ML17277B177

Forwards Updated Chapter 14.2, Sys Lineup,Preoperational & Initial Startup Test Program. Info Will Be Included in Amend 34 to FSAR

ML17277B177
Person / Time
Site:	Columbia
Issue date:	12/09/1983
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
GO2-83-1135, NUDOCS 8312190114
Download: ML17277B177 (215)

Text

REGULATORY ORMATION DISTRIBUTION SY M (RIOS)

AOCESSION NBR;8312190114, DOC ~ DATE! 83/12/09 NOTARIZED: NO DOCKET FACIL;50 397 WPPSS Nuclear Projects Unit 2~ Washington Public Powe 05000397 AUTH ~ NAME -

'UTHOR AFFILIATION SORENSEN<G'C, Washington Public Power Supply System

'-RFC IP ~ NAME RECIPIENT AFFILIATION SCHHENCEREA ~ Licensing 8r anch 2 p.t Q -Ar Forwards update Lhapt8r 14 ~ "Sys Lineup Preoperational E3'UBJECT: 8 Initial Star tup Teat pr arri am," Info wi'll be included: in Amend 34 to.'FSAR< Orrt DISTRIBUTION CODEi 8001S COPIES RECEIVED:LTR ZEr,:

TITLE: Licensing Submittal: PSAR/FSAR Amdts L elated Correspondence NOTESe RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME I.TTR ENCL ID CODE/NAME LTTR ENCL NRR/DL/ADL .0 NRRr LB2'BC 1 0 NRA I.B2", LA 1 0 AULUCKgR; 01 -1 INTERNAI e 1. "0 IE F ILE~ 1 1 ELO/HDS2'E/DEPER/EPB 36 IE/DEPER/IRB 35 1 1 IE/DEQA/QAB 21 1 NRR/DE/AEAB -1 0 NRR/DE/CEB 1 NRR/DE/EHEB 1 1 NRR/DE/EQB 13t 2  ? NRR/DE/GB'8 2" 2' NRR/DE/MEB 18 1 NRR/DE/MTEB 17 NRR/OE/SAB 24 1 ~

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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 December 9, 1983 G02-83-1135 Docket,No. 50-397 Director of Nuclear Reactor Regulation Attention: Hr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PROJECT NO. 2 INITIAL TEST PROGRAH, FSAR CHAPTER 14.2 Chapter 14.2 of the FSAR will be updated in FSAR Amendment No. 34 to reflect the Startup Power Ascension Test Program. Attached is a copy of the update.

Should you have any questions, please contact Hr. P. L. Powell, Hanager, WNP-2 Licensing.

Very truly yours, G. C. So ensen, Hanager Regulatory Programs tmh Attachment cc: R Auluck NRC WS Chin - BPA AD Toth NRC Site 83<>>9 PDR

" g Ssi209 ADOCK osooos~ pDR A

14.2 SYSTEM LINEUP, PREOPERATIONAL, AND INITIAL STARTUP TEST PROGRAM The initial test program consists of a series of tests cate-gorized as system lineup testing, preoperational, and initial tests. The system lineup testing determines correct itartup stallation and functional operability of equipment. Pre-op rational tests are those tests normally conducted prior to uel loading to demonstrate the capability of plant sys-tems to meet performance requirements. Initial startup tests begin with fuel loading and demonstrate the capability of the integr ted plant to meet performance requirements.

14.2.1 UMMARY OF TEST PROGRAM AND OBJECTIVES 14.2.1.1 nitial Test Program Objectives The objective of the initial test program are:

a. to nsure that the construction is complete and cceptable;

b. to dern nstrate the capability of structures, compone ts, and systems to meet performance requirem ts; c to effect el loading in a safe manner;

d. to demonstrat , where practical, that the plant is capable of ithstanding anticipated transients and postulated ccidents;

e. to evaluate and d onstrate, to the extent pos-sible, plant opera 'ng procedures to provide assurance that the o crating group is knowledge-able about the plant nd procedures and fully prepared to operate th facility in a safe manner; and

f. to bring the plant to rat d capacity and sus-tained power operation.

14.2-1

~ ,

J 14.2.1.2 Initial Test Program Summaries The three categories of tests in the initial test. program are summarized below:

a. System lineup tests such as pump and valve tests, mechanical actuation to" verify proper installation, and electrical continuity verifi-cations, are those tests which demonstrate that, components are correctly installed and opera-tional.

b. Preoperational tests are conducted prior to fuel loading to demonstrate that the plant systems have been properly designed and that they meet performance requirements.

c.. Startup tests consist of fuel loading, ascension precriti-cal tests, low power tests, and power tests that ensure fuel loading in a safe manner, confirm the design bases, demonstrate where practical that the plant is capable of with-standing the anticipated transients and postu-lated accidents, and ensure that the plant is safely brought, to rated capacity and sustained power operation.

14.2.1.3 Description of System Lineup Tests Typical system lineup tests 'generally include but are not limited to the following:

a. chemcial cleaning and flushing of systems, tanks and vessels;

b. electrical equipment test to, and including, energizing, e.g., checking grounding, relay checks, checking circuit breaker operation and controls, continuity checks, megger tests, phasing check, high potential measurements, and energizing of buses;

c. initial adjustment and bumping of motors;

d. checking control and interlock functions of instruments, relays, and control devices; 14.2-2

e. calibrating instruments and checking or setting initial trip setpoints;

f. pneumatic testing of instruments and service air system and cleanout of lines;

g. checking and adjusting relief and safety valves;

h. complete tests of safety-related motor-operated valves including adjusting torque switches and limit switches, checking all interlocks and controls, measuring motor current and operating speed, and checking leaktightness of stem packing and valve seat during hydrotests; and complete tests of NSSS control systems including checking all interlocks and controls, adjusting limit switches, measuring operating speed, checking leaktightness of pneumatic operators, and check-ing for proper operation of controllers, pilot solenoids, etc.; and

i. other tests and verifications such as structural; leaktightness; and vibration.

14.2.1.4 Description of Preoperational Tests A listing of the preoperational tests, together with sub-section and page references 'foach, follows as Table 14.2-1.

The general objectives of the preoperational test phase are as follows:

a. ensure that test acceptance criteria are met;

b. provide documentation of the performance and safety of equipment and systems;

c. provide baseline test and operating data on equipment and systems for future reference;

d. run-in new equipment for a sufficient period so that any design, manufacturing, or installation defects can be detected and corrected;

e. ensure that plant systems operate together on an integrated basis to the extent possible;

14. 2-3

WNP-2

f. give maximum oppoitunity to the permanent plant operating staff to obtain practical experience in the operation and maintenance of equipment and systems;

g. establish safe and efficient normal, abnormal and emergency operating procedures, to the extent possible; I

h. e'stablish and evaluate surveillance testing pro-cedures; and

i. demonstrate that systems and safety equipment are operational fuel and that lo'ading and to the it is possible to proceed to Startup Phase.

14.2.1.5 Description of Startup Tests After the Preoperational Test Phase has been completed, the Startup Phase begins. The Startup Phase begins with fuel loading and extends to commercial operation. This phase is subdivided into the following four parts:

a. Fuel loading and shutdown power level tests

b. Power testing from 0 to 25 percent of rated.

output

c. Power testing from 25 to 100 percent of rated output

d. Warranty demonstration The tests conducted. during the Startup Phase consist of Major Plant Transients (Table 14.2-2), Stability Tests (Table 14.2-3), and a remainder of tests which are directed towards correct performance of the nuclear boiler and 'emonstrating numerous auxiliary plant systems. while at power. Certain tests may be identified with more than one class of'est.

Table 14.2-4 shows the complete Startup Test Program.

14. 2-4

AMENDMENT NO. 7 WNP-2 November 1979 The general objectives of the Startup Phase are as follows:

a. to achieve an orderly and safe initial core loading;

b. to accomplish all testing and measurements necessary to determine that the approach to initial criticality and subsequent power ascension is safe .and orderly;

c. to conduct low power physics tests sufficient to ensure that test acceptance criteria have been met;

d. to conduct initial heatup and hot. functional testing so that hot integrated operation of all systems is shown to meet test acceptance cri-teria;

e. to conduct an orderly and safe power ascension program, with requisite physics and systems testing, to ensure that the plant operating at power meets test acceptance criteria; and

f. to conduct. a successful warranty demonstration program.

14.2.2 ORGANIZATION AND STAFFING 14.2.2.1 General The WPPSS Test and Startup Program is administered by two entities with distinct levels of responsibility. The Test Working Group provides review, approval and planning of general Test and Startup Program activities and the results of those activities. The Test and Startup Department and qualified members of other organizations represented on the Test Working Group provide the necessary development, imple-mentation and analysis of Test and Startup Program activities at the working level.

14.2-5

WNP-2 AMENDMENT NO. 7 November 1979 14.2.2.2 Definitions The definitions of phrases used in this section and through-out this chapter are as follows:

a. Test Working Group (TWG) a project on-site administrative body whose membership consists of personnel representing organizations directly responsible for preparation and performance of testing and startup. This group provides review and approval of test preparation and performance activities.

b. Test and Startup Program Division a WPPSS division in the Generations Group with respon-sibility for development and implementation of the Test and Startup Program. A Test and Startup Department for each project is organized within this division.

c. Plant Organization a WPPSS division in the Generations Group with responsibility to operate and maintain a Washington Public Power Supply System power plant in compliance with Federal, State, local and owner requirements.

d. Plant Operations Committee (POC) refer to definition in 13.4.1.

e. Startup Superintendent the Test and Startup Department Manager with responsibility for implementation of the Test and Startup Program.

f. Test and Startup Program that program which encompasses the transition from construction to commercial operation and consists of system lineup testing, preoperational testing and startup testing.

14.2-6

WNP-2 AMENDMENT NO- 7 November 1979

g. Test and Stagtup Program Manual the manual that defines generic administrative policy and pro-cedures for the initial testing'and startup of WPPSS nuclear facilities.

h. Test and Startup Instructions the specific in-structions required to implement the Test and Startup Program for'an individual project.

14.2.2.3 Test and Startup Program Division 14.2.2.3.1 General Test and Startup Programs is a division in the Generation Group. Relative to the Prog'ram, the Test and Startup Program Division is responsible for development and administration of plans, policies, and administrative procedures, procurement of test equipment and other test-related resources, and assignment of the Startup Superintendent for the project.

The Test and Startup Program Division organization and its relationship, to other WPPSS departments is shown in Figure

14. 2. 1.

14.2.2.3.2 Responsibilities of Test and Startup Department WNP-2 Test and Startup is a department of the Test and Startup Program Division. The manager of this department, the Startup Superintendent supervises an organization comprised of WPPSS test engineers and test technicians augmented by test personnel from the architect-engineer, the nuclear steam supply system supplier, and others as contractually estab-lished for the project. The Startup Superintendent is respon-sible for the development and implementation of the Test and Startup program for the project. His responsibilities are described in 14.2.2.3.3. The Test and Startup staff organi- )

zation is shown in Figure 14.2-2.

14.2.2.3.3 Test and Startup Department Position Responsibilities 14.2.2.3.3.1 Startup Superintendent

a. Chairman, Test Working Group

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WNP-2 P

AMENDMENT NO. 20 November 1981

b. Develop pl ans, schedules, methods, procedures and data systems for the testing and evaluation of all plant equipment and systems to permit acceptance and licensing.

C ~ Administer and coordinate the testing activities with other organizations involved in the test and startup program.

d 0 Manage and direct assigned test personnel in activities relating to the attainment of test and startup program objectives.

e. Manage and direct assigned test personnel to establish qualitative and quantitative acceptance criteria and develop test procedures to direct and guide performance of testing.

Provide recommendations and effect actions to eliminate equipment or system deficiencies as determined by test and startup program criteria which could adversely affect performance of safety-related functions.

14.2.2.3.3.2 Test Group Supervisor

a. .Supervise the activities of assigned Test Engineers.

b. Review and, where appropriate, approve test pro-cedures, field changes to procedures and test results and make recommendations to the Startup Superintendent.

C ~ Set schedules and priorities for assigned Test Engineers and assist them with problem resolu-tion.

d. With other Test Group Supervisors and the Startup Superintendent, plan and coordinate Startup activities and provide assistance.

e. Advise the Startup Superintendent on all matters concerning testing within their group and, if required, attend TWG meetings for this purpose.

Act for the Startup Superintendent when so delegated.

14.2-8

WNP-2 AMENDMENT NO. 20 November 1981

g. Prepare for and perform testing as required to support the Test and Startup Program.

h. Coordin'ate the identification and documentation of design problems and their resolution.

i. Perform the supervision necessary in the direct preparation of documents required for implemen-tation of the Test and Startup Program.

j. Assign system responsibilities to individual Test Engineers assigned to that group.

14. 2-Sa

BLANK AMENDMENT NO. 7 November 1979

'I 14.2.2.3.3.3 Test Engineers Within the category of Test Engineer, the Test Group Super-visor assumes the lead technical responsibility for the testing within a particular discipline or area. The Test Engineers provide for the routine development and implemen-tation of testing. The. general Test Engineer duties are as follows:

a. Prepare assigned test procedures.

b. Review tests and inspections prepared by others for application to assigned testing responsi-bilities.

c. Provide direction during performance of system and component testing.

d. Ident ify problem areas and recommend actions where deficiencies could adversely affect per-formance of safety related functions or oper-ating efficiency.

14.2.2.4 DELETED 14.2-9

WNP-2 AMENDMENT NO. 29 March 1983 14.2.2.5 Test Working Group (TWG) 14.2. 2.5.1 Purpose of the Test Working Group 4

The purpose of the Test Working Group, a composite of repre-sentatives from organizations directly responsible for pre-paration, performance, and review of Test and Startup Program activities, is to provide a means for a coordinated review of all testing concerns and assuring all obligations to the Test and Startup Program are met by the organizations represented.

The Test Working Group provides review and approval of all activities proposed and the results thereof as appropriate.

All decisions and approvals or recommendations of the Group are signified in the minutes of the meetings. Matters requiring approval by the Test Working Group include, but are not limited to:

a. System lineup procedures

b. Test procedures

c. Changes to test procedures

d. Results of testing 14.2.2.5.2 Membership and Responsibility of the Test Working Group The TWG membership consists of the following representatives:

as long as that member's organization has a direct support function for the current phase of testing or phase for which testing is to be developed.

14. 2-10

WNP-2 AMENDMENT NO. 12 November 1980 The Startup Superintendent is Chairman of the,TWG and is responsible to convene and conduct TWG meetings and achieve agreement from its membership on the administrative and technical content of program activities.

The Operations Superintendent is responsible for providing an operational review of test documents and for submitting safety-related documents to the Plant Operations Committee for review and for communicating the Committee's decisions to the TWG. He provides detailed plant operating procedures and sur-veillance procedures to be used for plant operation and testing during the Test and Startup Program.

The Operations Q.A. representative to the project shall be responsible for review of proposed activities, test procedures and test results per the requirements of the Operational Assurance Program description.

The Project Engineering representative is responsible for obtaining a technical review of proposed activities and test documents by assigned project engineers and for representing Project Management's concern in the Test and Startup Program.

Conditional Members are representative of any organization having responsibility and/or expertise in the area of the TWG meeting agenda. In this situation the representative will be requested to attend the meeting by the TWG chairman.

14.2.2.6 Plant Organization Functions and Responsibilities The plant organization has overall responsibility for the safe and efficient operation of plant systems and equipment, from provisional acceptance through commercial operation including responsibility for maintenance and operational control. Plant organization responsibilities in support'ing the Test and Startup Program are discussed in 14;2.2.7.1 below.

The responsibility of the plant organization representative to the Test .Working Group is as defined in 14.2.2.5.2.

14.2-11

WNP-2'MENDMENT NO. 12 November 1980 14.2.2.7*

WPPSS Support of the Test and Startup Program 14.2.2.7.1 Plant. Organization ln addition to the responsibilities described in 14.2.2.6, the plant operating,'echnical, and maintenance sections provide manpower for development, implementation, and review of testing.

