated as appropriate.'est Procedure A test of the simultaneous full closure of all NSIVs is performed at 295 percent o rated thermal power. Correct performance of the RCIC, HPCS, and relief valves is shown.
Reactor process variables are monitored to, determine the transient behavior of the system. during and following main steam line isolation.
The following test is performed:
Action Test Conditions Close all MSIVs (SUT-33 a. Perform at TC-6.
and SUT-5 are to be done b All.systems in NORM in conjunction with 'this mode.
test).
. Acce tance Criteria Level 1:
- 1. Reactor must scram to limit the severity of the neutron flux and simulated fuel surface heat flux transient.
- 2. Feedwater system settings must prevent flooding of the steam lines.
- 3. The recorded MS IV full closure times must meet the previously stated timing specifications (SUT-25A) .
Amendment 12 1 of 2 June 1984
Nine Mile Point Unit 2 FSAR TABLE 14 2 ccD ( Cont)
The positive change in vessel dome pressure occur'ring within the first 30 sec after a closure of all MSIV valves must not. exceed the Level 2 criteria by more than 25 psi. The positive change in simulated heat flux must not exceed the level 2 criteria by more than 2 percent of the rated value.
- 1. The positive change in vessel dome pressure and simulated flux occurring within the irst 30 sec after the closure of all MSIV valves must not exceed the BOL predicted values. Predicted values will be referenced to actual gest conditions of initial power level and dome pressure anc will use BOL nuclear data.
- 2. Initial action of the RCIC and HPCS a e automatic when Level 2 is reached, and system performance is within specifications.
- 3. Rec'culation pump trip shall be leve (L2') 's reached.- Recirculation pump in'iated ifpower low water w'll sni t ro the low freauency mo"or genera"ors i 'ow wa er level (L3) 's reached.
- 4. The tempera"'ure measured by thermocouples on the discharge side of the safety/relief valves must return to within 10 F of tne temperature recorded before the valve was opened.
2 of 2
Nine Mile Point Unit 2 FSAR A )A ITIII'Pl Jc1sJlaE t+
i4 1 Jl o a6 4rMv RELIEF VALVES Starts Test SUT-26 Test Ob ectives To verify that the relief valves function properly (can be opened and closed manually).
- 2. To verify that the relief valves reseat properly after operation.
- 3. To verify that there are no major blockages in the relief valve discharge piping.
Prere isites The preoperational tests have been completed, the SORC has reviewed and appxoved the test procedures and initiation of testing, and instrumentation has been checked or calibrated as appropriate.
Test Procedure A. functional test of each SRV is made as eaxly in the startup program as practical. This is normally the first time the plant reaches 250 psig. The test is then repeated at rated reactor pressuxe. Bypass valve (BPV) response is monitored during the low-pressure test and the electrical output response is monitored during the rated pressure test.
The test duration is about 10 sec to allow turbine valves and tailpipe sensors to reach a steady state.
The tailpipe sensor responses are used to detect the opening and subsequent closure of each SRV. The BPV and power level (MWe) responses are analyzed for anomalies indicating a restriction in an SRV tailpipe. In addition, lead BNR plants measure SRV tailpipe back pressure on the longest and shortest tailpipes.
Valve capacity is based on certification by ASME code stamp and the applicable documentation being available in the onsite records. The nameplate capacity/pressure rating assumes that the flow is sonic. This is true if the. back pressure is not excessive. A major blockage of the line may prevent sonic flow, and it should be determined that no 1 of 3
Nine Mile Point Unit 2 FSAR TABL>~ 1$ .2-230 (C nt) maj or blockage exists through the BPV or MWe response signatures.
Vendor bench test data of the SRV opening responses are available onsite. The response times of relief valves to reactor steam is measured on the three valves of any typ'e or model not previously installed and tested on a reactor.
This procedure is to ensure the validity of the bench testing.
The following tests are performed:
Action Test, Conditions
- 1. STS: 10-sec manual open- a. Heatup at 250 psig.
ing for functional check b. STS: Recirculation of valve and sensor system in MANUAL mode.
response. Other sytems in NORM mode.
- 2. Monitor tailpipe a. Between TC-2 and 3, sensors, BPV, MWe for anomalous and if any valve is read-justed, repeat test.
behavior as each b. Recirculation system SRV is opened. in MAN mode. Other SUT-33, Drywell systems in NORM mode.
Piping Vibration, is to be done in conjunction with this test.
Acce tance Criteria Level 1:
There is positive indication of steam discharge during 0he manual actuation of each valve.
Level 2:
- 1. Pressure control system-related variables may contain oscillatory modes of response. In these cases, the decay ratio for each controlled mode of response is less than or equal to 0.25.
- 2. The temperature measured by thermocouples on the discharge side of the valves returns to within 10 F of 2 of 3
Nine Mile Point Unit 2 FSAR TABLE 14.2-230 (Cont)
If pressure sensors are available, they return to their initial states upon valve closure.
- 3. During the 250-psig functional test the steam flow through each relief valve shall not be less than 90 percent of the average relief valve steam flow, as measured by bypass valve position.
- 4. During the rated pressure test the steam flow through each relief valve, as measured by MWe, is not less than 0 ' percent of rated MWe less than the average of all the valve responses.
3 of 3
Nine Mile Point Unit 2 FSAR tel Atft l.AQ<cs i'x 0 1
~ 46 s3 AQ I 1
TURBINE TRIP AND GENERATOR LOAD REJECTION Startu Test SUT-27 Test Ob ective To demonstrate the response of the reactor and its contxol systems to protective trips in the turbine and generator.
Prere isites The appropriate preoperational tests have been completed; the SORC has reviewed and approved the test procedures and initiation of testing. All controls and interlocks are checked and instrumentation calibrated.
Test Procedure
- 1. Turbine trip (closure of the main turbine stop valves within 0.1 sec) and generator trip (closure of the main turbine control valves within 0.3 sec) is performed at selected powe levels during the star-up test prog am.
At low power levels, reac-or protection following the trip is provided by high neutron flux and vessel high-pressure scrams. For the protective trips occurring at.
intermediate and higher power levels, the reactor scrams by relays, actuated by stop/control valve motion.
- 2. A generator trip is performed at low power level in such a way that nuclear boiler steam generation is just within the bypass valve capacity to demonstrate scram avoidance.
- 3. For the trips performed at intermediate power range, reactor scram is most important in controlling the transient peaks.
- 4. Above 30-percent power, the recirculation pump circuit breakers are both automatically tripped and subseque'nt transient pressure rise is limited by the opening of the bypass valves initially, and the safety relief valves, if necessary.