14.2.2.7.1.1 Support During Test and Startup Program Development Assistance during the development of the Test and Startup Program is provided, formally through the. plant organization's

,Test Working Group representative'. Input to test procedures

'nd other testing documentation ky the plant staff assures:

a. That the operational requirements of test pro-cedures are based on the knowledge and experi-ence of the operating staff.

b. That the technical considerations receive the review of the Plant Technical Staff.

c. 'hat important nuclear and 'perational safety considerations receive attention kp the Plant organization.

14.2.2.7.1.2 Support During Testing Detailed review and analysis of test results'will be per-formed by the plant technical section and/or plant operations section where their particular expertise is deemed necessary by the plant representative to the TWG to support approvals of completed tests.

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WNP-2 AMENDMENT NO. 7 November 1979 14.2.2.7.2 Project Division The WNP-2 Project Division is responsible for the performance of the organizations involved in the design, procurement, and construction of generating projects. The Project Division Manager supports the Test and Startup Program by providing and implementing project control systems, project engineering services, and engineering support services.

The NPPSS Project Manager supports the Test and Startup Pro gram by maintaining a high level of current. status information available to the Startup Program Organizations to assure that all startup program scheduling and preparation is based on an accurate assessment of the condition of systems and equipment being readied for testing. The Project Manager provides I liaison with Construction Management for the provision of construction craft support for the implementation of various system lineup and preoperational tests.

14.2.2.7.3 Quality Assurance Division The functions of the Quality Assurance organization during the Test and Startup Program will be to survey ongoing efforts to determine that the controls required by various regulations, guides, and standards are effectively implemented. The acti-vities of the Test Working Group will be monitored to assure that the proper degrees of control for safety related activi-ties are being maintained and that required activities are completed where they are prerequisite to another testing activity.

14.2.2.8 Architect-Engineer Support of the Test and Startup Program Burns and Roe, Inc. is responsible to provide information re-quired to assure timely completion of construction testing and equipment turnover for provisional acceptance. Burns and Roe also provides system-oriented engineers to assist the 14.2-13

WNP-,2 AMENDMENT NO. 7 November 1979 i WPPSS Test and Startup Department, as requested by WPPSS, in the provision of system boundary definitions, a preoperational i

test index prepared by WPPSS and technical direction and/or advice and consultation during system and component testing through preoperational testing.

14.2.2.9 General Electric Company Support of the Test and Startup Program The General Electric Company (GE) is the supplier of the BWR nuclear steam supply system (NSSS) for WNP-2. GE is respon-sible for generic and specific WNP-2 designs and for the supply of the NSSS. During 'the construction phase of the plant cycle the GE Resident Site Manager is responsible for all NSSS equipment disposition. When the testing phase of the project begins, the responsibility of GE-NSSS activities are assigned to Preoperational and Startup Group. The GE Preoperational and Startup staff responsibilities are outlined below.

14.2.2.9.1

't Staff Responsibilities 14.2.2.9.1.1 GE Operations Manager The GE Operations Manager is the senior NSSS vendor repre-sentative onsite at or near official fuel loading, and is the official site spokesman for GE for preoperational and startup testing. He coordinates with the Startup Superintendent for the performance of his duties which are as follows: .

a. reviewing all NSSS test procedures, including changes to test procedures, and test results as a conditional member of TWG.

b. providing technical direction to the station staff;

c. managing the activities of the GE site personnel in providing technical direction to WNP-,2 personnel in the testing and operation of GE supplied systems;

d. providing liaison between the site and the GE San Jose home office to provide rapid and effec-tive solution to problems which cannot be solved onsite; and

e. participating as a conditional member of the Test Work Group when required.

14.2-14

WNP-2 AMENDMENT NO. 7 November 1979 14.2.2.9.1.2 GE Operations Superintendent, The GE Operations,Superintendent is responsible to the GE Operations Manager for supervising the activities of GE Shift Superintendents. He works directly with the WNP-2 Operations Supervisor in providing GE technical direction to the operating organization.

I 14.2.2.9.1.3 GE Shift Superintendents The GE Shift Superintendents provide technical direction to WNP-2 shift personnel in the testing and operation of GE supplied systems. They provide 24-hour per day shift coverage as required beginning with fuel loading. They report to the GE Operations Superintendent.

14.2.2.9.1.4 GE Lead Engineer Startup Test, Design, and Analysis The GE Lead Engineer Startup. Test, Design, and Analysis is responsible to the GE Operations Manager for supervising the GE shift engineers and for verifying core physics parameters and characteristics and documenting that performance of the NSSS and components conform to test acceptance criteria.

He works with the WNP-2 Technical Supervisor to coordinate and effect implementation of the Startup Test Program instru-mentation including special test equipment required to con-firm these acceptance criteria.

14.2.2.10 Qualifications of Personnel Supporting the Test and Startup Program The qualifications described in this section are for those persons having authority to direct testing, review and approve test documentation and results or otherwise have direct influence on the conduct of testing and quality of acquired data. Although other personnel, specifically GE, Burns and Roe, and WPPSS technical specialists, are also involved in these processes, they are under the direction of individuals whose qualifications are described herein and who review and approve all test and startup program activities.

14. 2-15

WNP-2 AMENDMENT NO. 20 November 1981

14. 2. 2. 10. 1 Test and Startup Program Department Personnel Qualif'ications a ~ At the time of appointment to the active posi-tion, the Startup Superintendent shall have ten years of responsible thermal power plant ex-perience such as, but not limited to, managerial, technical, or administrative positions, of which a minimum of three years shall be nuclear power plant experience. A maximum of four years of the remaining seven years of experience may be fulfilled by academic training on a one-to-onein time basis. This academic training shall be engineering or the individual shall have acquired the experience and training normally required for examination by NRC for a senior'perator license whether or not the examination is taken.

Minimum qualifications for Test Group Supervisor are a Bachelor of Science degree in Engineering or related field and five (5) years of applicable

'xperience, at least three of which are in testing or operation of nuclear power generation, propulsion, or similar scale test or production facilities. Related experience may be substi-tuted for academic requirements when the candidate's professional background and level of

'chievement clearly demonstrate capabilities to fill the position. Previous preoperational testing experience is required. A good under-standing of Quality Assurance and regulatory requirements and an ability to effectively com-municate with others are necessities. A demon-strated technical leadership in his d'iscipline and necessary work experience at 'the Senior Test Engineer or equivalent level is evidence of required proficiency.

C ~ Minimum qualifications for a Test Engineer directing preoperational tests are a Bachelor of Science degree in Engineering or related field or a graduate of a technical or vocational school in an Engineering or related field and two years related experience. Related experience above the required minimum may be substituted for academic requirements when the candidate's record for per-formance clearly indicates the ability to fill

14. 2-16

WNP-2 AMENDMENT NO. 20 November 1981 the position without question. A good understanding of enginering principles and the ability to understand new concepts and to effec-tively communicate with others is a necesity.

Minimum requirements for a Test Engineer directing startup tests are a Bachelor of Science degree in Engineering or related field and two years of related experience or, a graduate of a technical or vocational school in an Engineering or related field and three years related experience. Related experience above the required minimum may be substituted for academic requirements when the candidate's record for per-formance clearly indicates the ability to the position without question. A good fill understanding of engineering principles and the ability to understand new concepts and to effec-tively communicate with others is a necessity.

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WNP-2 AMENDMENT NO. 7 November 1979 14.2.2.10.2 Plant Organization Personnel Qualifications Qualifications of the Plant Manager, Operation Superintendent, technical sections engineers, and operations supervision are found in 13. l. 3. 1.

14. 2. 2. 10. 3 DELETED

14. 2. 2. 10. 4 DELETED 14.2.3 TEST PROCEDURES 14.2.3.1 Development of Test Procedures WPPSS Test Procedures are developed by the Test and Startup Department to provide a detailed method to demonstrate the capability of the system to perform its design function under anticipated operating and accident condition.

General Electric Company General Electric Company as supplier of the NSSS provides test program specifications and instructions from which WPPSS prepares the preoperational and initial startup test procedures for systems supplied by GE.

AE and Vendors Technical assistance is provided by Burns and Roe and vendor technical representatives as deemed necessary.

14.2-18

WNP-2 AMENDMENT NO. 7 November 1979 14.2.3.1.1 DELETED 14.2.3.1.2 'Incorporation of Plant Procedures-The following program will be implemented on WNP-2 to utilize and qualify plant operating procedures during testing.

a. Plant Procedures, will have been prepared in at least draft form before preoperational testing begins using the best information currently available from the principal designer and re-sponsible equipment suppliers.

b. Preoperational Test Procedures will resemble plant operating and emergency procedures as nearly as possible.

c. Utilizing the results of preoperational testing, including the use-testing. of plant procedures where practical, the plant procedures will be updated and approved before the startup testing phase. Exceptions to this program will be those approved plant procedures required to be verified during the startup phase.

d. Simultaneous with the updating of Plant Procedures, Startup Test Procedures will be either updated, if already drafted, or developed, utilizing the results of preoperational testing.

14.2-19

-WNP-2 AMENDMENT NO. 7 November 1979 14.2.3.1.3 Format, of Test Procedures k

The minimum content requirements for WNP-2 Preoperational and Startup Test Procedures are specified in the generic WPPSS Test and Startup Program, Manual. The format for WNP-2 test procedures is specified in the WNP-2 Test and Startup Program Manual. The resulting format, and content is described below.

'a ~ Preoperational and Startup Test. Procedure Format

1) Purpose A concise description of the objectives of the test, including such test requirements as component. functions to be checked and testing under normal or simulated 'conditions to verify readiness for system startup and operation, and system tests to confirm that the performance of the system is in compli-ance with all applicable design requirements.

2) Prere uisites Provisions necessary for performance of the test. Conditions that should exist prior to start of the test. Instructions given to identify required operational status of "the plant and interfacing systems, environ-mental conditions, and individual component status requirements, including verification of the following:

Components being tested have been provisionally accepted and open deficiencies will not affect the performance of the test.

3 3 ~ System lineup testing on components included in the test is complete.

3.3.3. ~ Necessary support systems are avail-able.

14.2-20

3) Limits and Precautions Special precautions required for safety of personnel and equipment, or needed to assure a meaningful test and satisfactory performance of testing.

4) S ecial E ui ment A list of special material and equipment for the performance of the test.

5) Procedure A step by step. procedure for performing the test. Plant operating procedures will be utilized whenever practicable for the oper-ation of systems and equipment during test-ing and for returning the system to normal after completion of testing. Abnormal pro-cedures will be utilized as required to supplement normal plant operating procedures.

Data collection will be part of the proce-dure steps.

Restoration Includes those steps necessary to return the system to a normal operating or tagged status. This may include removal of special test instruments, temporary equip-ment, electrical jumpers, valve lineups, etc.

7) Acce tance Criteria The criteria against which the success or failure of the test will be judged must be identified. In some instances, these will be qualitative criteria, given event does or does not, occur. In other cases, quanti-tative values can be designated as accep-tance criteria.

14.2-21

WNP-2 AMENDMENT NO. 12 November 1980

l. All quantitative acceptance criteria s hall include su i table toler ances.

2. A readily apparent correlation should exist enabling a reviewer to cross-ref erence among procedure steps, data and acceptance criteria.

8) References A listing of all material required for the preparation and performance of the test.

This should include piping and instrumen-tation drawings, electrical elementary drawings, vendor instruction manuals, applicable FSAR sections, contract speci-f ications, and applicable codes, standards or guides, and applicable plant procedures.

14 .2.3.2 Review of Test Procedures Each member of the Test Working Group will provide for review of test procedures with respect to that member's organiza-tional area of responsibility. Startup test procedures will be reviewed by the Plant Operations Committee.

Comments submitted by Test Working Group members will be eval-uated by the Test Working Group and the test procedure revised accordingly. After discussion of the resulting ver-sion, the decision to reject, accept or accept with modifica-tion, will be obtained by consensus of the membership of the TWG. In the event the TWG cannot reach a consensus, the Chairman shall provide resolution or a method for resolving the issue to the appropriate division management for review and concurrence.

The results of the Plant Operations Committee review of Startup Test Procedures will be approved by the Plant Manager.

The qualifications of the individuals or organization repre-sentatives reviewing test procedures are described in 14.2.2.10. The qualificatons of POC members are described in 13.1.3.1.

The administrative procedures governing the test procedure review process are contained in .the WNP-2 Test and Startup Program Manual. These procedures cover the mechanism of review and comment resolution, documentation of this review and method of indication of the review status of a test procedure.

14. 2-22

WNP-2 AMENDMENT NO. 12 November 1980 14.2.3.3 Approval of Test Procedures Test procedures will, be approved by the Test Working Group Chairman by means of consensus of the TWG membership after review of the test procedure as described in 14.2.3.2.

Startup test procedures will be approved by the Plant Operating Committee in a similar manner.

Indication of approval of individual test procedures will be evidenced by the signatures of the chairmen of the Test Working Group and Plant Operations Committee, as required.

Evidence of the consensus of these two committees supporting their respective chairmens'ignatures of approval will be contained in the minutes of the groups'eetings.

The administrative procedures governing the exercise of approval of test procedures are contained in the WNP-2 Test and Startup Program Manual.

l4.2.4 CONDUCT OF TEST PROGRAM 14.2.4.1 Administrative Procedures for Preoperational Testing 14.2.4.1.1 Test Performance Authorization A significant period of time may have elapsed between the time a preoperational test procedure was approved and the time a test is to be performed. The test procedure is there-fore reviewed just prior to initiating the test. Any changes in the system since original approval of the test will be thoroughly researched and the test procedureprocedure revised and approved in accordance with 14.2.3.2 and 14.2.3.3. The Startup Superintendent will then approve the test procedure for performance of the test.

14.2.4.1.2 Preoperational Test Prerequisites Approval by the Startup Superintendent to perform a preopera-tional test also requires consideration of the prerequisite testing required to qualify components and systems for opera-tion. In general, completion of the system lineup testing (see 14.2.1.3)'ill qualify the system for preoperational testing. System Lineup testing, as a prerequisite to Preoperational testing, will include:

a. Instrumentation and protective relay checks, including calibration, setpoint adjustments, logic verification and line checks; 14.2-23

b. Component operability checks, including valve stroking, motor rotation, ventilation system balancing, rotating equipment run-in and pipe support inspection and adjustment;

c. Flushing,'ncluding proof flushes, flow instru-mentation response, and pump performance and capacity checks;

d. Electric component and system checks, including breaker trip setpoints;

e. Hydrostatic or pneumatic pressure tests on systems where dynamic testing, such as pump runs, are required to allow performance of pressure tests. Pressure integrity tests are otherwise performed during construction testing.

Verification that system lineup tests have been successfully completed will be contained in an information package which is reviewed by the Startup Program Manager prior to recom-mending turnover of a system or component from a contractor to WPPSS. Verification that the system is actually ready for preoperational testing will be performed as described in 14.2;4.3.

14.2-24

WNP-2 AMENDMENT NO. 7 November 1979 14.2.4.1.3 Conduct of Preoperational Testing

a. Implementation responsibilities for scheduling all tests are assigned to the Startup Super-intendent. The Test Working Group will be kept informed of the scheduled activities.

b. The satisfaction of prerequisites to commence-ment of the test, as indicated in the test procedure, will be verified by the test engineer prior to performance of the test.

c. The assigned test engineer is responsible for directing the performance of each test. Testing is performed in direct coordination between the test engineer and shift supervision.

d. All testing will be conducted in accordance with approved test procedures. If, during the per-formance of a test, it is found that the pro-cedure is unacceptable for some reason, the test engineer can propose changes by use of a "Test Change Notice" (see 14.2.4.4). This provides both documentation of the change and confirmation by the Test Working Group.

e. All test data will be entered on the official copy of the -test procedure.

14.2.4.1.4 Deficiency Reporting Deficiencies or discrepancies identified during testing will be reported individually as described in 14.2.5.2.

Corrective action or satisfactory disposition shall be taken on all deficiencies and discrepancies in equipment and pro-cedures prior to final approval of the preoperational test results. All deficiencies or discrepancies identified during the test, or which have not been resolved upon completion of the test, will be recorded in the official copy of the pre-operational test.

14.2-25

WNP-2 AMENDMENT NO: 7 November 1979

14. 2. 4. 1.5 Equipment Maintenance and Modifications During Preoperation Testing Modifications or repair to safety related systems will be implemented as a result of a formal system of problem and deviation reporting. Disposition of problems requiring mechanical or electrical changes or repairs by Contractors will be implemented by work requests.

a. Startup Problem Reports (SPR), Startup Deficiency Reports (SDR) and Startup Work Requests (SWR) are administered through closed-loop procedural controls to assure resolutions. A completed SPR, SDR and SWR is approved for closure by the Startup Superintendent.

b. Startup Problem Reports (SPR) are used to report design deficiencies and are coordinated by the WPPSS Project, Engineering Division for resolution by the original design organization or qualified alternate. The SPR's are reviewed by Project Engineering and a Project Engineering Directive (PED) is issued to define plant modi-fications or changes that are required. A Start-up Work Request (SWR) is then issued to perform the plant modification by Contractor personnel or a Startup Deficiency Report is issued to defer the work or have personnel.

it performed by Startup c ~ Startup Deficiency Reports (SDR) are used to report and track non-design related deficiencies.

If required, an SWR will be issued to perform the repair work to resolve the non-design related deficiency, by Contractor personnel. Work accomplished by Startup personnel can be accom-plished by the SDR without issuing an SWR.

d. Retest requirements will be identified on the SWR or SDR and attached to, or referenced by work request number in test files.

e. Startup Problem and Deficiency Reports, Startup Work Requests, design change documentation, re-test results, and procurement records for safety related systems will be filed in assembled packages or with appropriate cross referencing for retrievability.

14. 2-26

WNP-2 AMENDMENT NO- 7 November 1979 14.2.4. 1.6 Preoperational Test Summary Upon completion of the preoperational test, the test engineer will prepare a test report which includes a summary of the conduct. of the test, and evaluation of the test results with reference to-the acceptance criteria, and a description of problems encountered and corrective actions taken or proposed.

This report will be attached to the official copy of the test.

14.2.4.1.7 Evaluation of Preoperational Test Data Upon completion of the test, a copy of the official test procedure, data, the test summary, and other applicable attachments will be transmitted to each member of the Test Working Group responsible for review.

14.2.4.1.8 Preoperational Test Records The Startup Superintendent will maintain all official test records (the copy of the test procedure containing the ori-ginal test data and signatures and all attachments-) untilof of the test program. See 14.2.6 for details 'ompletion the test records handling and retention program.

14.2.4.2 Administrative Procedures for Startup Testing 14.2-26a

WNP-2 WNP-2 .AMENDMENT NO. 7 November 1979 14.2.4.2.1 Plant Operation During Startup Testing During initial startup tests and operations, the plant pro-cedures are followed except. as specifically modified by approved test procedures. In addition, special safety pre-cautions and limitations are included in the test procedures.

Approved test procedures will be used to control test condi-tions outside of Plant Technical Specification Limits where allowed for test. purposes.

Certain individual tests or power escalations may require authorization by both the Plant Operating Committee and the Plant Manager immediately prior to implementation and will be so identified in the applicable test procedure.

The final authority to start or continue a test is the respon-sibility of the shift supervisor after all previous approvals have been exercised. Testing is performed in direct coor-dination between the-test engineer and shift supervisor.

14.2.4.2.2 Startup Test Scheduling and Sequencing Scheduling and sequencing of testing during startup is per-formed under the direction of the Plant Manager.

The startup or power escalation test sequence is described in terms of individual test, evolutions and specific power plateaus due to interfaces with other simultaneous tests, requirements for continuous data review and plant administra-tive requirements for authorization to proceed or continue.

The test sequence identifies hold points for data review and authorization to proceed and establishes the general plant conditions for each group of tests.

14.2.4.2.3 Startup Test Performance Before starting each test, the assigned test engineer will review the test procedure to assure 'that prerequisite acti-vities or conditions have been satisfied as described in 14.2.4.3.

The test will be formed stopped or curtailed if it cannot be per-safely or in accordance with the approved test pro-cedure. Required test procedure deviations or changes may be effected in accordance with a "Test Change Notice" as described in 14.2.4.4.

14.2-27

, WNP ANENDNENT NO. 12 November 1980 Should apparent deviations of test results from performance requirements or acceptance criteria be revealed, or should other apparent anomalies develop, the plant will be placed in a safe condition and relevant test data reviewed by the test engineer and Shif t Supervisor. Xf the apparent discrepancy or anomaly is substantiated, the situation will be reviewed by the Plant Operations Committee to ascertain if a plant safety question is involved. Control of any identified non-conformance or noncompliance will be in accordance with the plant administrative procedures.

Evaluation of the effect of the discrepancy or anomaly on plant safety will be performed at the appropriate level of review and appropri ate corrective actions will be taken before resumption of the test or test conditions at which the pro-blem was revealed.

At the completion of an entire test procedure, the test engineer will assemble all of the data and supporting infor-mation, nonconformance documentation and test results evalu-ations for review ky the Plant Operating Committee. Any data reduction or analysis required will be done as soon after the data is available as is practical so that the results of the analysis may be included in the completed test package.

Test. records will be maintained as described in 14.2.6.

14.2.4.3 Control of Test Prerequisites Conditions and activities prerequisite to a given test wilg be identified in the applicable test procedure. Prior to commencement of the particular test, the test engineer will verify that the identified prerequisites, as described below, have been satisfied. The verifications will be recorded and retained as part of the test record.

The test engineer will verify that:

a. The test procedure has been approved by the appropriate committee and Plant Manager or Startup Superintendent as required. The test procedure is compatible with the latest versions of material referenced in the test procedure.

14.2-28

WNP-2 AMENDMENT NO. 12 November 1980

b. The official working copy of the test procedure is identical to that contained in the master file;. including the latest TWG/POC approved revi-sions or test procedure field changes (see 14.2.4.4) .

c. Prerequisite tests have been completed. If TWG and/or Plant Superintendent approval of the completed test is also a prerequisite that approval will have been obtained.

d. The test procedure has been made available for shift operator review and familiarization. Oper-ator support has been scheduled, as necessary.

e. Test equipment is available or in place as required. Cali br ation or other readiness requirements have been completed. System instru-mentation to be used in the test has been cali-brated within the required time period established for surveillance testing and/or pre-ventative maintenance.

f. Test and operating personnel involved .in the performance of the test have been briefed immediately prior to starting the test.

14.2.4.4 Modification of Test Procedures During Testing The Test and Startup Program Manual provides a means of con-trolling modifications to TWG-approved test procedures during testing. This administrative procedure, contained in the WNP-2 Test and Startup Program Manual, applies to changes made to an approved test procedure during preoperational and startup testing. The procedure does not apply to revisions made during the preparation of test procedures.

The procedure provides control of revisions which change the intent or the acceptance criteria of the test procedure.

The required changes, when identif ied by the responsible test engineer, are described on a special form (Test Change Notice/Procedure Change Notice) which identif ies the af fected test procedure or plant procedure, justifies the change, and contains spaces for the appropriate approvals.

A Test Change Notice for a Preoperational test is reviewed by the TWG and approved by the Startup Superintendent, TWG Chairman.

14.2-29

WNP-2. AMENDMENT NO 12 November 1980 The Test Change Notice for a Startup Test is approved by the POC and Plant Manager prior to implementation.

The Test Change Notice forms a permanent part of the test reco'rde 14.2.5 REVIEWS EVALUATION AND APPROVAL OF TEST RESULTS 14.2.5.1 Control of Test Results Review The individuals responsible for reviewing the results of particular tests will be designated ky the Startup Superin-tendent. These reviews will be obtained through TWG members in accordance with their represented areas of responsibility.

TWG members will provide names of individuals in their repre~

sented organizations who meet the requirements of Regulatory Guide 1.58 November 1973, for evaluation of inspection and test results.

Based on the recommendations of the qualified reviewers, the completed test will be approved ta'he TWG. POC review and Plant Superintendent approval of startup test results is required.

14.2.5.2 Design Organization Participation in Problem Resolution Failures of tests to meet acceptance criteria and other problems discovered in the course of testing will be docu-mented as deficiencies in accordance with the requirements of the Test and Startup Program Manual. Reports of such deficiencies will indicate the parties or organizations deemed responsible for providing an acceptable resolution of the deficiency. The responsible organization wild. be re-quested to provide a resolution of the defined problem.

Documentation of the final resolution will include the rec-ommendation of the responsible organization and a description of the measures implemented in accordance with that recommen-dation. Design problems will require resolution by the appropriate WPPSS Technical Division Department, Project Engineering, Plant Technical Staff or original design organi-zation, depending upon the technical nature of the problem.

14.2-30

WNP-2 AMENDMENT NO. 20 November 1981 14.2.5.3 Results Analysis Prerequisites to Continuation of Startup Testing The Plant Operating Committee will establish preiequisites for various tests, test conditions and test phases insubse-con-sideration of system or component qualification for quent testing.

The control of prerequisites to an individual test will be as described in 14.2.4.3.

The POC will, also require an evaluation of the data acquired during a particular test phase or plateau before approving commencement of the following phase or plateau. The items to be considered in this evaluation will include, but not be limited to, the following:

a. The need for additional testing or retesting to improve assurance that a particular system or component will perform as required in subsequent testing, especially under more demanding condi-tions such as higher power levels;

b. The need for analysis of certain data to qualify measured variables or parameters for use in subsequent measurements;

c. The completeness of testing up to the point in question as evidenced by the documentation of the completed tests;

d. The need for specific reviews and approvals of particular sets of data to satisfy the above.

l4.2.6 TEST RECORDS 14.2.6.1 General The Test and Startup Program Manual contains a generic pro-cedure regarding filing and record keeping to be applied to testing documentation. This procedure is intended to assure compliance of WPPSS project startup programs with the appli-cable provisions of American National Standard N45.2.9-1974 14.2-31

WNP-2 AMENDMENT NO. 7 November 1979 "Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants," as required by Regulatory Guide 1.88, Revision 1, December 1975.

The following sections describe the provisions of the afore-mentioned procedure, which will be contained in specific detail in the WNP-2 Test and Startup Instructions.

14.2.6.2 Test Record Re'sponsibilities The Startup Superintendent is responsible for identifying the responsibilities, controls and requirements for estab-lishing and implementing a test and startup program filing and record keeping system, in accordance with 10CFR50 Appendix B, ANSI N45.2.9 and the WPPSS Quality Assurance Program Manual. The Startup Superintendent will ensure that adequate procedures are prepared and maintained within the Test and Startup Instructions. The Startup Superintendent will ensure that trained and qualified personnel maintain the Test and Startup Program files.

14.2.6.3 Types of Documents and Records Requiring Test Record File Retention Documentation and records that will be maintained within test and startup program files are:

a. Test and startup program records as specified by ANSI N45.2.9.

b. All records and documents as specified by the Test and Startup Program and Instruction Manuals.

Other records, documents, correspondence, etc., may, be main-tained at the discretion and approval of the Startup Program Manager, provided their. access requirements do not compromise the security of the mandatory files.

14.2.7 CONFORMANCE OF TEST .PROGRAMS WITH REGULATORY GUIDES 14.2.7.1 Conformance with Regulatory Guide 1.68 The WNP-2 Test and Startup Program conforms to the requirements of Regulatory Guide 1.68 Rev. 0, "Preoperational and Initial Startup Test Programs for Water-Cooled Power Reactors,"

14.2-32

WNP-2 AMENDMENT NO. 26 July 1982 except where specifically noted otherwise. This Regulatory Guide has been reviewed by the Supply System for applicability of individual items 'in the guide to WNP-2 and its systems.

The applicability to this plant has determined the nature and scope of testing to be performed. Actual exceptions to the testing required by this guide have been specifically addressed and are discussed in 14.2.7.2. Areas where the guide does not apply are not considered to be exceptions.

14.2.7.2 Exceptions to Regulatory Guide 1.68 The exceptions to Regulatory Guide 1.68 are listed below with an explanation of the justification for the exception.

a. Exception to Format of Test Procedures The iormat of the test procedures is different from that found in Appendix C of Regulatory Guide 1.68, but the difference is not considered an exception to the regulatory guide since the guide specifies required elements of a test procedure while merely implying a format.

b. Refer to C.2 for a delineation of specific excep-tions to the requirements of Regulatory Guide 1.68.

14.2.7.3 Conformance with or Exceptions to Regulatory Guides other than 1.68

a. Regulatory Guide 1.70, "Standard Format and Content of the Safety Analysis Reports for Nuclear Power Plants" will be complied with for the section which pertains to the Test and

'Startup Program.

b. Regulatory Guide 1.33, "Quality Assurance Program Requirements" will be complied with in "Operational Quality Assurance Report" section 17.2 of the FSAR for the Test and Startup Program.

c. All other regulatory guides pertaining to indiv-idual tests will be complied with unless noted otherwise in 14.2.12.

14.2-33

WNP-2 AMENDMENT NO. 7 November 1979

d. Regulatory Guide 1.58 "Qualifications of Nuclear Power Plant Xnspection Examination and Testing Personnel".

WPPSS Test and Startup personnel involved in testing meet the requirements of Regulatory Guide 1.58.

14. 2-34

WNP-2 AMENDMENT NO. 7 November 1979 14.2.8 UTILIZATION OF REACTOR OPERATING AND TESTING EXPERIENCES IN THE'EVELOPMENT OF THE TEST PROGRAM As a matter of Supply System policy, a continuous program of review of reactor operating experience is coordinated by the Operations Division of WPPSS. The sources of information re-viewed in compliance with this policy are NRC information bulletins, operating experience reports, preoperational test summaries and startup reports from other plants, administra-tive and test procedures. from other plants'tartup programs, personal contacts with other nuclear plant licensees or appli-cants, and additional information supplied by WPPSS Technical and Operations Division's members. All available sources are utilized; relevance to particular WPPSS Nuclear projects is determined in the review process.

The information is reviewed by WNP-2 Startup Program personnel for applicability,to- the WNP-2 test and startup program, for incorporation into test procedures or for consideration in the administrative control of testing.

14.2.9 TRIAL USE OF PLANT OPERATING AND EMERGENCY PROCEDURES 14.2-35

To the extent practical throughout the preoperational and initial startup test program, test procedures utilize operating, emergency, and abnormal procedures where applicable in the performance of tests. The use of these procedures is intended to do the following:

(1) prove the specific procedure or illustrate changes which may be required, (2) provide training of plant personnel in the use of these procedures, and (3) increase the level of knowledge of plant per-sonnel on the systems being tested.

Test procedures may use these operating, emergency, and ab-normal procedures in several ways: the test procedure may reference the procedure directly; the test procedure may extract a series of steps from the procedure; the test pro-cedure may use a combination of the first. two methods.

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 is conducted in accor-dance with written procedures after all prerequisite tests are satisfactorily completed and an operating license has been issued. Prior to approving fuel loading, the plant must be verified to load fuel. This verification is accomplished by the following steps, which are performed at the completion of preoperational testi'ng.

14.2.10.1.1 Loss of Power Demonstration Standby Core Cooling Required This test demonstrates the capability of each Emergency Diesel Generator to start automatically and assumes all of its emergency core cooling loads in a loss of normal auxiliary power.

14.2.10.1.2 Cold Functional Testing The cold, functional testing defined here is an integrated system operation of various plant systems that can be 14.2-36

AMENDMENT NO. 7 WNP-2 November 1979 operated as systems prior to fuel loading. The intent is to observe any unexpected operational problems from either an equipment or a procedural source and to provide an opportunity for operator familiarizations with the system-operating pro-cedures under operating conditions.