- 5. For the turbine trip, the main generator. breakers remain loaded for a time so there is no rise in turbine generator speed, whereas in the generator trip, the main 1 of 4
Nine Mile Point Unit 2 FSAR TABLE 14.2-231 (Cont)
'v <<a Q << A~0<<C')0 vv o ~
hQ J 5 0 ~ P4$
<<<<cL1~
'Via a JJ causes a momentary rise in the generator speed.
~
V V ~~
..c o.. 'es Concit:ons
- 1. Gene
~ a '4 't\
a o w<< ply~ <<
load
\ <<'l1~.t&
re j ec 'n, a. A 0 sr TC-1
<<r'
'1% 4 tA ca<<++
( SU
'rat'n,
~
<<<< ~ ~V <<
0 1s to 0 .-..o=; o=".e '%1'C wi th ~11 te t 1 ~
O<<2 V
s
~ <<c <<0<<<<
S .
' ~ ~ ')4 Manual
~ "4'1a ~ ~
interve nt~ on
)
permissible to prevent high or low water level 4
<<ip
- 2. Main turbine trip scram. a. TC-3 (60-80% power) at P g Vibrat'n, (SUT-33, Drywe
be done in conjunction i to b.
295%
mode.
core flow.
All systems in NORM with this test. )
- 3. Generator trip scram. a. Will be done at TC-6.
(SUT-33, Dr ywell Piping b. All systems in NORM Vibration, is to be done mode.
in conjunction with this test..).
Previous experience demonstrates that reactor responses to a tu bine trip and a generator'load rejection at, full powe a e sim'lar for plants like Un't 2 which have steam bypass capac'ties eauivalen to approximately 25 percent o ratec power .. The load rejection trip is performed at full powe to test the turb'ne over'speed protection system.
Ac'eotance C" teria.
Leve 1
- 1. Eor turbine and gener ator trips at power levels greate" th'an 50 percent NBR, there is a delay of less tha..
0.3. sec ollow'ng the beginning of control or stop valve closure before the beginning o bypass valve opening.
The bypass valves are opened to a point corresponding to grea"er than or equal to 80 percent of their capacity Amendment 12 2 of 4 June 1984
Nine Mile Point Unit 2 FSAR T~~LE 14.2-231 (Cont) within 0.3 sec from the beginning of control or stop valve closure motion.
- 2. Feedwater system settings must prevent flooding of the steam line following these transients.
- 3. The two pump drive flow coastdown transients during the first'5 sec must be bounded by the criteria that are specified in SUT'-30B.
The positive change in vessel dome pressure occurring within 30 sec after either generator or turbine trip must not exceed'he Level 2 criteria by more than 25 psi.
- 5. The positive change in simulated heat flux must not exceed the Level 2 criteria by more than 2 percent of rated value.
The total time delay from start of turbine stop valve motion or from star" of turbine control valve motion to
.the complete suppression of electrical arc between the fully open contacts of the RPT circuit breakers shall be less than 190 milliseconds.
Level 2:
There shall be no MSIV closure during the first 3 min of the transient, and operator action shall not be required during that period to avoid the MSIV trip. (The operator may take action as he desires after the first 3 min, including switching out of run mode. The operator may also switch out of run mode in the first '
min if he confirms from measured data that this action did not prevent MSIV closure.)
- 2. The positive change in vessel dome pressure and in simulated heat flux which occurs within the first 30 sec after the initiation of either generator or turbine trip must not exceed the predicted values.
(Predicted values are referenced to actual test conditions of initial power level and dome pressure and use beginning-of-life nuclear data. Worst-case design or technical specification values of all hardware performance are used in the prediction, with the exception of control rod insertion time and the delay 3 of 4
Nine Mile Point Unit 2 FSAR TABLE 14.2-231 (Cont) from beginning of turbine control valve or stop valve motion to the generation of the scram signal.
pressure and heat flux are coxrected for the The'redicted actual measured values of these two parameters.)
- 3. For the generatox trip within the bypass valve capacity, the reactor must not scram for initial thermal powex values within that bypass valve capacity and below the power level of which trip scram is inhibited. The measured bypass capacity (in percent of rated power) is equal to or greater than that used for FSAR analysis'.
Low level initiation of total recirculation trip, HPCS, and RCIC must not occur.
- 5. Recirculation LFMG sets must take over after the initiation of RPT and adequate vessel temperature difference must be maintained.
- 6. Feedwater level control must avoid loss of feedwater due to possible high level (LS) trip du ing the event.
- 7. The temperature measured by thermocouples on the discharge side of the safety/ elief valves must return to within 10 F of the temperature recorded before the valve was opened.
4 of 4
Nine Mile Point Unit 2 FSAR
~
TABLE 14.2-233 RECIRCULATION FLOW CONTROL VALVE POSITION CONTROL Startu Test SUT-29A.
Test Ob ective To demonstrate the recirculation flow control system's capability, while in the valve pos'tion {POS) mode.
P re reaui si te s The appropriate preoperational tests have been completed; the SORC has reviewed and approved the test procedures and initiation of testing. All controls are checked and in-strumentation calibrated.
Test Procedure The testing of the reci culat'on ~low control sys em follows a buil¹ng-block approach wh'e the plant is ascending from low to h'h power levels. Components and inner control loops are tested first, followed by drive f ow control and plant power maneuvers to adjust and then demonstrate the oute loop controller performance. Preliminary component and valve position loup tests are run when the plant is in cold shutdown in order to v'ually observe the hydraulic cylinder response. .%nile operating at low power with. the pumps using the low-frequency power supply, small step changes are input into the position controller and the responses recorded.
The following test is performed:
Action Test Conditions
- 1. Small and large step a. Prior to plant heatup, changes input into position reactor shutdown, re-cont oiler. circ pumps off. {Preop-erational testing re-sults may be used to satisfy this testing requirement.)
1 of 3
Nine Mile Point Unit 2 FSAR TAB E 14.2- 33 ( n )
- 2. Small step changes input into position f
- a. Be ore or at TC-1 wi th pumps using low fre-controller. quency power supply; at TC-3; between TC-5 and 6.
- b. Recirculation system in POS mode; other systems in NORM mode.
Acceptance Criteria Level 1:
The transient response of any recirculation system-related variables to any test input must not diverge.
Level 2:
- 1. Recirculation system-related .
variables may contain osc'llatory modes of response. In these cases, the decay ratio for eacn controlled mode of response must be less than or eaual to 0.25.
- 2. Maximum rate of change of valve position shall be 10 + 1 percent/sec.