Some of the cold functional testing will be accomplished, during the preoperational test program. For example, integrated and simultaneous operation of the following systems may take place during the flush of the total system: Condensate System, Condensate Demineralizer System, LPCI System, Core Spray System, RWCU System, Service Water System, CCW System, and others. As required, additional integrated systems perfor-mance will be demonstrated prior to fuel loading.

14.2.10.1.3 Routine Surveillance Testing Because of the interval between completion of a preoperational test on a system and the requirement for that system to be operated may be of considerable length, a number of routine surveillance tests must be performed prior to fuel loading and must be repeated on a routine basis. The Technical Specifications (Chapter 16) detail the test frequency. In general, this Surveillance Test Piogram (specified in the Technical Specifications) is instituted prior to fuel loading by the plant operating staff.

14.2.10.1.4 Master Startup Checklist A detailed list of items that must be complete, 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 com-pletion just prior to the final approvals for fuel loading and at, each significant new step such as heat up, opening MSIV's and power operation.

14.2.10. 1.5 Initial Fuel Loading Fuel loading requires the movement of the full core complement of assemblies from 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 shutdown margin and subcritical 14.2-37

WNP-2 AMENDMENT NO. 7 November 1979 checks are made at predetermined intervals throughout the loading, thus ensuring safe loading increments. Specially sensitive in-vessel neutron monitors that are maintained at the loading face as loading progresses serve to provide indication for the shutdown margin measurements, and also to allow the recording of the core flux level as each assembly is added. A complete check is made of the fully loaded core to ascertain that all assemblies are properly installed, correctly oriented and are occupying their designated posi-tions.

14.2.10.1.6 Zero Power Level Tests At this point in the program, a number of tests are conducted which 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 fuel is loaded, and to establish base and background levels, which will be re-quired to facilitate later analysis and instrument calibra-tions. Plant and site radiation surveys are made at specific locations for later comparison with the values obtained at the subsequent operating power levels. Shutdown margin checks are repeated for the fully loaded'ore, and criticality is achieved with each of the two prescribed rod sequences in turn, the data being recorded for each rod withdrawn. Each rod drive is subjected to scram and performance testing. The initial setting of the Intermediate Range Monitors (IRMs) is at max 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 14.2.10.1s5 and. 14.2.10.1.6) and further checks are made of coolant chemistry together with radiation surveys at. the selected plant locations. All CRDs are scram-timed at rated temperature and pressure, with

,selected drives timed at two intermediate reactor pressures and for different accumulator pressures: The process computer

-checkout continues as more process variables become available for input. The RCIC System will undergo controlled starts at low reactor pressure and at rated conditions, with testing in the gnick-start mode at 150 and 1000 psig. Correlations 14.2-38

WNP-2 AMENDMENT NO 29 March 1983 are obtained 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 expansion are recorded for comparison with design data.

14.2.10.3 Power Testing From 25 Percent to LOO Percent of Rated Output The Power Test Phase comprises the following tests, many of are repeated several ti'mes at the different test levels; 'hich consequently, reference should be made to Table 14.2-4 for the probable order of execution for the full series. While a certain basic order of testing is maintained relative to power ascension, there is,-nevertheless, considerable flexibility in the test sequence at a particular power level which may be used whenever it becomes operationally expedient.

instance, however, is nuclear safety compromised.

In no (1) Coolant chemistry tests and radiation surveys are made at each principal test level in order to preserve a safe and efficient power increase.

(2) Sel cted CRDs are scram-timed at various power levels to provide a correlation with the initial data'3)

The effect of control rod movement on other parameters (e.g., electrical output, steam flow, and neutron flux level) is examined for different power conditions.

(4) Following the first reasonable, accurate heat balance (25 percent power) the APRMs ate calibrated and IRMs are reset if necessary.

(5) At each major power level (25 percent, 60 percent, and 100 percent), the LPRMs are calibrated.

(6) The APRMs are calibrated initially at each new power level and following LPRM calibration.

14. 2-39

WNP-2 AMENDMENT NO. 20 November 1981 Completion of the process computer checkout is made for all variables, and the various options are compared with hand calculations as soon as significant power levels are available.

(8) Further tests of the RCIC are made with and without injection into the reactor pressure vessel (RPV).

(9) Collection of data from the system expansion tests is completed for those piping systems which had not previousl'y reached full operating temperatures.

(10) The axial and radial power profiles are explored fully by means of the TIP System at represen-tative power levels during the power ascension.

(11) Core performance evaluations are made at all test points above the ten percent power level and for selected flow transient conditions; the work involves the determination of core thermal power, maximum fuel rod surface heat flux, the Minimum Critical Power Ratio (MCPR), and other thermal parameters.

(12) Overall plant stability in relation to minor per-turbations is shown by the following group of tests which are made at selected test points:

a. Core power-void mode response

b. Pressure regulator setpoint change

c. Water level setpoint change

d. Turbine valve surveillance

e. Recirculation flow setpoint change For the first of these tests, a centrally located control rod is moved and the flux response is noted on a selected LPRM chamber. The next two tests require that the changes made should approximate as closely as possible a step change in demand, while for the next test the turbine stop, control and bypass valves are opened to verify stability and power 14.2-40

WNP-2 AMENDMENT NO. 7 November 1979 level for surveillance testing. The remaining test is per-formed to properly adjust the control loop of the recircu-lation system. For all of these tests the plant performance is monitored by recording the transient behavior of numerous process variables, the one of principal.interestbeing neutron flux. Other imposed transients are produced by step changes in demand core flow, partial loss of a feedwater heating and simulating failure of the operating pressure regulator to permit takeover by the backup regulator. Table 14.2-3 indicates the power and flow levels at which all these stability tests are performed.

(13) The category of major plant transients includes full closure of all the main steam isolation valves, fast closure of turbine-generator control valves, fast closure of turbine-generator stop valves, loss of the main generator and offsite power, tripping a feedwater pump and several trips of the recirculation pumps. The plant transient behavior is recorded for each test and the results may be compared with the acceptance criteria and the predicted design performance. Table 14.2-2 shows the operating test conditions for all the proposed major transients.

(14) A test is made of the relief valves in which leaktightness and general operability are demon-strated.

(15) At all major power levels the jet pump flow instrumentation is calibrated.

(16) The as-built characteristics of the recirculation system are investigated as soon as operating con-ditions permit full core flow.

(17) The local control loop performance, based on the drive pump, jet pumps and control equipment is checked.

14.2.11 TEST PROGRAM SCHEDULE test program schedule for preoperational and startup The tests are indicated on Table 14.2-4 and Figure 14.2-4. These schedules are preliminary and will be adjusted to consider actual construction and testing progress; they are included to provide general information but are not considered to be identical to the schedules in use during the startup program.

The test procedures will be made available for 'review at least 60 days prior to the test date or fuel load.

14.2-41

WNP-2 AMENDMENT NO. 12 November 1980 14.2.l2 . INDIVIDUALTEST DESCRIPTIONS 14.2.l2.l Preoperational Test Procedures The following general descriptions are the specific objectives of each preoperational test. During the final construction phase, it may be necessary to modify the preoperational test methods as operating and preoperational test procedures are developed. Consequently, methods described in the following descriptions are general, not specific.

Specific acceptance criteria for each preoperational test are in accordance with the detailed system and equipment specifi-cations for equipment in those systems. The tests demonstrate that the installed equipment and systems perform within the limits of these specifications.

In addition to the prerequisites listed on each of the fol-lowing preoperational tests there will be electrical poyer available to each of the systems.

Table 14.2-1 lists the preoperational test anticipated for this 'facility.

14.2.12.l.l Reactor Feedwater System Preoperational Test

a. ~Pur ose To verify the operation of the Reactor Feedwater (RFW) System, including pumps, valves, turbines, turbine auxiliaries, turbine control systems.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The condensate system, control air system and service water system must have a readiness verification.

c. General Test Methods and Acce tance Criteria The performance of the Reactor Feedwater (RFW)

System is verified within the limitations of the auxiliary steam supply by the demonstration of the proper operation of the following:

(1) Valves and related controls, interlocks and position indicators 14.2-42

WNP-2 AMENDMENT NO. 12 November 1980

2. Reactor feedwater pumps, turbines and auxiliaries

3. Control logic

4. Annunciators and protective devices 14.2.12.1.2 Condensate System Preoperational Test

a. ~Pus ose To verify the operation of the Condensate System, including pumps, valves and control systems.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The condenser, condensate filter demineralizers, feedwater, and control air systems are capable of supporting this test as necessary.

c. General Test Methods and Acce tance Criteria The performance of the Condensate System is verified by the demonstration of the proper operation of the following:

(1) Valves and related controls, interlocks and position indicators.

(2) Condensate pumps, condensate booster pumps and auxiliaries.

(3) Control logic.

(4) Annunciators and protective devices.

14.2.12.1.3 Fire Protection System Preoperational Test

a. ~Pus ose To verify the operation of the Fire Protection System, including the diesel engine, pumps, valves, detection and alarm circuits and control and instrumentation circuits. To verify the location and status of all portable equipment.

14.2-43

WNP-2 'MENDMENT NO.

November 1980.

12 The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Star tup Superintendent has approved the initiation of testing. The circulating water system, control and service air system, and electrical distribution system are available to support operation.

c ~ General Test Methods and Acce tance Criteria Verification of the Fire Protection System cap-ability is demonstrated by the proper integrated operation of the following:

(1) Diesel engine and pump operation and related 1

control and logic.

(2) Fire alarm and detection circuits.

(3) Fire control panel in the Main Control Room.

(4) Deluge, wet pipe and pre-action sprinkler systems.

(5 ) C ar bon dioxide and H alon sys tems.

In addition, portable equipment and hose station cap abili ty will be ver ified.

14.2.12.1.4 Reactor Water Cleanup System Preoperational Test

a. ~Pur ose To verify the operation of the Reactor Water Cleanup (RWCU) System, including pumps, valves, and filter/demineralizer equipment.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Filter aid, and anion and cation resin should be available. Closed Cooling Water (CCW) System and instrument air system must have readiness verification.

14.2-43 a

AMENDMENT NO. 7 WNP-2 November 1979

c. General Test Methods and Acce tance Criteria Verification of the RWCU System capability is demonstrated by the proper integrated operation of the following:

(1) Drain flow regulator flow interlocks (2) System isolation and logic (3) Valve-operating sequence (4) Pump operation and related control and logic 14.2-43b

WNP-2 AMENDMENT NO. 12 November 1980 (5) Annunciators ~ y (6) Filter/Demineralizer System Operation l4.2.l2.1.5 Standby Liquid Control System Preoperational Test a0 P~ur ose To verify the operation of the Standby Liquid Control (SLC) System including pumps, tanks, control, logic, and instrumentation.

b. Prere'isites The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Star tup Superintendent has approved the initiation of testing. Valves should be pre-viously bench tested and other precautions rela-tive to positive displacement pumps taken. The reactor vessel should be available for injecting demineralized water.

c ~ General Test Methods and Acce tance Criteria Verification of the SLC System capability is demonstrated by the proper integrated operations of the following:

(1) SLC System tank level instrumentation (2) Heaters (3) Alarms and logic (4 ) Relief v alves (5) Pumps and related controls and logic (6) Flow testing with different flow paths l4.2.12.1.6 Nuclear Boiler System Preoperational Test 14.2-44

WNP-2 AMENDMENT NO. 12 November 1980

a. P~ur ose To verify'proper operation of the Nuclear Boiler System, including safety/relief valves and re-lated controls and logic.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Verify that all safety/relief valves have been previously bench tested.

c. General Test Methods and Acce tance Criteria Functional and capacity tests of safety/relief valves are not performed; verification of the Nuclear Steam Supply System capability is demon-s tr ated by the proper integr ated oper ation of the following:

(l) System valves and related sensors and logic (2) Vacuum breaker in relief valve discharge lines (3) Automatic isolation function of reactor water sample isolation valves (4) Isolation and leak detection systems (5) Automatic depressurization system logic (6) RV Actuators'ccumulator capacity .test (7) Safety/relief valves air piston operation (8) Reactor head seal leak detection

'(9) Alarms and annunciators 14.2-45

WNP-2 AMENDMENT NO. 12 November 1980 14.2.l2.1.7 Residual Heat Removal System Preoperational Test

a. ~Pur ose To verify the operation of the Residual Heat Removal (RHR) System under its various modes of operation: Low Pressure Coolant Injection (LPCI), shutdown cooling and vessel head spray, containment spray, suppression pool water cooling, and steam condensing.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the S t ar tup Superintendent has approved the initiation of testing. The RHR service water system must have readiness verification. The reactor vessel and recirculation loops shall be i nt act and capable of receiving water.

c. General Test Methods and Acce tance Criteria Verification of the RHR System capability is demons tr ated by the proper integr ated oper ation of the following:

(1) System isolation valve control and logic tests (2) RHR and RHR service water pump and motor operation, controls and related logic features (3) Automatic LPCI initiat'ion logic (4) Verification of all flow paths. The time from, initiation signal to full flow should be similarly verified.

(5) Alarms and annunci ators 14.2-46

WNP-2 AMENDMENT NO ~ 12 November 1980 14.2.12.1.8 Reactor Core Isolation Cooling System Preoper at ion al Tes t

a. P~ur oae To verify the operation of the Reactor Core Isolation Cooling (RCIC) System inc3,uding tur-bine, pump, valves, instrumentation and control.

The System Lineup Tes ts have been comple ted and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The turbine, disconnected from the pump shall be tested. The turbine instruction manual shall be reviewed in detail in order that precautions relative to turbine opera-tion are followed. Then the system shall be tested within the capability of a temporary steam supply with the pump coupled to the turbine.

c. General Test Methods and Acce tance Criteria Verification of system capability is demonstrated by the proper integrated operation of the follow-ing:

(1) All valves and related controls, interlocks, and indicators (2) Manual and automatic initiation (3) Automatic isolation, including leak detec-tion system logic (4) Turbine speed control, trip, mode selection, and test mode (5) Barometric condenser condensate pump, and v acuum pump controls (6) Flow path verif ication (7) Annunciators 14.2-47

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.1.9 Reactor Recirculation System and Control Preoperational Test

a. P~ur use To verify the operation of the Reactor Recircu-lation System, including pumps, and their associated motors, valves, instrumentation, and controls. The rated conditions tests will be conducted during the startup testing program.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The CCW System must receive readiness verification. All required testing of equipment up to the operation of the recirculation pump has been completed, including recirculation pump motor (uncoupled) and all control loops.

c. General Test Methods and Acce tance-Criteria After prerequisite testing, verification of system capability is demonstrated by the proper integrated operation of the following.

(1) System valves (2) Logic and interlocks (3) Recirculation pumps,. valves, and related controls and interlocks (4) Annunciators (5) LFMG set 14.2-48

AMENDMENT NO. 12 November 1980 14.2.12.1.10 Reactor Manual Control System Preoperation Test

a. P~ur ose To verify the operation of the Reactor Manual Control System (RMCS ), including relays, control circuitry, switches and indicating lights, and control valves.

The System Lineup Tests have been completed and the TNG has reviewed and approved .the procedure and the Startup Superintendent has approved the initiation of testing. Control rod drive (CRD) pump will not be operational during this test.

c. General T'est Methods and Acce tance Criteria Verification of RMCS capability is demonstrated by the proper integrated operation of the following:

(1) Rod blocks, alarms, and interlocks for all modes of the reactor mode switch (2) Rod position information system

'3) Rod drift alarm circuit (4) Rod directional control valve time sequence for insert and withdraw commands 14.2.12.1.11 Control Rod Drive Hydraulic System Preoperational Test

a. ~Pur ose I

To verify the operation of the CRD Hydraulic System, including CRD mechanisms, hydraulic control units, hydraulic power supply, instru-mentation, and controls.

14.2-49

WNP-2 AMENDMENT NO. 12 November 1980 The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the S t ar tup Superintendent has approved the initiation of testing. The CRD Manual Control SystemPreoperational Test must be completed on associated CRD's. The CCW System and instrument air system must receive readiness verification.

/

c~ General Test Methods and Acce tance Criteria Verification of CRD System capability is demon-strated .by the proper integrated operation of the following:

(1) Logic and interlocks e

(2) CRD pumps and related controls and interlocks (3) Flow controller, pressure control valves, and stabilizer valves (4) Scram discharge level switches, and CRD position indication, alar'ms, and interlocks (5) CRDs functional testing including latching and position indication (6) Scram testing of control rods at atmosph'eric pressure (7) Annunciators 14.2.12.1.12 Fuel Handling and Vessel Servicing Equipment Preoperational Test

a. P~ur ose To verify the operation of the fuel handling and vessel servicing equipment, including tools used in the servicing of control rods, fuel,assem-blies, local power range monitors (LPRM's) and dry tubes, and vacuum cleaning equipment.

WNP-2 AMENDMENT NO. 12 November 1980 The System Lineup Tests have been completed.and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Additionally, the refueling platform, fuel preparation machine, and fuel racks must be installed and operational; all slings and lifting devices must be certified at their design load, at least by the vendor.

c. General Test Methods and Acce tance Criteria Verification of th'e fuel handling and vessel servicing equipment is demonstrated by dry operation of the following equipment:

( l) Cell disassembly tools (2) Channel replacement tools

~

(3) Instrument handling tools (4) Vacuum cleaning equipment (5) Interlocks and logic associated with the refueling and service platform are verified (6) Proper operation of refueling and service platforms are verified l4.2.12.1.13 Low Pressure Core Spray System Preoperational Test

a. ~Puu use To verify the operation of the low pressure core spray system, including spray pumps, sparger ring, spray nozzles, controls, valves, and i ns trument ation.

e The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The reactor vessel must be available and ready to receive water.

14.2-51

AMENDMENT NO. 12 November 1980

c. General Test Methods and Acce tance Criteria Verification of low pressure core spray system capability is demonstrated by the proper inte-grated operation of the following:

(1) Logic and interlocks (2) Low Pressure Core Spray system pumps, including auto initiation (3) Flow path verification, including deter-mination of system hydraulic performance to

'verify proper sizing of restricting orifice in LPCS discharge line to vessel, see 6.3.2.2.3.

(4) Annunciators (5) The time for initiation signal to full flow should be verified (6) Photographs to prove acceptability of core spray patterns 14.2.12.1.14 High Pressure Core Spray System Preoperational Test 0

a. ~Pur oae To verify the operation of the High Pressure Core Spray (HPCS) System, including diesel generator and related auxiliary equipment, pumps, valves, instrumentation and control.

The System Lineup Tests hav'e been completed and the TNG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The HPCS diesel generator must be installed and be operational.

c. General Test Methods and Acce tance Criteria Verification of HPCS System capability is demon-s tr ated by the proper integr ated oper ation of the following:

14.2-52

WNP-2 AMENDMENT NO. 12 November 1980 (1) Valve controls and interlocks (2) HPCS electrical system tests, including DC and AC (3) HPCS diesel generator functional tests, including starting, rated load, load re-jection (4) Pump and motor tests with normal power supply and with diesel generator (5) HPCS flow path and flow rate verif ication (6) Annunciators (7) The time from initiation signal to full flow should be verified (8) Photographs to prove acceptability of HPCS spray pattern 14.2.12.1.15 Fuel Pool Cooling and Cleanup System Preoperational Test

a. ~Pur use To verify the operation of the fuel pool cooling and cleanup system including the pumps, heat e xchangers, controls, v alves and instrumentation.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The instrument air, ser-vice air, fuel pool emergency makeup, service water, and RHR systems must be available.

c. General Test Methods and Acce tance Criteria Verification of the fuel pool system capability is demonstrated by the integrated operation of the following:

14.2-53

WNP-2 .'MENDMENT NO.

1'2'ovember'980'1)

Logic and interlocks (2) Interconnection to RHR system (3) Pump operation and related controls (4) Cleanup subsystem operation (5) Annunciators 14.2.12.1.16 Leak Detection System Preoperational Test a'. ~Pur ose To summarize the test requirements and verify the leak detection test data for each of the nuclear systems.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The prerequisites are included in the preoperational test specifica-tions for each of the nuclear systems listed below.

c. General Test Methods and Acce tance Criteria As an integral part of each of the following system preparational tests, the nuclear systems leak detection is verified by the proper opera-tion of the leak detection features of the following nuclear systems:

(1) Feedwater Control System (2) RWCU System (3) NSSS (4) RHR System (5) RCIC System (6) Recirculation System (7) Radwaste System

14. 2-54

WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.1.17 Liquid and Solid Radwaste System Preoperational Test

a. ~Pur oae To verify that the radioactive waste system will perform its design functions of processing liquid and solid radioactive wastes.

The System Lineup Tests have been completed and the TNG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing.

c. General Test Methods and Acce tance Criteria Testing will demonstrate that the pumps, tanks, controls and valves including automatic isola-tion, diversion and protective features and func-instrumentation and alarms will operate and tion in accordance with design requirements.

14.2-54a

BLMK WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.1.18 Reactor Protection System Preoperational Test

a. ~Pur oee To verify the proper operation of the Reactor Protection System (RPS), including sensor logic and their respective scram relays, scram reset time delay, the annunciators, and motor-generator set power supply.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing.

c. General Test Methods and Acce tance Criteria Verification of the RPS capability is demon-strated by the proper integrated operation of the following:

(1) Motor-generator set performance (2) Sensor logic and scram relay logic (3) Scram reset time delay (4) Sensors input-to-scram trip actuator response time on all channels of each function for which response times are required by Technical Specifications.

(5) Annunciators (6) Mode switch tests (7) Auxiliary sensor operation The ability of the system to scram the reactor within a specified time must be demonstrated in the CRD Hydraulic System Preoperational Test (14.2.12.1.11).

1 4. 2-55

WNP-2 AMENDMENT NO. 1 2 November 1980 l4.2.l2.1.19 Neutron Monitoring System Preoperational Test

a. ~Pur ose To verify the operation of the Neutr'on Monitoring System (NMS), including startup, intermediate, and power'ange detectors, and their related equipment.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Additionally, all source range monitors (SRM's) and pulse preamplifiers, intermediate range monitors (IRM's) and voltage pre'amplifiers, and average power range monitors (APRM's) will have been calibrated per vendor's instructions.

c. General Test Methods and Acce tance Criteria Veri f ication of the NMS capability is demon-strated ky the proper integrated operation of the following:

(l) All SRM detectors, and their respective in-sert and retract mechanisms, and cables (2) SRM channel, including pulse preamp, remote meter and recorder, trip logic, logic bypass and related lamps and annunciators, control system interlocks, refueling instrument trips, and power supply (3) All IRM detectors and their respective in-sert and retract mechanisms and cables (4) IRM channels, including voltage preamps, remote recorders, RMCS interlocks, RPS trips, annunciators and lamps, and power supplies (5) All LPRM detectors and their respective cables, and power supplies 14.2-56

WNP-2 AMENDMENT NO. 13 February 1981 (6) All APRM channels, including trips, trip bypasses, annunciators and lamps, remote recorders, RMCS interlocks, RPS trips, and power supplies (7) Recirculation flow bias signal, including flow unit, flow transmitters, and related annunciators, interlocks, and power supplies (8) Both RBM channels, including trips, trip bypasses, annunciators and lamps, remote recorders, RMCS interlocks and power supplies.

14.2.12.1.20 Traversing In-Core Probe System Preoperational Test

a. ~Par ose To verify the operation of the Traversing In-Core Probe (TIP) System, including the TIP detector, controls and interlocks, containment secure lamp and containment isolation circuits'he System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Additionally, the TIP detector and dummy detector, ball valve time delay, core top and bottom limits, clutch, X-Y Recorder, and purge system will have been shown to 'be operational.

c. General Test Methods and Acce tance Criteria With the exception of the shear valve, which is not tested, verification of the TIP System is demonstrated by the proper integrated operation of the following:

(1) Indexer cross-calibration interlock (2) Shear valve control monitor lamp (3) Drive motor manual control and override, automatic control and stop, and low speed control 14.2-57

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.1.21 Rod Worth Minimizer System Preoperational Test

,a. ~Pur ose To verify the operation of the Rod Worth Minimizer (RWM) System under its various modes of operation.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Additionally, the Rod Position Indication System (RPIS) will have been shown to be operational, Rod Sequence Control (RSC) System bypassed, and computer diagnostic and special tests complete.

c. General Test Methods and Acce tance Criteria

-Verification of the RWM System is demonstrated by the proper computer initiation of the following:

(1) Rod test option (2) System initialization both above and below the low power setpoints, and above and below the low power alarm points (3) RWM program (4) Rod withdrawal and insertion error block (5) Rod drift scan, and annunciation RWM program acceptance of an operator-supplied rod position value must be demonstrated.

14.2-58

WNP-2 AMENDMENT NO- 12 Nov ember 1 980 14.2.12.1.22 Process Radiation Monitoring System

'Preoperational Test

a. ~Pur ose To verify the operation of the Process Radiation Monitoring (PRM) System, including the offgas vent, offgas, main steam line, liquid process, and building ventilation radiation monitoring su bsys tems.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Additionally, the process radiation monitors and pulse preamplifiers, power supplies, indicator and trip units, and sensors and converters're calibrated according to the vendor's instruction manual; insulation resistance and high potentiometer tests will have been completed.

c. General Test Methods and Acce tance Criteria Verification of the PRM System is demonstrated by the proper integrated operation of the following:

(1) Vent sensors, preamps, channels, trip points, annunciators and lamps, sample rack, and check source (2) Offgas vial sampler, Log Radiation Monitor (LRM) and their related annunciators, lamps and recorders, and high/low flow detector (3) Main steam gamma detector and LRM channels, trip points, and annunciators and lamps, High-High and Xnop Trip, and recorders (4) Liquid process scintillation detector, preamps, channels, trip points, and annunci-ators and lamps, and recorders 14.2-59

WNP-2 AMENDMENT NO. 12 November 1980 (5) Building ventilation system tr ip points, and annunci sensors,'hannels, ators and lamps, recorders, and standby gas treatment interlock (6) Control center air monitoring sensors, channels, annunicators, and indicators 14.2.12.1.23 Area Radiation Monitoring System Preoperational Test

a. ~Pus ose To verify the operation of the Area Radiation Monitoring (ARM) System, including sensors and channels, .trip points, alarms, and recorder.

b. Prere uisites The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiaton of testing. Additionally, indicator and trip units, power supplies, and sensor/

converters are cali br ated according to the vendor's instruction manual.

c. General Test Methods and Acce tance Criteria Verification of the ARM System capability is demonstrated by the proper integrated operation of the following:

(1) Sensor/converter, and associated channels (2) Channel trip points (3) Alarm annunciators and lights

'(4) Recorder 14.2.12.1.24 Process Computer Interface System Preoperational Test

a. ~Puu ose To verify the operation of the Process Computer Interf ace (PCI) System, including computer inputs and printout.

14.2-60

WNP-2 AMENDMENT NO. 12 November 1980 The System Lineup Tes ts have'een completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Additionally, computer diagnostic checks and programming are completed.

c. General Test Methods and Acce tance Criteria Verification of the PCI System is demonstrated by proper operation of the following:

(l) Analog input signals (2) Computer printout (3) Digital input signals (4) Digital output signals l4.2.12,.1.25 Rod Sequence Control System (RSCS)

Preoperational Test

a. ~Pur ose To verify the operation of the Rod Sequence Control System (RSCS) under its various modes of operation.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the St ar tup Superintendent has approved the initiation of testing. Additionally, the self-test feature of the RSCS is verified.

c. General Test Methods and Acce tance Criteria Verification of the RSCS is demonstrated ky the proper initiation of the following:

(l) Low power setpoint and low power alarm point tests 14.2-61

WNP-2 AMENDMENT NO. 13 February 1981 (2) RSCS status displays and annunciators (3) Reactor mode switch test (4) System diagnostic and data quality tests (5) Rod position data tests (6) Single rod bypass provision (7) Rod sequences tests (8) Rod group assignment (9) Constraints of rod movement tests (10) 100% to 758 control rod density tests (ll) 75% to 508 control rod density tests (12.) 50% control rod density to low power.

setpoint tests 14.2.12.1.26 Remote Shutdown 'Preoperational Test

a. ~Pur use To verify the feasibility and operability of the shutdown functions from the remote shutdown panel and its ability to bring the reactor to a cold condition in an orderly fashion.

The System Lineup Tests have been completed and the TNG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Additionally, the control power should be supplied to the remote shutdown panel, and the independence of power supply voltage, and fuses should be verified.

'c. General Test Methods and Acce tance Criteria Verification of the remote shutdown system is demonstrated by the following tests:

14.2-62

l WNP- 2 AMENDMENT NO. 31 June 1983 Operation of valves, controls, instru-ments, and pumps on sys tems available from this panel.

(2) Transfer switch operation from the con-trol room panels to the remote shutdown panel.

14. 2e12.L.27 . Offgas System Preoperational Test Pur~se To verify the operation of the offgas system .

including valves, recombiner, condensers, coolers, filters, and hydrogen analyzers.

h. ~Prere nisites The System Lineup Tests have been completed TWG has reviewed and approved the procedure and'he and the Startup Superintendent (Assistant Plant Manager) has approved the initiation of test-ing. Addi tionally, the instrument air sys tern, electrical power, and cooling water should be operational .

c. General Test Nethcds and dence tance Criteria Ver i fi cz t ion o f the o f fgas sys tern 's demon-strated by the following tests a Valve operation including fail safe and isolation features and valve status lights indicate the correct valve posi-.

tion; (2) Pump operation; (3) Level and temperature control and indi-cation; (4) Recombiner and preheater tests >,

-ondenser, cooler and moisture separator tests; Gas dryer and cooler tests; Filter efficiency;

14. 2-63

NNP-2 M1EVDNENT NO. 31 June 1983 analyzer per formance test; 'ydrogen Purge and bleed air rate test; and Charcoal absorber vault refrigeration test.

14. 2-63a

WNP-2 W."TP-2 AMENDNEHT NO. 29 March 1983 14.2s12.1.28 Environs Radiation Monitoring Preoperational Test a.' Pu~sose To verify the operation of t'e environs radia-tion monitoring system, including dosimetets, sampling pump, and filter equipm nt.

Pter~a uisites System Lineup Tests have been word compl ted, the TNG has reviewed and approved the procedure, and the Startup Superintendent has approved the initiation of testing. Additionally, indicator power supplies are calibrated according to the vendor 's instruction manual.

C ~ General Test Method and Acceptance Criteria Verification of the environs radiation monitor-

. ing system capability is demonstrated by the proper operation of the following:

(1) Air Sample Equipment (2) 7LD (Passive Dosimeters) 14.2.12.1 ~ 29 Main Steam System Preoperational Test

a. ~Put ose To verify the proper operation of the Main Steam Isolation Valves (NSIVs) and related controls.

b.

The System Lineup Tests have been completed, the TWG has revi wed and approve9 the procedure, and the Startup Superintend nt has approved the initiation of testing.

14.2-64

WNP-2 AMENDMENT NO. 12 November 1980

c. General Test Methods'nd Acce tance Criteria Verification of the Main Ste'am System is demon-strated by the following:

(1) Automatic isolation of the MSIV's.

(2) Minimum closing times are met.

(3) MSIV accumulator capacity tests are satis-f actory.

(4) Valves, heaters, blowers and initiating logic of the Main Steam Isolation Valve Leakage Control System.