During TC-3 and TC-6 while operating on the high speed (60 Hz) source, gains and limiters shall be set to ob-tain the following response.
- 3. Delay time for position demand step shall be:
For step inputs of 0. 5 percent to 5 percent 50.15 sec For step inputs of 0.2 percent. to 0.5 percent (see Figure 14.2-234-1)
- 4. Response time for position demand step shall be:
For step inputs of 0.5 percent to 5 percent 50.45 sec For step inputs of 0.2 percent to 0.5 percent (see Figure 14.2-233-1) 2 of 3
Nine Mile 'Point Unit 2 FSAR vanr~ aa ~ ~e3 (ro ~)
~"e~""ov- a=te= a Bmall bosi Lo i Qemand lncut ( 1
~,I H ~ A &0 input.
Amendment 16 3 of 3 Decembe" 1984
Nine Mile Point Unit 2 FSAR TADwc> Ls c 244
~
RECIRCULATION FLOW LOOP CONTROL Startu Test SUT-29B Test Ob'ectives
- 1. To demonstrate the core flow system's control capability over 0he .entire flow control range including core flow, neutron flux.
- 2. To determine tnat all electrical compensators and con-trollers are set for desired system performance and stability.
Prere isites The preoperational test. have been completed; the SORC has reviewed and approved the test procedures and initiation of testing. All cont o's are checked and instrumentation calibrated.
Tes- Procedure Following the initial position mode tests of Part 1 the final adjustment of the position 'oop gains, flow loop gains, and preliminary values of the flux loop adjustments are made on the midpower line. This is the most extensive testing of the recirculation control system. The core power distribution is adjusted by control rods to permit a broad range of maneuverability with respect to PCIOMR. In general, the controller dials and gains are raised to meet the maneuvering performance objectives. Thus the system is set to be the slowest that will perform satisfactorily, in order to maximize stability margins and minimize eauipment wear by minimizing actuator motion.
Because of PCIOMR power maneuve ing rate restrictions, the fast flow maneuvering adjustments are performed along a mid-powe rod line, and an extrapolation is made to the expected results along the 100-pe cent rod line. The utility ha the option to decide to:
- 1. Perform the faste" power changes on the 100-percent rod line that are greater than what the PCIOMR allows, or
- 2. Accept the mid-power load line demonstrations as accept-able proof of maneuverability.
1 of 5
Nine Mile Point Unit 2 FSAR TABLE 14 2 234 (Co At)
~
For immediate commercial . operation,. the flux loop is set slower, and the operator limits his action in the manual mode. If PCIOMRs are ever withdrawn, the tested faster auto settings can be inserted onto the controller with only a brief dynamic test, rather than a full startup test.
The following tests are performed:
Antinn To st Conditions
- 1. Large and smail seep a. Between TC-2 and 3.
and ramp inputs. b. Recirculation system in FLO and FLX modes; other systems in NORM mode.
- c. Normal power sources to be used as applicable.
- 2. Step and amp input a ~ Between TC-5 and 6.
changes to demon- Rec'culation system stra-e sa 's ac"orv in FL and FLZ modes; esponse. othe" sys"ems in NORE mode.
Acceptance Cr'teria Flow Loops C iteria Level 1:
The ransient response if any recirculation system-related variable to any test input must not diverge.
level 2:
- 1. The decay ratio of the flow loop response to any test inputs must, be (0.25.
- 2. The low loops provide equal flows in the two 'oops during steady-s ate opera~ion. Flow loop ga'ns should be set to correc a flow imbalance in about 20 + 5 sec.
- 3. The delay time for flow demand step (55 percent) must be
- 0. 4 sec or less.
2 of 5
Nine Mile Point. Unit 2 FSAR TABLE 14.2-234 (Cont)
~e response "'me fc" flow demand step (55 perce..t) mus-be 1.1 sec or iess..
ma~'u cw overshoo" or ster> demand o=
w>>> a>>>> oercen o~ he cemanQ The f ow de.-..a"..d s=ep se"-ling time mus" be S6 sec.
The flux loop response to test. inputs must not'diverge.
Level 2 Flux overshoot to a flux demand step must not exceed 2 percent of ra ed for a step demand of 520 pe cent of rated.
- 2. The delay time for flux response fo a flux demand step must, be 50.8 sec.
- 3. The response time for flux demand step. must be 52. 5 sec.
- 4. The flux setting time must be 51S sec for a flux demand s ep <20 percent of rated.
Amendment 16 3 of 5 Dec embe r 19 84
Nine Mile Point Unit 2 FSAR Scram Avoidance and General Criteria Level 1:
Not applicable.
Level 2:
For any one of the above loops'est ma.".euvers, th trip avoidance margins mus be at least the following:
- 1. For APPN 27.5 percent.
- 2. For simulated heat flux 25.0 percent.
- 3. The load following loop response must produce steam flow variations no larger than 0.5 percent of rated steam flow.
%of 5
4 Nine Mile Point Unit 2 FSAR TABLE 14.2-234 (Cont)
Flux Estimator Test Criteria Level 1:
Not applicable.
Level 2:
- 1. Swi"ching between est'mated ano sensed flux should not exceed 5 times/5 min 'at steady state.
- 2. During flux step transient there should be no switching to sensed flux or if switching does occur, it switch back to estimated flux within 20 sec of the start should of the transient.
Flow Con rol Valve Dut Test Cr-'teria Level 1:
No applicable.
revel 2:
The flow control valve duty cyc'e in any operating mode must not exceed 0.2 percent - H~. Flow control valve duty cycle is defined as:
Inte rated valve movement 2 x span in percent (in sec)
'z, 5 of 5
Nine Nile Point Unit 2 FSAR SLY l+. C v A<Af Qplt7f 0 lflf~gf (+v(%ttlg'ig 4 sroSeswg gqq>> <<og~
a(seoloavvka ~ ee o e o v e Startu Test SUT-30A 5Cv cata r c rcala o..g ='='=':.. ~ ~.,~..
~ W ~
~ a tn'e pump t-'p, flow coas"down, anc pump rescar
~ a>>'~ i ~ ~ ~~a <<ss~i'a~ar control svs s.it ca.i
~g>>'
s Co~ qov' c ~ corot ol water 'evel w"thou- a esu't a ~bs~ aVM n~ a a P ereaui si tes The appropriate preoperational tests have been completed and the SORC has reviewed and approved the test proces..es and initiation of testing. Instrumentation has been checked or calibrated as'appropriate.
Test Procedure The reactor coolant recirculation system consists of the reactor vessel and two piping loops. Each loop contains a constant speed centrifugal recirculation pump, a flow control valve, two isolation valves located in the drywell, and 10 j et pumps in parallel, situated in the reactor downcomer. Each recirculation pump takes suction from the reactor downcomer and discharges through a manlfnld system to the nozzles of the 10 jet pumps. Here the flow is augmented by suction flow from the downcomer and .delivered to the reactor inlet plenum.
A potential threat to availability is the high water level turbine trip scram caused by the level upswell that results after an unexpected recirculation one-pump trip. The change in core flow and the resultant power decrease causes void formation which the level sens'ng system senses as a rise in water level. The one-pump t ip tests prove that the water level will not rise enough to threaten a h'h level trip of the main turbine or the feedwater pumps.
Amendment 12 1 of 3 June 1984
Nine Mile Point Unit 2 FSAR TABLE 14.2-235 (Cont)
The following tests a e performed:
Action Test Conditions
- 1. Trip one pump. a. At TC-3 with core flow (Drywell piping 29S% of rated.
vibration test b. All systems in NORM
[SUT-33] can be mode.
done in conjunc-tion with this tes .)
- 2. Restart pump. a. Be-ween TC-2 and 3 (with as high a control rod line as possible).
- b. All 'systems in NORM mode.
- 3. Trip other pump. a. At TC-6.
(Drywell p'ping v.'bra- b. All systems in NORM tion test [SUT-33) mode.
can be done in con-,
junction w 'h th' test).
- 4. Restart pump using p"o- a. On 100% load. line.
cedures developed du ing, b. All systems in NORM ea lier low power mode.
restart ( Item 2) .
Acceptance Crite ia Level 1:
The reactor shall not scram during the .one pump trip recove y.
Level 2:
- 1. The reactor water level margin to avoid a high level trip is greate than or eaual to 3.0 in dur'ng the one-pump trip.
2 of 3
Nine Mile Point Unit 2 CESAR TABLE 14.2-235 (Cone)
NOTE: Margin to trip is defined as:
Margin = LS - (1/2 (L4 + L7) + hL) where:
dL = magnitude of the level swell during the one pump trip event LB = high water level t ip setting L4 = low water level alarm setting L7 = high water level alarm setting
- 2. The simulated heat f3.ux margin to avoid a scram is greater than or equal to 5.0 percent during the one-pump trip and during pump trip recovery.
- 3. The APRM margin to avoid a scram is greater than or ecual to 7.5 percent during the one-pump trip recove y.
3 of 3
II Nine Mile Point Unit 2 FSAR TABLE 14.2-236.
RECIRCULATION SYSTEM, TWO-PUFiP TRIP Startu Test SUT-30B Test Ob'ective To record and verify acceptable perfo mance of the recirculation two-pump ci cuit trip system.
Prereauisites The appropriate preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate. r Test Procedure In case of highe power turbine or generator trips, there is an automatic opening of circ it breakers in the pump power supply. The result is a fast core flow coastdown that helps.
reduce peal neutron and heat flow in such events. This two-pump trip test verif's that th's flow coastdown is satisfactory prior to the high power tu bine generator trip tests and subsequent operation.
The fo 1 lowing test i s per formed:
Ac ion Test Conditions Simulate TG-initiated RPT a. At TC-3 above-50 per-to trip all four RPT cent rated power and at breakers simultaneously. 95 percept or more of (SUT-33, Drywell Pip'ng rated core flow but Vibration, can be done 'n before SUT-27, Turbine conjunction with this Trip and Generator test.) Load Rejection.
- b. All systems in NORM mode. Water level may be lowered to avoid possible turbine trip scram 1 of 2
Nine Nile Point. Unit, 2 FSAR TABLE 14.2-236 {Cont)
~Aece tance Criteria Level 1:
The two-pump drive flow coastdown transient during the fi st 5 sec is bounded by the limiting curves specified in Figure 14.2-236-1. {The limiting curves will he determined based upon measurement of the recirculation flow delta. P using the elbow flowmeters, transmitter time delay, and time constant.)
Level 2:
Not applicable.
2 of 2
Nine Mile Point Unit 2.FSAR TABLE 14.2-237 RECIRCULATION SYSTEM PERFORMANCE Startu Test SUT-30C Test Ob'ective To record recirculation system parameters during the power test program.
Prereauisites The preoperational tests are complete. The SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate..
Test Procedure Recirculation system paramete s are recorded at several power-flow conditions and 'n conjunction w'th s'ngie pump tr'p recoveries.
The ollowing test, ' p rformed:
Act'n Test Conditions Record steady-s ate a. At TC-2, 3, 4, and 6.
operating data. b. Du ing recovery f om single pump trips of SUT-30A.
Acce tance Criteria Level 1:
Not applicable.
Level 2:
- 1. The core flow shor- all snail not exceed 5 percen- at rated power.
- 2. The measu ed core hP shall not be )0. 6 psi above prediction.
- 3. The calculated jet pump M ratio shall not be <0.2 points below prediction.
1 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-.237 (Cont)
- 4. The drive flow shortfall shall not exceed 5 percent at rated power.
- 5. The measured recirculation pump efficiency shall not be
>B percent points below the vendor-tested efficiency.
- 6. The nozzle and riser plugging criteria shall not be exceeded.
2 of 2
Nine Mile Point Unit 2 FSAR TPBL E 1n o 23o RECIRCULATION PUMP RUNBACK Startu Test SUT-30D Test Ob 'ective To verify the adequacy of .the recirculation runback to prevent a scram on loss of one feedwater pump and subsequent Level 4.
Prereauisites The appropriate preoperational tests have been completed.
The SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.
Test Procedure While operating at near rated recirculation. flow, a loss of a feedwater pump is simulated. The transient and final condition are studied to determine tne adecuacy of the system in preventing a scram during the scheduled loss of a single feedwater pump trip test (SUT-23C).
The following test i's performed:
Action Test Condi ions Simulate loss of a. At TC-3 with core flow feedwater- pump to 295% of rated.
initiate recircula- b. All systems in NORM mode.
tion runback mode..
Acceptance Criteria Ievel 1:
Not applicable.
Level 2:
The recirculation flow control valves shall run back to 45 percent drive flow upon a trip of the runback circuit.
1 of 1
Nine Mile Point Unit 2 FSAR TABfE 14.2-239 RECIRCULATION SYSTEM CAVITATION
.Startu Test SUT-30E Test Ob'ective To verify that no recirculation system cavitation occurs in the operable region of the power-flow map.