14.2.12.1.30 Radwaste Building HVAC System Preoperational Test

a. ~Par ose To verify that the Radwaste Building HVAC System will function in accordance with the design requirements as set forth in the design specifications.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The 480 VAC,Power System, Control Air Supply Service Air System and the Turbine Service Water System is capable of sup-porting this test as necessary.

c. General Test'Methods and Acce tance Criteria Verification of the Radwaste Building HVAC System is demonstrated by the proper operation of the following:

(1) Ventilation fans and their related controls (2) Filters and instrumentation (3) Dampers and controls (4) Annunciators and protective devices 14.2-64 a

WNP-2 P

BLANK

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.1;31 Closed Cooling Water System Preoper ational Test a~ ~pur ose 4

To verify the operation of the Closed Cooling W'ater. (RCC) System, including pumps, valves, logic and annunci ator.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing.'he following support systems must have received readiness verification:

(l) Control and Service Air (CAS/SA)

(2) Makeup Water Treatment (3) Essential 480 Vac Power (4) Instrumentation Power

c. General Test Methods and Acce tance Criteria Verification of the Closed Cooling Water System is demonstrated by the proper operation of the following:

(l) Surge tank level control (2) System pumps and control logic (3) Chemical addition pump and control (4) Remote-operated valves 14.2.12.1.32 Primary Containment Atmospheric Control System Preoperational Test

a. P~ur ose To verify the operation of the Primary Contain-ment Atmospheric Control (CAC) System including blowers, coolers, valves, instruments and al arms.

14. 2-65

WNP-2 AMENDMENT NO. 12 November 1980 The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Primary Containment, Essential 480 Vac Power, Standby Service Water, Instrument Power and Control Air Systems must have received readiness verification.

14.2-65a

WNP-2 BZAHK

WNP-2,, AMENDMENT NO. 12 November 1980 c~ General Test Methods and Acce tance Criteria Verification of the Primary Containment Atmos-pheric Control System is demonstrated by the proper integrated operations of the following:

(l) Isolation and control valves (2) Blowers (3) Instrumentation (4) Alarms (5) Recombiner components to the extent that flow paths are verified Primary Containment Atmospheric Control System hydrogen/oxygen recombining performance capa-bilities are not demonstrated during the pre-operational test.

14.2.12.1.33 Primary Containment Cooling System Preoperational Test

a. ~Pur ose To verify the operation of the Primary Contain-ment Cooling (CRA) System including ans, f dampers, related controls and instrumentation.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. 480 Vac Power, Instrument Power, and Closed Cooling Water Systems must have received readiness verification.

c. General Test Methods and Acce tance Criteria Verification of the Primary Containment Cooling System is demonstrated by the proper operation of the following:

14.2-66

WNP-2 AMENDMENT NO. 12 November 1980 (1) Fans and control logic (2) Cooling coils (3) Dampers, cooling water flow control valves and related controls (4) Instrumentation (5) Related loss-of-power logic (6) Annunciators Primary Containment Cooling System heat removal capabilities are not demonstrated during the preoperational test.

14.2.12.1.34 Primary Containment Instrument Air Preoperational Test

a. ~Vur ose To verify proper operation of the Containment Instrument Air System, including compressors, dryers, valves and related controls and logic.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Star tup Superintendent has approved the initiation of testing. The Plant Service Water Supply System must receive a readiness classif i-cation.

c. General Test Methods and Acce tance'Criteria Verification of the CIA System capability is demonstrated by the proper integrated operation of the following:

(1) Logic and interlocks (2) CIA System air compressors 14.2-67

WNP-2 AMENDMENT NO. 20 November 1981 (3) CIA System air dryers (4) System non return check valves (5) Alarms and controls (6) Nitrogen backup supply (7) Valve/component failure modes for those valves/components supplied by the CIA system to simulated loss of air supply 14.2.12.1.35 Primary Containment Atmospheric Monitoring System Preoperational Test

a. ~Pur oae To verify the capability of the Primary Contain-ment Atmospheric Monitoring (CMS) System to monitor and display containment atmospheric conditions.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Instrument power is available to system components.

c. General Test Methods and Acce tance Criteria Verification of the Primary Containment Atmos-pheric Monitoring System capability is demon-strated by the proper operation of the following:

(1) Samples and controls (2) Analyzers (3) Pressure and temperature instrumentation (4) Radiation monitors (5) Indicating/recording instrumentation (6) Annunciators 14 '-68

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.1.36 Standby Gas Treatment System Preoperational Test

a. ~Pur ose To verify the reliable operation of the Standby Gas Treatment (SGT) System,'ncluding fans, filter trains and related controls.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The following systems must have readiness verification:

(1) Essential 480 Vac power (2) Instrument power

,(3) Control air (4) Reactor Building Heating and Ventilation

c. General Test Methods and Acce tance Criteria Verification of the Standby Gas Treatment System is demonstrated ky the proper integrated opera-tion of the following:

(1) SGT fans and control logic (2) Filter trains and related instruments

.(3) Automatic valves and control logic (4) System interconnections to,Reactor Building Heating and Ventilation, and Primary Con-tainment Atmospheric Control Systems (5) Annunciators 14 . 2-69

WNF-2 AMENDMENT NO. 26 July 1982 14.2.12.1.37 Loss of Power and Safety Testing Preoperational Test

a. Purpose To verify the operaton of the 230/115kV, 6.9kV, 4.16kV, and 480V distribution systems.

To verify the integrated ability of the plant electrical distribution and safety systems to operate on normal and standby power sources during accident conditions.

To verify that loss of a single AC or DC distri-bution system division (exclusive of the HPCS diesel generator and batteries) will not prevent the remaining systems from actuatinq during an accident condition.

b. Prerequisites The System Lineup Tests and the 69/N consecutive starts for the emerqency D/Gs have been completed and the TWG has reviewed and approved the proce-dure and the Startup Superintendent has approved the initiation of testing. The 125V DC system and the FCCS are available to support testing.

c. General Test Methods and Acceptance Criteria Verification of the 230/115kV, 6.9kV, 4.16kV and 480V distribution system operability shall be demonstrated by the following:

(1) Demonstration of circuit inteqrity and

,integrated operation of circuit breakers, controls and interlocks, instrumentation, automatic transfer features and protective devices and 'alarms.

(2) Demonstration of proper system response to a loss of the 230kV,and 115kV distribution systems independently and simultaneously both with and without BOCA/containment isolation signals.

(3) Demonstration of proper system response to a loss of the 230/115kV distribution systems and one individual standby diesel generator during an ECCS/containment isolation actuation.

14. 2-70

WNP-2 AMENDMENT NO. 20 November 1981 Signals for these tests shall be simulated from the actual initiating devices when this is practical.

(4) Testing of the Diesel Generators will include the followihg:

a ~ Sequential loading of each diesel generator unit.

b. Maintenance of specified frequency and voltage during the loading sequence.

c~ The diesel generator's capability to reject and restart their largest single load anytime after the design loading sequence is complete.

(I ~ The dieselgenerator's capability to supply power to vital equipment during loss of station normal power conditions.

14, 2. 12. 1. 38 DELETED 14.2-70a

WNP-2 BLANK

WNP-2 AMENDMENT NO. 7 November 1979 14.2.12.1.39 DELETED 14.2.12.1.40 DELETED 14.2-71

WNP-2., AMENDMENT NO. 12 November 1980 14.2.12.1.41 Instrument Power Preoperational Test

a. ~Pur ose To verify the operation of the Instrument Power (IP) Systems.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing.

The 125Vdc and the 480Vac power systems are energized and capable of supplying power to the Instrument Power Systems.

c. General Test Methods and Acce tance Criteria, Verification of the Instrumentation Power Sys-tems shall be accomplished by demonstrating circuit integrity and integrated operation of:

14.2-72

WNP-2'MENDMENT NO. 12 November 1980 (1) Static inverters, transformers and buses (2) Controls and interlocks (3) Transfer features (4) Instrumentation (5) Protective devices and alarms 14.2.12.1.42 Emergency Lighting System Preoperational Test

a. ~Pur ose To verify the operation of the Emergency Lighting system (EL) within the design requirements of the System.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Star tup Superintendent has approved the initiation of testing. The 125 Vdc system has received a readiness verif ication.

c. General Test Methods and Acce tance -

Criteria Verification of the Emergency Lighting system is to demonstrate proper automatic operation of the system and to provide sufficient lighting during loss of normal lighting.

1$ .2,e12.1.43 Standby AC Power System Preoper'ational Test

a. P~ur ose To verify the operation of th'e Standby AC Power System including diesel engines, auxiliaries, gener ators, controls and instrumentation.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing.

14.2-73

WNP-2 r AMENDMENT NO. 20 November 1981 The following support systems or components must have received readiness verification:

(1) Standby Service Water (2) 125/250 Vdc Power (3) Instrument Power (4) Essential 4160 Vac Power

c. General Test Methods and Acce tance Criteria Verification of the Standby AC Power System is demonstrated by the proper integrated operation of the following:

(1) The diesel engines and auxiliaries (2) The generators, exciters and voltage regulators (3) Fuel storage and 'supply system (4) Start and control logic circuitry and interlocks (5) Protective devices (6) Instrumentation (7) Annunciators Testing will be performed to demonstrate the following design features:

(1) The diesel-generators'erformance capabil-ity to establish frequency, voltage and load acceptance with a specified time interval upon initiation of an automatic start signal under both cold and hot con-ditions.

14'. 2-,74

WNP-2 AMENDMENT NO. 20 November 1981 (2) Specified full- and over-load performance capabilities.

(3) The. diesel generator's capability to reject the maximum rated load without exceeding speeds or voltage which will cause tripping.

14.2,.12.1.44 250 Vdc Power System Preoperational Test

a. ~Pur ose To verify the operation of the 250 Vdc Power System including batteries, chargers, controls, interlocks, instruments and protective devices.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Battery room ventilation and 480 Vac power supply to the chargers have received readiness verification.

c. General Test Methods and Acce tance Criteria Verification of the 250 Vdc Power System is demonstrated by the proper integrated operation of the following:

1. Battery chargers including capability to recharge the battery in accordance with 8.3.2.1.4.3.

14. 2-75

WNP-'2 AMENDMENT NO. 12 November 1980 (2) Batteries '(including charge and 'discharge rate/capacity tests and load prof iles described in Table 8.3-5)

(3) Protective relays and devices (4) 'ystem control logic (5) Instrumentation (including, ground detection)

(6) Breakers (7) Annunciators 14.2.12.1.45 125 Vdc Power System Preoperational Test

a. ~Pur ose To verify the operation of the 125 Vdc Power System including batteries, chargers, controls, interlocks; instruments and protective devices.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Battery room ventilation and 480 Vac power supply to. the chargers have received readiness verification.

c. ,General Test Methods and Acce tance Criteria Verification of the 125 Vdc Power System is demonstrated by the proper integrated operation of the following:

(1) Battery chargers including capability to recharge the battery in accordance with 8.3.2.1.1.3 (2) Batteries (including charge and discharge rate/capacity tests and load profiles described in Table 8.3-4a and b)

(3) Protective relays and devices (4) System control logic 14.2-76

WNP-2 AMENDMENT NO. 12 November 1980 (5) Instrumentation (including ground detection)

(6) Breakers (7) Annunciators 14.2.12.1.46 24 Vdc Power System Preoperational Test

a. ~Pur ose To verify the operation of the 24 Vdc Power Sys tern.

b.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Sperintendent has approved the initiation of testing.

Battery room ventilation is operating and

.120/240 Vac power is available and capable of supplying the battery chargers.

c. General Test Methods and Acce tance'Criteria Verification of the 24 Vdc Power System shall include demonstrations of battery capacity and battery charger capabilities described in 8.3.2.1.3.3 14.2.12.1.47 Plant Service Water System Preoperational Test

a. ~Pur ose To demonstrate the proper operation of the Plant Service Water (TSW) System, including pumps, valves and related controls.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing.

14.2-77

WNP-2 AMENDMENT NO. 12 November 1980 The following support systems or components must have" received readiness verification: .

(1 ) 4160 Vac Power (2) 480 Vac Power (3) Instrument Power (4) Service water pump house structure (5) Various heat exchangers or coolers utilizing service water (6) Tower Makeup (TMU)

c. General Test Methods and Acce tance Criteria Verification of the Plant Service Water System is demonstrated by the proper operation and per-formance of the service water pumps, the opera-tion of filters, remote-operated valves, related controls and instrumentation.

14.2.12.1.48 Standby Service Water System Preoperational Test

a. ~Pur ose To verify the proper operation of the Standby Service Water (SWS) System for normal and abnor-mal plant operating modes.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The following support systems or components must have received readi-ness verification:

(1 ) Essenti al 4160 Vac power 14.2-78

(2) Instrument power (3) Control Air (4) Standby service water pump house structure (5) Various heat exchangers or coolers utilizing standby service water (6) Tower Makeup (TMU)

c. General Test Methods and Acce tance Criteria Standby Service Water System heat. dissipation capabilities are not demonstrated during the preoperational test. Verification of this sys-tem is demonstrated by the proper, integrated operation and performance of the following:

(1) Pumps and related controls (2) Remote-operated valves and controls (3) Automatic-operated valves and control logic (4) Instrumentation (5) Annunciators (6) Standby Service Water System control logic response to a simulated loss of normal station power event.

14.2.12.1.49 Plant Communications System Preoperational Test

a. ~Per ose To demonstrate that the Plant Communications and Evacuation Alarm System will provide effective communication between various plant locations and to verify proper operation of the emergency evacuation alarm components and system.

14. 2-79

WNP-2 AMENDMENT NO. 12 November 1980

b. Prere uisites The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of te'sting.

c. General Test Method and Acce tance Criteria Proper operation of all the communication system components and the emergency evacuation alarm system 'and components will be demonstrated.

14.2.12.1.50 Reactor Building Emergency Cooling System Preoperational Test a.'Pur ose To demonstrate the proper integrated operation of the Reactor Building Emergency Equipment Cooling System including f ans, cooling coils, instrumentation and controls.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The following support systems or components must have received readi-ness verification:

(1) Electrical power to motors, control cir-cuits and instrumentation (2) Standby Service Water System

c. General Test Method and Acce tance Criteria Verification of this system is demonstrated by the proper integrated operation of the fan coil units, their associated controls, interlocks and -annunciations.

14.2-80

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.1 e51 Control, Cable and Critical Switchgear Rooms Heating, Ventilation and Air Conditioning System Preoperational Test I

a. ~Per ose To verify that the Control, Cable and Critical Switchgear Rooms Heating, Ventilation, and Air Conditioning (CR-HVAC) Systems will function in accordance with the design requirements as set forth in the design specifications.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The following support systems have received readiness verification; (1) 480 Vac Power (2) Instrument Power (3) Chilled water

c. General Test Methods and Acce tance Criteria Verification of the Control, Cable and Critical Switchgear Rooms Heating, Ventilation and Air Conditioning System is demonstrated by the pro-per integrated operation of the following:

(1) Supply and exhaust fans and their related controls (2) Filters, campers, valves and related instrumentation and control logic (3) Coolers (4) Annunciators 14.2-81

WNP-2 AMENDMENT NO. 20 November 1981

14. 2. 12. 1. 52 Standby Service Water Pumphouse H & V System Preoperational 'Test

a. ~Pur ose To verify that the Standby Service Water Pump House H 6 V System will function in,.accordance with the design requirements as set forth in the design specifications.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The 480 Vac Power System must have received readiness verification.

c. General Test Method and Acce tance Criteria Verification of the Standby Service Water Pump-house H 6 V System is demonstrated by the proper operation of the following:

i. Ventilation fans and their related controls

2. Tilters and instrumentation

3. Dampers and controls

4. Annunciators 14.2.12.1.53 Reactor Building Crane Preoperational Test a ~ ~Pur ose "

To verify the operation of the Reactor Building Crane.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. Construction load tests of 125% static and 100% operational are complete.