Prerecuisites The appropriate preopera ional test have been completed.
The SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.
Test Procedure Both the jet pumps and the recirculation pumps will cavi ate at conditions of high flow and low power where NPSH demands are high and little feedwater subcooling occurs. However, the recirculation flow wi'1 automatical' run back upon sensing a dec ease in subcoo'ing (as measured by the diffe ence between the steam dome and reci culation loop temperature) to lower the reactor power.'t w'l be veri fied that these 'mi ts are su fficient to prevent operation where recirculation pump or jet pump cavitation is predicted to occur.
The recirculation system flow control valves will cavitate at conditions of high d'ferential pressure and low power (low subcooling) . The recirculation flow will automatically run back upon sensing a decrease in subcooling (as measured by a low feedwater flow). This limit will be verified to ensure that operation is prevented where flow control valve cavitation may occur.
In both of these cases, flow runback is accomplished by a shift in the powe supply to the recirc.lation pump motors from normal power to the low reauency motor generators.
1 of 2
Nine Wile Point Unid 2 CESAR
'P5'll'' d. 2 930 (C~~4 )
+Sv a sv+O+
Va ~ aat
~
Action Test Conditions V 'U ~ V
)
4 8 V 4 C7 V Pl 4I 7hk I
~ ~
- a. A":':
-2 a.".d .3.
I V b. A svstems in NC+'1 4Lil 4 4 a cav ta -io n int "- mode.
'ock ates re c'culat'n QO V$
'vte~ ' yt gQ ~
0~c~ s c ~ w~ ~ L ev ch ievel 1:
0 aQQi cable Leve':
Runbacl. logic se" ings are adecua e to prevent operation in areas of potential cavita ion.
Amencnren- 12 2 of 2 June 1984
Nine Mile Point Unit 2 FSAR TABi E 14.2-240 LOSS OF TURBINE GENERATOR AND OFFSITE POWER Startu Test SUT-31 Test Ob'ective To determine the electrical equipment and reactor transient performance during the'oss of auxiliary power.
Prereauisites The appropriate preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.
Test Procedure The loss of auxiliary power test is per ormed at 20 to 30 percent of rated power. The .proper response of reactor plant equipment, au omat' sw'ching equipme. t, and the proper sequenc'ng of the diese'enera=o load are checked.
Appropriate reactor parame=ers are recc ded during the resultant trans'ent. The loss of power w ll be maintained long enough for plant conditions to stabi3.ize (230 min) .
Systems which do not affect vessel level and pressure may be manually started and operated, as necessary.
The following tes is performed:
Action Test Condit. ons After transferring auxiliary a. At TC-2..
loads to the unit auxil'ry b. Recirculation system transformer and starting in POS mode. All other main turbine dc oil pump, systems in NORM mode.
use the trip relay to trip the main generator. (SUT-33, Action Item 1, can be done in conjunc ion with this test.)
1 of 2
Nine Mile Point Unit 2 CESAR
'ZABLE 14.2-240 {Cont,)
Acceptance Criteria Level 1:
1, All safety systems such as the RPS, diesel generators, and HPCS must function properly without manual ass'tance, necessary, and HPCS and/or RCIC system shall keep the reactor water level action, above the if initia ion level of the IPCS, LPCI, ADS, and MSIV closure. Diesel generators shall start automatically.
Level 2:
- 1. Proper instrument display to the reactor operator shall be demonstrated, including power monitors, pressure, water level, control rod position, suppression pool temperature, and reactor cooling system status.
Displays shall not be dependent on specially installed instrumentation.
- 2. If safety)relief va'ves ope... the temperature measu ed d'charge by thermocouples on he side of the safety/ elief valves must return to with'n 10 O~F of -he temperature recorded before the valve was opened.
2 of 2
Nine Mile Point Unit 2 FSAR TABLF. 14.2-2il DRYWELL PIPING VIBRATION Startu Test SUT-33 Test Ob ectives
- 1. To verify that the vibration of the reactor recir-culation is within acceptable limits.
- 2. To verify that stresses are within code limits during operating transient loads.
Prere isites The appropriate preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.
Tes- Procedure This test is an extension of the system expansion test (SUT-17). Consul" the spec'cation of SUT-'17 for piping considered to be within the scope of testing.
Because of limited access due to high radiation levels, no visual observation is reauired during the startup phase of the testing. Remote measurements of piping vibrations. are made during the following steady-state conditions:
- 1. Recirculation at minimum flow and coincident temperature.
Nine Mile Point Unit 2 FSAR TZBuF. 14. 2-241 (Cont)
- 2. Recirculation at 50 percent +5 percent of rated flow and operating temperature.
- 3. Reci'rculation at 75 percent +5 percent of rated flow and operating temperature.
4.. Recirculation at 100 percent of rated flow.
During'he operating transient load testing the amplitude of displacement flectionn and number of cycles per transient of the
! recirculation piping are measured, and the di splacements compared with acceptance criteria. Remote vibration and de-measurements are taken during the following transients:
- 1. Recirculation pump start.
- 2. Recirculation pump trip at 100 percent of rated flow.
The locations o be monitored and predicted displacements for the monitored loca=ions in each plant will be provided later.
The following tests are performed:
Action Test Conditions Record recirculation a. Recirc. at minimum flow. at, loop vibration TC-1
- b. At 50, 75, and at approxi-mately 100% of rated recirc-ulation flow on 100% load line.
- c. In conjunction with recirc-ulation pumps starts and trips (Tests 30A and B) at TC-3 and 6.
- d. In conjunction with Test 71 while at 100% of rated RHR flow in the shutdown cool-ing mode.
2 of 4
Nine Mile Point Unit 2 FSAR TABLE 14.2-241 (Cont)
Acce tance Criteria Level 1:
Operating transients: Level 1 limits on piping displacements are prescribed in GE Test Specification No. 5 23A4138. These . limits ar e based on keeping the
.loads on piping and suspension components within safe limits. If any one of the transducers indicates that these movements have been exceeded, the test is placed on hold.
- 2. Operating vibration: Level 1 limits on piping displacement are prescribed in GE Test Specification No. 23A4138. These limits are based upon keeping piping stresses and pipe mounted eauipment accelerations within safe limits. If any one of the transducers indicates that the prescribed limits are exceeded, the test is placed on hold.
Level 2 Operating transients: Transducers have been placed near points of maximum anticipated movement. Where movement values have been p edicted, tolerances are prescribed for differences between measurements and are basec on instrument accuracy amd suspen-predictions'olerances sion free play. Where no movements have been predicted, limits on displacement have been prescribed. GE Test Specification No. 23A4138 tabulates allowable movements or movement tolerances for each transducer.