14.2-82

WNP-2 AMENDMENT NO. 12 November 1980 Contractor use of the Reactor Building Crane for construction purposes is complete.

c. General Test-Methods and Acce tance'Criteria Verification of the Reactor Building Crane is demons tr ated by the proper oper ation of the following:

(1) Crane Traverse components (2) Hook traverse and hoist components (3) Controls and indicators (4) Safety devices (S) Instrumentation 14.2.12.1.54 Primary Containment Integrated Leak Rate Preoperational Test

a. ~Pur use To verify overall primary containment integrity by pressurizing to specified test pressures and conducting integrated leak rate measurements.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The following supporting activities, systems or components must have been completed or received readiness verification:

(1) All type B and C local leak testing completed, documented and verified as a System Lineup Test, refer to FSAR 6.2.6.2 and 6.2.6.3

~

(2) All containment isolation valves fully operable and closed in the normal manner using the isolation signal 14.2-83

WNP-2 AMENDMENT NO. 12 November 1980 (3) All containment-associated piping hangers,'

uppor ts, res tr ai nts and anchors have been installed and properly set (4) Residual Heat Removal and Core Spray Systems preoper at ion al tests complete (5) A containment area survey completed to locate, isolate or remove any instrumen-tation, light bulbs, etc., which .may be damaged by high external pressure

c. General Test Methods and Acce tance Criteria Verification of primary containment integrity is demonstrated by pressurizing to the required test pressure. See FSAR 6.2.6.1 for a detailed test description.

The drywell-wetwell leakage test will be per-formed as part of this test to verify the accep-tance cri teri a described in FSAR 3.8.3.7.

14.2.12.1.55 Secondary Containment Integrated Leak Rate Preoperational Test

a. ~Pur ose To verify overall secondary containment integ-rity Q subjecting the Reactor Building to a specified negative pressure 'and measuring the i nle ak age.

,The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The following activities or systems/components must supporting have been completed or received readiness verification:

(1) Reactor Building structure complete with personnel and railroad air lock doors in-stalled and operable (2) Reactor Building conduit, pipe and other structural penetrations sealed (3 ) Standby G as Treatment System 14.2-84

WNP-2, AMENDMENT NO. 20 November 1981

c. General Test Methods and=-Acce tance Criteria Verification of secondary containment integrity is demonstrated by operating the Standby Gas Treatment System at a specific capacity while maintaining the Reactor Building internal struc-ture at a specified negative pressure.

14 ~ 2, 12. 1. 56 Diesel Generator Building H & V System Preoperational Test

a. ~Pur ose To verify that the Diesel Generator Building H&V System will function in accordance with the design requirements as set forth in the design specifications.

The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing. The 480 Vac Power System must have received readiness verification.

c. General Test Methods and Acce tance Criteria Verification of the Diesel Generator Building H & V System is demonstrated by the proper operation of the following:

(1) Ventilation fans and their related controls (2) Tilters and instrumentation (3) Dampers and controls (4) Annunciators 14.2. 12. 1.57 Seismic Monitoring system Preoperational Test

a. ~Pur ose To verify the operation of the Seismic Monitoring System.

14. 2-85

WNP-2 AMENDMENT NO. 20 November 1981 The System Lineup Tests have been completed and the TWG- has reviewed and approved the procedure and the Startup Superintendent has approved the initiation of testing.

c. General Test Methods and Acce tance Criteria Verification of the Seismic Monitoring System is demonstrated by proper integrated operation of the following:

(1) Annunciators (2) Instrumentation 14.2-85a

NNP-2 4

BLMK

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.2 General Discussion of Startup Tests All those tests comprising the Startup Test Phase (Table 14.2-4) are discussed in this section. For each test a description is provided for test purpose, test prerequisites, test description and statement of test acceptance criteria, where applicable. Additions, deletions, and chang'es to these discussions are expected to occur as the test program progresses. Such modification to these discussions will be reflected in amendments to the FSAR.

In describing the purpose of a test, an attempt is made to identify those operating and safety-oriented characteristics of the plant which are being explored.

Where applicable, a definition of the relevant acceptance criteria for the test is given and is designated either Level 1 or Level 2. A Level criterion normally relates 1

to the value of a process .variable assigned in the design of the plant, component systems or associated equipment. If a Level 1 criterion is not satisfied, the plant will be placed in a suitable hold-condition until resolution is obtained.

Tests compatible with this hold-condition may be continued.

Following resolution, applicable tests must be repeated to verify that the requirements of the Level criterion are 1

now satisfied.

A Level 2 criterion is associated with expectations relating to the performance of systems. If a Level 2 criterion is not satisfied, operating and testing plans would not neces-sarily be altered. Investigations of the measurements and of the analytical techniques used for the predictions would be started.

For transients involving oscillatory response, the criteria are specified in terms of decay ratio (defined as the ratio of successive maximum amplitudes of the same'polarity). The decay ratio must be less than unity to meet a Level 1 criter-ion and less than 0.25 to meet Level 2.

14.2-86

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3 Startup Test Procedures 14.2.12.3.1 Test Number 1 Chemical and Radiochemical 14.2.12.3.1.1 Purpose The principal objectives of this test are a) to secure information on the chemistry and radiochemistry of the reactor coolant, and b) to determine that the sampling equipment, procedures and analytic techniques are adequate to supply the data required to demonstrate that the chemistry of all parts of the entire reactor system meet specifications and process requirements.

Specific objectives of the test program include evaluation of fuel performance, evaluations of demineralizer operations by direct and indirect methods, measurements of f iltqr per formance, conf irmation of condenser integrity, demonstra-tion of proper steam separator-dryer operation, measurement and calibration of the offgas system, and calibration of certain process instrumentation. Data for these purposes is secured from a variety of sources: plant operating records, regular routine coolant analysis, radiochemical measurements of specif ic nuclides, and special chemical tests.

'I 14.2.12.3.1.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.1.3 Description I

Prior to fuel loading a complete set of chemical and radio-chemical samples will be taken to ensure that all sample stations are functioning properly and to determine initial concentrations. Subsequent to fuel loading during reactor heatup and at each major power level change, samples will be taken and measurements will be made to determine the chemical and radiochemical quality of reactor water and reactor feedwater, amount of radiolytic gas in the steam, gaseous activities leaving the air ejectors, decay times in the offgas lines and performance of filters and deminerali-zers.

14.2-87

WNP-2 AMENDMENT NO. 20 November .1981 Calibrations will be made of monitors in the stack, liquid waste system and liquid process 'lines.

14.2.12.3.1.'4 Criteria Level 1 Chemical factors defined in the Technical Specifications must be maintained within the limits specified.

The activity of gaseous liquid effluents must conform to license limitations.

Water quality must be known at all times and should remain ~

within the guidelines of the Water Quality Specifications.

Level 2 Not applicable.

14.2-.88,

WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.3.2 Test Number 2 Radiation Measurements 14.2.12.3.2.1 Purpose The purposes of this test are a) to determine the background radiation levels in the plant environs prior to operation for base data on activity buildup and b) to monitorof radiation person-at selected power levels to assure the protection nel during plant operation.

14.2.12.3.2.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.2.3 Description A survey of natural background radiation throughout the plant site will be made prior to fuel loading. Subsequent to fuel loading, during reactor heatup and at power levels of 25%, 60% and 100% of rated power, gamma radiation level measurements and where appropriate, thermal and fast neutron dose rate measurements will be made at significant locations throughout the plant. All potentially high radiation areas will be surveyed.

14. 2. 12. 3. 2. 4 Criteria Level 1 The radiation doses of plant origin and the occupancy times of personnel in radiation zones shall be controlled consis-tent with the guidelines of the Standards for Protection Against Radiation outlined in 10 CFR 20.

Level 2 Not applicable.

14.2-89

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3.3 Test Number 3 Fuel Loading "14.2'.12.3.3.1 Purpose The purpose of this test is to load fuel safely and effi-ciently to the full core size.

14.2.12.3.3.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant'Manager has approved the test proce-dures and initiation of testing. Also the following pre-requisites will be met prior to commencing fuel loading to assure that this operation is performed in a safe manner:

a. The status of all systems required for fuel loading will be specified and will be in the status required.

b. Fuel and control rod inspections will be com-plete. Control rods will be installed and tested.

1

c. At least three movable neutron detectors will be calibrated and operable. At least three neutron detectors will be connected to the high flux scram trips. They will be located so as to provide acceptable signals during fuel loading.

d. Nuclear instruments will be source checked with a neutron source prior to loading or resumption i f suf f icient delays are incurred.

e. The status of secondary containment will be specified and established.

f. Reactor vessel status will be specified relative to internal component placement and this place-ment established to make the vessel ready to receive fuel.

g. Reactor vessel water level will be established and minimum level prescribed.

14.2-90

WNP-2 AMENDMENT NO. 20 November 1981

h. The standby liquid control system will be operable and in readiness.

i. Fuel handling equipment will have been checked and dry runs completed.

j. The status of protection systems, interlocks, mode switches, alarms, and radiation protection equipment will be prescribed and verified. The high flux trip points will be set for a relati-vely low power level.

k. Water quality must meet required specifications.

l. A neutron source will be installed near the center of the core.

14. 2. 12. 3. 3. 3 Description Prior to fuel loading, control rods and neutron sources and detectors will be installed and tested. Fuel loading will begin at the center of the core and will proceed radially to the fully loaded configuration.

Control rod functional tests, subcriticality checks, and shut-down margin demonstrations will be performed periodically during the loading.

14.2.12.3.3.4 Criteria Level 1 The partia'lly loaded core must be subcritical by at least 0.38% 5k/k with the analytically strongest rod fully withdrawn.

Level 2 Not applicable.

14.2-91

WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.3.4 . Test Number .4 . Full Core Shutdown Margin

14. 2. 12. 3. 4. 1 Purpose The purpose of this test is to demonstrate that the reactor will be subcritical throughout the first fuel cycle with any single control rod fully withdrawn.

14.2.12.3.4.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Also the following prere-quisites will be complete prior to performing the full core shutdown margin test:

a. The predicted critical rod position is available

b. The Standby Liquid Control System is available c~ Nuclear instrumentation is available with neutron count rate of at least two counts per second and signal to noise ratio greater than two.

d. High-flux scram trips are set conservatively low .

14.2.12.3.4.3 Description This test will be performed in the fully loaded core in the Xenon-free condition. The shutdown margin test will be per-formed by withdrawing the control rods from the all-rods-in configuration until criticality is reached. If the highest worth rod will not be withdrawn in-sequence, other .rods may be withdrawn providing that the reactivity worth is equivalent.

The difference between the measured Keff and the calculated eff for the in-sequence critical will be applied to the calculated value to obtain the true shutdown margin.

14. 2. 12. 3. 4. 4 Criteria Level 1 The shutdown margin of the fully loaded, cold (68'F or 20'C) f xenon-free core occuring at the most reactive time during the cycle must be at least 0.38% pk/k with the analytically

14. 2-92

WNP-2 AMENDMENT NO. 20 November 1981 strongest rod (or its reactivity equivalent) withdrawn. If the shutdown margin is measured at some'ime during the cycle other than the most reactive time, compliance with the above criterion is shown .by demonstrating that the shutdown margin is 0.38% LLk/k plus an exposure dependent correction factor which corrects the shutdown margin at that time to the minimum shutdown marg in.

Level 2

a. Criticality should occur within + 1% k/k of critical (predicted critical to be the'redicted determined later).

14. 2-93

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3.5 Test Number 5 Control:Rod Drive System 14.2.12.3.5.1 Purpose The purposes of the Control Rod Drive System test are a) to demonstrate that the Control Rod Drive (CRD) System operates properly over the full range of primary coolant temperatures and pressures from ambient to operating, and b) to determine the initial operating characteristics of the entire CRD system.

14.2.12.3.5.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. The Reactor Manual Control System Preoperational Testing must be completed on control rod drives being tested. The Reactor Vessel, Closed Cooling Water System, Condensate Supply System and Instrument Air System must be operational to the extent required to conduct the test.

14.2.12.3.5.3 Description The CRD tests performed during the startup test program are designed as an extension of the tests performed during the preoperational CRD system tests. Thus, after it is verified that all control rod drives operate properly when installed, they are tested periodically during heatup to assure that there is no significant binding caused by thermal expansion of the core components. A list of all control rod drive tests to be performed during startup testing is given below.

14.2-94

CONTROL ROD DRIVE SYSTEM TESTS Reactor Pressure with Core Loaded Test Accumulator Preop ps I g (kg/cm )

~Descrl tion Pressure Tests 0 600(42.2) 800(56.2) Rated Position Indication all all Normal Times all al I Insert/Withdraw Coupling all all"""

Friction all Scram Normal el I al I al I Scram Min i mum Scram Zero Scram (Scram .Norma I 4 Discharge Volume (ful I High Level) core scram)

Scram Normal Value refers to the four slowest CRDs as determined from the normal accumula-tor pressure scram test at ambient reactor pressure. Throughout the procedure, "the four slowest CRDs" implies the four slowest compatible with rod worth minimizer and CRD sequence requirements.

Scram times of the four slowest CRDs wil I be determined at 25$ , 50-75>~ and 100$ of rated power during planned reactor scrams.

""" Establish initial ly that this check is normal operating procedure.

Note: Single CRD scrams should be performed with the charging valve closed (do not ride the charging pump head).

WNP-2 AMENDMENT NO. 26 July 1982 1 4. 2. 12. 3. 5. 4 Criteria Level 1 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.

The mean scram time of all operable CRDs at any reactor pressure must not exceed the following times: (Scram time is measured from the time the pilot scram valve solenoids are deenerg ized. )

Rod Scram Time Position (Seconds) 45 0.430 39 0.868 25 1. 936 05 3.497 The mean scram time of the three fastest CRDs in a two-by-two array at any reactor pressure must not exceed the following times: (Scram time is measured from the time the pilot scram valve solenoids are deenergized.)

Rod Scram Time Position (Seconds) 45 0.455 39 0. 920 25 2. 052 05 3. 706 Level 2 Each CRD must have a normal insert or withdraw speed of 3.0 +

0.6 inches per second (7.62 + 1.52 cm/sec), indicated by a full 12-foot stroke in 40 to 60 seconds.

14. 2-'96

ttith'respectto the control rod drive friction tests, if the differential pressure variation exceeds 15 psid (1 kg/cm )

for a continuous drive in, a settling test must be performed, in which 'case, the differential2settling pressure should not be than less than 30 psid (2 10 psid (0.7 kg/cm 1

)

kg/cm over a

) nor should full stroke.

it vary by more

14. 2-97

WNP-2 AMENDMENT NO. 12 November 1980 14.2. 12.3. 6 Test Number 6 SRM Per formance and -Control Rod Sequence 15.2.12.3.6.1 Purpose The purpose of this test is to demonstrate that the opera-tional sources, SRM instrumentation, and'od withdrawal sequences provide adequate information to achieve criticality and increase power in a safe and efficient manner. The effect of typical rod movements on reactor power will be determined.

14.2.12.3.6.2 Prere'quisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test procedures and initiation of testing. The Control Rod Drive System must be operational.

14.2.12.3.6.3 Description The operational neutron sources will be installed and source range monitor count-range data will be taken during rod withdrawals to critical and compared with stated criteria on signal and signal count-to-noise count ratio.

A withdrawal sequence has been calculated which completely specifies control rod withdrawals from the all-rods-in condition to the rated power configuration. Critical rod patterns will be recorded periodically as the reactor is he ated to r ated temper ature.

Movement of rods in a prescribed sequence is monitored by the Rod North Minimizer, which will prevent out of sequence withdrawal. Also not more than two rods may be inserted out of sequence.

As the withdrawal of each rod group is completed during the power ascension, the electrical power, steam flow, control valve position, and APRM response will be recorded.

14.2.12.3.6.4 Criteria Level 1 There must be a neutron signal count-to-noise count ratio of at least 2 to on the required operable SRMS or Fuel 1

Loading Chambers.

14.2-98

WNP-2 AgPNDNENT NO. 20 November 1981 There must be a minimum count rate of 3 counts/second on the required operable SRMs or fuel loading chambers.

The XRNs must be on scale before the.Sos exceed the'od block set point.

Level 2 Not applicable.

14.2-99

I' I

14.2.12.3.7 Test Number 7 Not Applicable 14.2.12.3.8 Test, Number 8 Not Applicable ~

14.2-'100

WNP-2 AMENDMENT NO. 29 March 1983 14.2.12.3.9 Test Number 16B Water Level Reference Leg Temperature Measurement 14.2.12.3.9.1 Purpose The purpose of this test is to measure the reference leg tem-perature and recalibrate the affected. level instruments if the measured temperature is different than the value assumed during the initial calibration.