- 2. Operating vibration: Acceptable levels of operating vi-bration are prescribed in GE Test Specification No. 23A4138. The limits have been set based on con-sideration of analysis, operating experience, and protection of pipe mounted components.
3 of 4
Nine Mile Point Unit 2 CESAR TABLE 14.2-241 (Cont)
THIS PAGE INTENTiONALLY BLANK 4 of 4
Nine Nile Point Unit 2 CESAR TPDLE 14. 2-242 iCN ST:"A c LOW CAL:BM xON Sta~ua Te'st SUT-35
<<wb j oc
<<4S
~
~>>
lsss <<1~a>
I a I 4 e>><<<<
culat'n system ='w 'strumentation.
<<>>o>>ar
="=c=e"ational tests have been completed SGRC ha- " ;" ewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.
Te'st Procedure vi
<<'<<<<r<<so s << ~ "gr=-... a= ooe "at'ng cond'"'ons that al-1"w -he w or v>>
~
<<V svs" e.-., to be opera"ed a" "a"ed ='ow at
~
power, the jet pump flow instrumentat'on is adjusted to provide correct flow indicat'on based on jet pump flow. Af-ter the relationship between dr'ive flow and core flow is established, the flow biased APRM/RBM (rod block mon'or) syst m-is adjusted to match this relationship.
The following test is performed:
Action Test Conditions Take recirculation system a. At TC-3.
data and recalibrate b. At TC-6.
instrumentation.
Acceptance Criteria Level Not applicable.
Level 2:
- 1. Jet pump flow inst umentat'on is adjusted in such a way that the jet pump total flow recorder provides. a correct core flaw indication at rated conditions.
Amendment 8 1 of 2. January 1984
Nipe Mile Point Unit 2 CESAR 1 4 2 2d2 (Pont )
~' 'I % ~8 / e1 ~ ~ 'W gQ A 2 ~ e 4 ~
function properly at rated conditions.
v'i ~ vp4 ~
0\ Qt~ ~
~~ we I VA V'V P% ~ 1
=v2. 3 v8 v'o ) . p, y~ o~~ pi Amendment 12 2 of 2
Nine Mile Point Unit 2 FSAR TABLE 14.2-243 REACTOR WATER CZEANUP SYSTEM Startu Test SUT-70 Test Ob'ective To demonstrate specific aspects of the mechanical ability of the RWCU.. (This test, performed at rated reactor pressure and temperature, is actually the completion of the preoperational testing that, could not be done without nuclear heating.)
Prere isites The preoperational tests have been completed, and the SORC has reviewed and approved the test procedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.
Test Procedure W'n the'eactor a" ratec temperature and pressure, process variables are recorded during steady-state operation in three modes as defined by the system process diagram: hot s andby, noxmal, and blowdown. A comparison of the bottom head flow indicator and the RWCU inlet flow indicator is made during these modes. The RWCU system sample station is tested at hot process conditions as paxt of SUT-1.
The following test is performed:
Action Test Conditions Take heat balance and a. Reactor at rated tempexa-pressure data. ture and pressure during heatup.
- b. Cleanup system operate in hot standby, normal, and blowdown modes..
Acceptance Criteria Ievel 1:
Not applicable.
1 of 2
Nine Mile Point Unit 2 FSAR T~BLi 14.2-243 (Cont)
Level 2:
- 1. The temperature at the tube side of the nonregenerative heat exchangers does not exceed 130 F in the blowdown mode or 120 F in the normal mode.
- 2. The pump available NPSH at least 13 ft during the hot standby mode is as defined in the process diagrams.
- 3. The cooling water supplied to the nonregenerative heat exchangers shall be less than 6 percent above the flow corresponding to the heat exchanger capacity {as determined from the process diagram) and the existing temperature differential across the heat exchangers.
The outlet temperature shall not exceed 180 F.
- 4. Recalibrate bottom head flow indicator against RWCU flow indicator if the deviation is greater than 25 gpm.
Pump v'bration sna be less than or equal to 2 mils peak-to-peak (in any " d'rec ion) as measured on the bearing nousing, anc -..i's peak-to-peak sha t vibration as measured on the coupling end.
2 of 2
0 Nine Mile Poi.nt Unit 2 FSAR TABLE 14.2-244 RESIDUAL HEAT REMOVAL SYSTEM Startu Test SUT-71 To demonstrate the ability of the RHR system to:
h ea t from the reactor system so that the
- 1. Remove l'
refue ing an nuclear n system servicing can be performed.
- 2. Condense steam while the reactor is isolated from the main condenser.
Prere isites The appropria e preoperational p tests have been completed, and approved the te st procedures the SORC h ass reviewed andInstrumentation initiation o f testing. has been checked and or calibrated as approp iate.
Test Procedu e With the reactor at a convenient thermal power, the steam condensing mode of the RHR System is tuned and demonstrated. Condensing heat exchanger performance characteristics are demonstrated. Final demon-stration of the condensing mode is done from an isolated condition.
During the first suitable reactor cooldown, the shutdown cooling mode of the RHR system is demonstrated. Unfortunately the decay heat load is insignificant during the startup test period. Use of this mode with low core exposure could result in exceeding the 100'F/Hr cool-down rate of the vessel if both RHR heat exchangers are used simultane-ously. Late in the test program after accumulating significant core exposure, this demonstration would more adequately demonstrate the heat exchanger capacity. The RHR heat exchangers will also be tested in the suppression pool cooling mode.
The following tests are performed:
1 of 3
Nine Mile Point Unit 2 CESAR TABLE 14..2-244 (Cont)
Action Test. Conditions
- 1. Controller adjust- a ~ Reactor not isolated ment based on sub- above 10$ rated power system per- but 525% rated power.
turbations b. RHR system in steam condensing mode.
- 2. Demonstration of a ~ Reactor at hot standby steam condensing and isolated.
- 3. Take heat ex- a ~ RHR in shutdown cooling changer capacity mode.
data. b. After trip or cooldown from TC-6 in order to pro-vide sufficient decay heat.
c ~ RHR in suppression pool cooling mode.
Acceptance Criteria level 1:
The transient response of any system-related variable to any test input must not diverge.
Level 2:
- 1. The RHR system must be capable of operating in the steam condensing, suppression pool cooling, and shutdown cooling modes (with both one and two heat exchangers) at the flow rates and temperature differentials indicated on the process diagrams.
- 2. System-related variables may contain oscillatory modes of response. In these cases, the decay ratio for each controlled mode of response must be less than or equal to 0.25.
2 of 3
Nine Mile Point Unit 2 FSAR TABLE 14 2 4P3 QUALIFICATION OF GE PRINCIPAL TESTING PERSONNEL DURING STARTUP TESTING The GE Site Operations Manager ,meets the equivalent of ANSI N45.2.6, 1978, discussed foz a Level III person. The Operations Manager is normally present for pzeoperational testing and will be SRO certified under the GE cextification program.
The GE Operations Superintendent meets the equivalent of ANSI N45.2.6, 1978, discussed for a Level III person or a Level II pe son. The Operations Superintendent is normally present for preoperational testing and will be SRO certified under the GE certification program.
The GE Shift Superintendents meet the equivalent of ANSI N45.2.6, 1978, discussed for a Level II person. They will also be SRO certified under the GE certification program.
The GE Lead S"ar"up Tes" Design and Analysis Engineer meets the equivalent of ANSI N45.2.6, 1978, discussed for a Level III person or a Level II person. He is qualified at the time of appointment to the position.
The GE Sta tup Test Design and Analysis Engineers meet the equivalent of ANSI N45.2.6, 1978, discussed for a Level II person.
The GE Startup Control and Instrumentation Engineers meet the equivalent of ANSI N45.2.6, 1978, discussed for a Level II person.
The GE Startup Chemist meets the equivalent 0f ANSI N45.2.6, 1978, discussed for a Level II person.
In addition, all GE personnel listed above will meet ANSI 3. 1, 1978, Section 4.3.2 minimum qualifications.
1 of 1
START-UP INTERNAL TECHNICAL REVIEW TEST GROUP MANAGER REVIEW AND APPROVAL (1)
REVIEW CYCLE (2)
JOINT TEST GROUP APPROVAL
- 1. FINAL STEP FOR SELECTED PRELIMINARYTESTS.
.2. JTG MEMBERS, QUALITYASSURANCE AND OTHERS AS DESIGNATED BY THE TEST GROUP MANAGER.
FIGURE 14.2-1 REVIEW CYCLE FOR SELECTED PRELIMINARYAND ALL PREOPERATIONAL TEST PROCEDURES NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
TECHNICAL REVIEW SORC REVIEW GENERAL SUPERINTENDENT NUCLEAR APPROVAL AND SIGNATURE SRAB REVIEW OF ACCEPTANCE CRITERIA SCOPE, AND PURPOSE SECTIONS*
APPROVAL AND SIGNATURE STATION SUPERINTENDENT STATION SHIFT SUPERVISOR FOR TEST USE
- NOTE THAT THE TEST IS NORMALLYEXECUTED AFTER SRAB CONCURRENCE FIGURE 14.2-2 REVIEW CYCLE FOR INITIAL STARTUP TEST PROCEDURES NIAGARA MOHAWK POWER CORPORATION NlNE MILE POlNT-UNlT 2 FINAL SAFETY ANALYSIS REPORT
TEST ENGINEER REVIEW TEST GROUP MANAGER/LEADENGINEER (1)
JOINT TEST GROUP REVIEW AND APPROVAL SORC REVIEW AND ACCEPTANCE O'F SYSTEM ACCEPTANCE BY THE STATION SUPERINTENDENT
- 1. FINAL STEP FOR PRELIMINARYTEST RESULTS EXCEPT AS NOTED IN 14.2,5.1 FIGURE 14.2-3 PRELIMINARYAND PREOPERATIONAL TEST RESULTS REVIEW NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
0 SORC REVIEW AND APPROVAL SRAB REVIEW AND CONCURRENCE*
APPROVAL STATION SUPERINTENDENT RECORDS MANAGEMENTFILING
- NOTE THAT SRAB REVIEWS THE PURPOSE, SCOPE, ACCEPTANCE CRITERIA, RESULTS, AND EXCEPTIONS.
FIGURE 14.2-4 INITIALSTARTUP TEST RESULTS REVIEW NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT13 AUGUST 1984
130 A. NATURALCIRCULATION 120 8 LOW RECIRCULATION PUMP SPEED VALVE MINIMUiMPQSITION C. LOW R CIRCULATION PUMP SP ED VALV MAXlhIUMPOSITION O. RATFO R 'RCUL 'ON PU51 SP D VALVESIINI. IUM PCSITION 110 AiiIALYi ICAL CW R LIMITOF hIAS ER POWER FLOW CON ROI ~
F. ANALYTICALUPPER LIMITOF MASTER POWER FLOW CONTROL 100 NO. 6 105lii ROD LINE 90 100 Ii ROD LINE 80 75% ROD LINE I 70 NO. 5 I
Z 60 C NO. 3 K
W 50 NO. 4 40 30 MINIMUMFLOW CONTROL LINE FQR TRANSFER TO 100% SPO NO. 2 20 CAVITATIONREGION R ECQLIMEiNOED STARTUP PATH 10 NQ. I i I I I 10 20 30 40 50 60 70 80 90 100 110 PERCENT CORE FLOW CONDITION (TC) 1 BEFORE MAIN GENERATOR SYNCHRONIZATIONAND RECIRC PUMPS OPERATING Ohl LOW FREQUENCY POWER SUPPLY 2 BETWEEN 50% ANO 751e CONTROL ROD LINES. AT OR BELOW THE ANALYTICALLOWER LIMITOF MASTER FLOW CONTROL MODE FROM 50% TO 75% CONTROL ROO LINES ANO CORE FLOW BETWEFN 60% ANO MAXIMUMALLOWABLE NATURALCIRCULATION ANO WITHIN 5% OF THE INTERSECTION WITH 100% ROD LINE MID POWER RANGE WITHIN 5'Yi OF 100% CONTROL ROO LINE AND 0 TO >5% CORE FLOW OF THF MINIMUMFLOW LINE. FOR MASTER FLOW CONTROL IN MANUALMODE. ANO FOR AUTOMATICPOWER CONTROL IN AUTO MODE WITHIN 0 TO -5Fii OF RATFD THERMAL POWER, AND WITHIN 5% OF RATED CORE FLOW RATE AT 1059o OF RATED THERMAL POWER ANO 100% CORE FLOW FIGURE 14.2-5 TEST CONDITION REGION DEFINITION NIAGARA MOHAWK POWER CORPORATION NlNE M)LE POINT-UNlT 2 FINAL SAFETY ANALYSIS REPORT
'THlS FIGURE HAS BEEN DELETED FIGURE 14.2-6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
NMP2 SWEC STATION PROJECT PROJECT SUPERINTENDENT OIRECTOA MANAGER SUPEAVISOA STAATUP OF MANAGER OPEAATIONS GE SWED STARTUP TEST PAOJECT UNIT SITE ADMIN. GROUP OPEAATIONS ADVISORY STAFF MANAGER MANAGERS MANAGEA ENGINEEA LEAD ENGINEERS TEST GE LEAD ENGINEER GE STARTUP A TEST OPERATIONS GROUP DESIGN ANO SUPERINTENDENT SUPERVISOAS ANALYSIS GE STARTUP A TEST ENGINEERS GE TEST DESIGN SHIFT AND ANO ANALYSIS STAFF SUPERINTENDENTS ENGINEERS FIGURE 14.2-7 UNIT 2 STARTUP ORGANIZATION NIAGARA MOHAWK POWER CORPORATION NlNE MlLE POINT-UNlT 2 FINAL SAFETY ANALYSIS REPORT
p 45 0.4 AREA OF AREA OF ACCEPTABLE RESPONSE UNACCEPTABLE RESPONSE O
LLl vl P3 LLl l-Lll VL z0 LL.
V)
Lll LL:
0.2 0.1 0.1 0.2 0.3 DELAY TIME (SEC)
FIGURE 14.2-233-1 TRADEOFF CURVE FOR STEP SIZES 0.2% TO 0.3%
NIAGARA MOHAWK POWER CORPORATION NINE M)LE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
The foi3 owing are drafts of the revised resnonses to the ex.'sting FSAR Chapter 14 questions that t equire modification due to the proposed revision to the chap"er. Ef a response is not included in this list then our ~ review indicates that the submitted amendment does not alter the present response. These revised responses will be formally submitted in the near future.
9 F648. 86 Valves requir ing loss of air /N were added "'.o 2
the . Tab3.e 14. 2-43. This amendment adds the ability to do the valves with each sys em instead of as a group with the air/N sys ems.
9 F648. 88 '. ~ iuMP2 compl ies w 'h the int n<<of egulator y Guide. See rev'ed Sec" -'o' 14. 2. 7 a Tables 14. 2-125, 126 and 123.
- 3. Verificat ion of check valves supplying coo'..g water to the diesel generators in the Preservice and Enservice inspect ion Pr ograms.
4a. See r evised test abstr act 14. 2-129.
4b. The design of the YiNP2 Diesel Generator sta. -.
logic precludes the complete consumption of the starting air on an initial failure to start as described in the subject ERE Information >Yotice.
a F648.11 Revised responses.
. 2.. Cooling ability of the transformers is
~ verif ied in the LOOP/ECCS test (Table '4. 2-123>,
additional checks are made during the appropr iate tests conducted during the Startup Test Phase, such as the 188/ warranty r un. However we do no.
intend to per form at these tests at fu3.1 l a ed load of the transformers (with the exception of the Main Transformer> as this is impractical, essent ial ly impossible with present design and highly expensive, as it would require tern orary.
buses and circuit breakers capable of hand. ling loads in excessive of pr esent design in order to fully load the transformers and then tee acquisition of sufficient high voltage loads and cabling capable of dissipating this every and finally the installation (and removal, if not permanent > of this equi prnent. Present plan is to use maximum available loads in plant and verify that the transformer temperatures are within speci ficat ion.
in-plant
- 3. Al 1 supply power to vita'c tested. See revised test abstracts buses we pawer generat ing equi "merit
- 14. 2-9 1 aa<
'5 and 125.
iona
- 4. See . evised test aastract '.4. 2- 25 ~
Q F648. '3 Veri f i cat iar. of emergency heat r ernava. rates cannot be per formed dur in- the Preoperat Phase due to the lack af heat praducinc 'est sources. Neasur ernents of the appl icab' par ameters (temperat ures and f 1c<~s) w- 1 1 be performed dur ing the Startup 7 st Phase out 'rg the vat ious test ln wh ch su ~ ' cnt ~ 1 a" bein- pradu ed i",i the =S,= ecui =ment at eas. '",." se values w. '; ~
be t eviewec and evaluated bv .4:nPC Engineering ta insure the heat removal, ates are adequate and cort espond ta the des"'.;
calculai ians.
Q F648. 19 Al 1 radiat ian detect ian and monitoring devices for the L'quid and Soi'd Radwaste Systems are included in the Digita'adiat'on <Nc<nitaring equipment <Table 14. 2-185) . Cal ibr at ian of these devices is per formed using "spiked" samples and/or sources as a prerequisite ta the preaper at i anal test. The opera.:on c<f' percentage of these devices is reverified durin" the pr caper at ional test. The o er at of the t emaining devices are a;sa io'na'nterfaces veri f ied in the pr cape. at ional tes using simulated or test si g'nals.
Q F648. 22 Incorr ect t ab 1 e is re ferenced. Should be
- 14. 2-184 not 14 2-98. ~
Q F648. 34 Revised responses.
- 1. L(5) Condenser off-gas isolation and logic assoc'ated with this feature is tested as part of the radiat ion monitoring <table 14. 2-186) and Qf f-Gas
<Table 14. 2-68) systems prec<perat i anal test s.
- 1. L(7) Liquid Radwast e e f f l.uent i sa 1 at i an inst rurnent at i on and logic associated with this feature is tested as par t af the radiat ian mani t or in g syst erns. (Table 14. 2-185)
- 1. n(3) Vent ilat ian chilled water systems wi 1 1 be tested during the HVAC pr eoperat ianal tests.
<<P I
- i. m(3) Leak tests of sect ianali "ing devices and d. a (5) gasket or bellows leak tests in the refuel inc canal will be tested pr ior ta tne Fue Pool Cooling System Preaperatioral Test. ( able
- 14. 2-56)
Polar crane and hoist dynamic and s"atic .aac
- 1. a (1) tests are performed as a arerequis 'e '". - "he polar cr ane preaperat i oral . est (; able 14. 2- =: 3) .
Q F648. 34-2 Abstract 14. 2-78 has been deleted.: his system is not considered to required a preaperat iona ~
test as def ined Xy Reg. Guide 1. 68 and its test ing is therefore not described in the FSAR.
Q F648.35 Revised . espanses.
il These tests, gust if'icat ian for their I
1 ~
delay and the t ime ant icipated rar their performance wi1 1 be pr ovided by faur th quart et 1985.
- 2. The methods for obtaining changes to approved preoperat ianal and start up test procedures is described in FSAR Sect ian
- 14. 2. 4. 4. No r equirement exists, ar p. iar 'a NRC not i f icat ions for changes preoperat ional test procedure es.