14.2 '2 ' '.2 Prerequisites The Preoperationl Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. All applicable system instrumentation is installed and calibrated.

14.2.12.3.9.3 Description To monitor the reactor vessel water level, five lev 1 instru-ment systems are provided. These are:

a. Shutdown Range Level System

b. Narrow Range Level System

c. Wide Range Lev 1 System

d. Fuel Zone Level System

e. Upset Range These systems are used respectively as follows:

Water level m asurement in cold shutdown conditions (Shutdown Range Level System)

b. Feedwater flow and water level control functions in hot operating conditions (Narrow Range Level System)

c. Safety functions in hot operating conditions (Wide Range L vel System)

d. Safety functions in cold shutdown onditions (Fuel Zone Level System)

e. High water 1 vel protection, hot operating condition (Upset Range) 14.2-101

WNP-2 AMENDMENT NO. 29 March 1983 The test will be done at rated temperature and pressure; and under st ady-state conditions and will verify that the reference leg temperature of the level instrument is the value assumed during initial calibration. Xf noti the instruments will be recalibrated using the measured value.

14.2.12 ';9.4 Criteria Level 1 Not applicable.

Level 2'he indicator readings on the narrow range level system should agree with +1.5 inches of the average readings or the reading calculated from the correct reference leg temperatures.

The wide and upset range level system indicators should agree within +6 inches of the averag readings or the readings calculated from the correct reference leg temperatures.

14.2-102

WNP-2 AMENDMENT NO. 20 November 1981

14. 2. 12. 3. 10 Test Number. 10 IRM Performance

14. 2. 12. 3. 10. 1 Purpose The purpose of this test is to adjust the Intermediate Range Monitor System to obtain an optimum overlap with the SRM and APRM systems.

14.2.12.3.10.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. All source range monitors and pulse preamplifiers, intermediate range monitors and voltage preamplifiers, and average power range monitors have been calibrated in accordance with vendor's instructions.

14, 2. 12. 3. 10. 3 Description Initially the IRM system is set to maximum gain. After the APRM calibration, the IRM gains will be adjusted to optimize the IRM overlap with the SRMs and APRMs.

14. 2. 12. 3. 10. 4 Criteria Level 1 Each IRM channel must be adjusted so that overlap with the SRMs and APRMs is assured. The IRMs must produce a scram at 96% of full scale.

Level 2 Not applicable.

14. 2-103

WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.3.11 Test Number 11 L'PRM Calibration 1 4. 2. 12. 3. 11. 1 Purpose, The purpose of this test is to calibrate the Local Power Range Monitoring System.

14.2.12.3.11.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation for calibra-tion has been checked and installed.

14.2.12.3.11.3 Description The LPRM channels will be calibrated to make the LPRM readings proportional to the neutron flux in the water gap at the chamber elevation. Calibration factors will be obtained through the use of either an off-'ine or a process computer calculation that relates the LPRM reading to average fuel assembly power at the chamber height.

14.2.12.3.11.4 Criteria Level 1 Not applicable.

Level 2 Each LPRM reading will be within 10% of its calculated value.

14. 2-104

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3.12 Test Number 12 APRM Calibration 14.2.12.3.12.1 Purpose The purpose of this test is to calibrate the Average Power Range Monitor System.

14.2.12.3.12.2 Prerequisites The Preoperational Tests have been completed and the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation for calibra-tion has been checked and installed.

14.2.12.3.12.3 Description A heat balance will generally be made each shift and after each major power level change. Each APRM channel reading will be adjusted to be consistent with the core thermal power as determined from the heat balance. During heatup a preliminary calibration will be made ky adjusting the APRM amplifier gains so that the APRM readings agree with the results of a constant heatup rate heat balance. The APRMs should be recalibrated in the power range ky a heat 'alance as soon as adequate feedwater indication is available.

14.2.12.3.12.4 Criteria Level 1 The APRM channels must be calibrated to read equal to or greater than the actual core thermal power.

Technical Specification Limits on APRM scram and Rod Block sh'all not be exceeded.

In the startup mode, all APRM channels must produce a scram at less than or equal to 158 of rated thermal power.

Recalibration of the APRM system will not be necessary from safety considerations if at least two APRM channels per RPS trip circuit have readings greater than or equal to core power.

14 ~ 2-105

V NNP>>2 Level 2 Xf the above criteria are satisfied then the APRN channels wil'1 be considered to be reading accurately if with the heat balance to'ithin'7% of rated'ower.

they agree I

14 ~ 2-'106

NNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3.13 Test Number 13 Process Computer 14.2.12.3.13.1 Purpose The purpose of this test is to verify the performance of the process computer under plant operating conditions.

14.2.12.3.13.2 Prerequisites The Preoperational Tests have been completed and the POC has reviewed and the Plant Manager has approved the test proce-and initiation of testing. Computer diagnostic test 'ures completed. Construction and construction testing on each input instrument and its cabling shall be completed.

14.2.12.3.13.3 Description Computer system program verifications and calculational program validations at static and at simulated dynamic input conditions will be preoperationally tested at the computer supplier's site and following delivery to the plant site. Following fuel loading, during plant heatup and the ascension to rated power, the nuclear steam supply system and the balance-of-plant'. system process variables sensed by the computer as digital or analog signals will become available. Verify that the computer is receiving correct values of sensed process variables and that the results of performance calculations of the nuclear steam supply system and the balance-of-plant are correct. At steady power conditions the Dynamic System Test Case will be performed.

14.2.12.3.13.4 Criteria Level 1 Not applicable.

Level 2 Programs OD-1, P1, and OD-6 will be considered operational when:

(1) The MCPR calculated by BUCLE and the process computer either:

14. 2-107

'WNP-2

a. Are in the same'uel'assembly and do not differ in value by more than 2% or,

b. For the case in which the NCPR calculated by the process computer is in a different assembly than that. calculated by BUCLE, for each assembly, the MCPR and CPR cal-culated by the two methods shall agree within 2%.

(2) The maximum LHGR calculated by BUCLE and the process computer either:

a. Are in the same fuel assembly and do not differ in value by more than 2%, or

b. For the case in which the maximum LHGR calculated by the process computer is in a di'fferent assembly than that calculated by BUCLE, for each assembly, the maximum LHGR and LHGR calculated by the two methods shall agree within 2%,.

(3) The MAPLHGR calculated by BUCLE and the process computer either: I

a. Are in the same fuel assembly and do not differ in value by more than 2%, or

b. 'or the case in which the MAPLHGR calculated by the process computer is in different assembly than that calculated by BUCLE, for each assembly, the MAPLHGR and APLHGR cal-culated by the two methods shall agree within 2%.

(4) The LPRM calibration factors calculated by BUCLE and the process computer agree to within 2%.

(5) The remaining programs will be considered opera-tional upon successful completion of the static and dynamic testing.

14.2-108

WNP-2 . AMENDMENT NO. 20 November 1981 14.2.12.3.14 Test Number 14 RCIC System 14.2.12.3.14.1 Purpose The purpose of this test is to verify the proper operation of the Reactor Core Isolation Cooling (RCIC) system over its expected operating pressure range.

14. 2. 12.3. 14. 2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing.

14.2. 12.3. 14.3 Description The RCIC system test consists of two parts: Injection to the condensate storage tank and injection to the reactor vessel. The initial CST injections consist of manual and automatic starts at 150 psi and at rated reactor pressure.

The pump discharge pressure during these tests is throttled to 100 psi above reactor pressure. This initial testing is done to demonstrate system operability and making initial controller adjustments. This is followed by vessel injections beginning with cold RCIC hardware. "Cold" being defined as a minimum three days without any kind of RCIC operation.

The vessel injections verify the adequacy of the startup tran-sient and also include steady state controller adjustments.

Five consecutive successful system initiations starting from cold conditions and with the same equipment settings are necessary to demonstrate system reliability. Two of these initiations are vessel injection tests with one performed using the controllers on the remote shutdown panel.

After final controller settings are determined, three CST injections at rated pressure and/or 150 psig pressure are done with initially cold RCIC equipment. These runs provide a bench mark for future surveillance testing and provide further assurance of system reliability.

A demonstration of extended operation of 30 minutes of con-tinuous running or until pump and turbine oil temperature is stabilized is scheduled at a convenient time during the test program, probably in conjunction with one of the system reliability tests. During thisto demonstration, automatic RCIC the suppression pool will be suction transfer from the CST performed to confirm system stability in this configuration.

14. 2-109

• ~ NNP-'2 AMENDMENT NO. 20 November 1981 During vessel injections all reactor steam is routed to the turbine bypass valves. The steam admission valves of the main and feedwater turbines should be closed whenever the 'moisture carryover threshold is reached.

14. 2. 12. 3. 14. 4 Criteria Level 1 The time from actuating signal to required flow must be less than 30 seconds at any reactor pressure between 150 psig (10.5/kg/cm2) and rated.

14. 2-109a

WNP-2 WNP-2 AMENDMENT NO. 7 November 1979 With pump discharge at any pressure between 150 psig (10.5 kg/cm~) and 1220 psig (85.8 kg/cm2), the required flow is 600 gpm. (The limit of 1220 psig includes a conservatively high value of 100 psi for line losses. The measured value may be used if available.)

The RCIC turbine must not trip off during startup.

If any Level 1 criteria will be restricted to thearepower not met, th'e reactor operation level defined by Figure 14.2-5. This restriction is in addition to any restrictions defined by the Technical Specification.

Level 2 The turbine gland seal consenser system sha3,1 be capable of preventing steam leakage to the atmosphere.

The differential pressure switch for the RCXC steam supply line high flow isolation trip shall be adjusted to actuate at 300% of the maximum required steady state flow.

14.2-110

14.2.12.3.15 : Test Number 15 Not Applicable 14.2-111

NNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3.16 Test, Number 16 Selected Process Temperatures 14.2. 12.3. 16.1 Purpose The purpose of this procedure is to (1) verify the setting of low flow control limiter for- the recirculation pumps to avoid coolant temperature stratification in the reactor 'pressure vessel bottom head region, (2) assure that the measured bot-tom head drain temperature corresponds to bottom head coolant temperature during normal operations and (3) identify any reactor operating modes during recirculation pump restarts or one pump operation that cause temperature stratif ication.

14.2.12.3.16.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Mariager has approved the test proce-dures and initiation of testing. System and test instrumen-tation have been calibrated.

14.2.12.3.16.3 Description The adequacy of bottom drain line temperature sensors will be determined by comparing it with recirculation loop coolant temperature when core flow is 100% of rated.

During initial heatup while at hot standby conditions, the bottom drain line temperature, recirculation loop suction tem-perature and applicable reactor parameters are monitored as the reciruclation flow is slowly lowered to either minimum stable flow or the low recirculation pump speed minimum valve position whichever is the greater. The effects of cleanup flow, CRD flow and power level will be investigated as opera-tional limits allow. Utilizing this data it can be determined whether coolant temperature stratification occurs and if so, what minimum recirculation flow will prevent it.

Monitoring the preceding information during planned pump trips and restarets 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 dermined if changes in operati,ng procedures are required.

14.2-112

WNP-2 AMENDMENT NO. 26 July 1982

14. 2. 12. 3. 16. 4 Criteria Level 1

a. The reactor recirculation pumps shall. not be started nor flow increased unless the coolant temperatures between the steam dome and bottom head drain are within 100 F (56 C).

b. The recirculation pump in an idle loop must not be started unless the loop suction temperature is within 50 F (28 C) of the steam dome temperature.

Level 2 Durinq two pump operation at rated core flow, the bottom head temperature as measured by the bottom drain line thermocouple should be within 30 F (17 C) of the recirculation loop temperatures.

14. 2-112a

BLANK WNP-2 AMENDMENT NO. 26 July 1982

14. 2. 12. 3. 16. 4 Criteria Level 1

a. The reactor recirculation pumps shall not be started nor flow increased unless the coolant temperatures between the steam dome and bottom head drain are within 100'F (56 C).

b. The recirculation pump in an idle loop must not be started unless the loop suction temperature is within 50 F (28'C) of the steam dome temperature.

Level 2 During two pump operation at rated core flow, the bottom head temperature as measured by the bottom drain line thermocouple should be within 30 F (17 C) of the recirculation loop temperatures.

14.2-113

WNP-2 AMENDMENT NO. 33 November 1983 14.2.12.3.17 Test Number 17 System Expansion 14.2.12.3.17.1 Purpose The purpose of this test is to verify that piping systems are free and unrestrained in regard to thermal expansion and that suspension components are functioning in the specified man-ner. This test also verifies that all accessible snubbers installed on safety-related systems whose normal operating temperature is greater than 250'F have adequate swing clear-ance to accommodate system thermal expansion.

The test also provides data for calculation of stress levels in nozzles and weldments.

14.2.12.3.17.2 Prerequisites Necessary Preoperational Tests have been completed. The pre-heatup examination program relating to component supports as contained in the WNP-2 Preservice Inspection Program Plan has been completed. The POC has reviewed, and the Plant Manager has approved the test procedure and initiation of testing. Instrumentation has been installed and calibrated.

14.2.12.3.17.3 Description During the Power Ascension Testing (PAT) Program, hot condi-tion piping support performance and settings will be verified in accordance with System Test Instruction (STI), "Piping System Expansion and.Vibration Tests." Hanger positions of major equipment and piping in the nuclear steam supply system and auxiliary systems will be prerecorded during the initial thermal cycle and after shakedown has taken place (normally about three cycles). At specified temperature intervals during initial system heatup and following cooldown, visual inspections are made by personnel certified to,Level II or Level III for VT-3 and VT-4 to assure components are free to move as designed. Adjustments are made as necessary.

Snubber thermal movement and swing clearance is verified during each inspection. For systems inspected that do not attain operating temperature, swing clearance for projected snubber movement will be verified by observation and/or calculation.

Devices for measuring continuous pipe deflections are mounted on main steam, recirculation, feedwater, RCIC, and selected safety/relief valve discharge lines. Motion measured during heatup is compared with calculated values.

14.2-114

WNP 2 ANENDMEHT NO. 29 March 1983 14.2.12 '.17.4 Criteria Level 1 Thermally induced displacement of system components shall be unrestrained, with no evidence of binding or impairment'pring hangers shall not be bottomed out or have the spring fully stretched.

Snubbers shall not reach the limits of their travel. The displacements at the established transducer locations used to measure pipe deflections shall not exceed the allowable values. The allowable values of displacement shall be based on not exceeding ASME Section IXX Code stress allowables.

Level 2 Spring hangers will be in their operating range (between the hot and cold settings).

Snubber settings must be in the operating range and should be about the midpoint of the total travel at operating tempera-ture, or as specified on the hanger detail drawing.

The displacements at the established transducer locations shall not exceed the expected values.

14. 2-115

WNP-2 AMENDMENT NO. 12 November 1980 14.2 12.3.18

~ Test Number 18 Core Power Distribution 14.2. 12.3. 18.1 Purpose I The purpose of this test is to determine the reproducibility of the TIP system readings.

14.2.12.3.18.2 Prerequisites The Preoperatonal Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. The TIp detector and dummy detector, ball valve time delay, core top and bottom limits, clutch, x-y recorder, and purge system will have been shown to be operational. Instrumentation has been 'alibrated and installed.

14.2.12.3.18.3 Description TIP reproducibility consists of a random noise component and a geometric component. The geometric component being due to variation in the water gap geometry and TIP tube orientation from TIP location to location. Measurement of these com-ponents is obtained by taking repetitive TIP readings at a single TIP location, and by analyzing pairs of TIP readings taken at TIP locations which are symmetrical about the core diagonal of fuel loading symmetry.

One set of TIP data will be taken at the 50% power level and at least one other set at 75% power or above.

The TIP data will be taken with the reactor operating with an octant symmetric rod pattern and at steady state conditions.

The total TIP reproducibility is obtained by dividing the standard deviation of the symmetric TIP pair nodal ratios by The nodal TIP ratio is def ined as the nodal BASE value of the TIP in the lower right half of the core divided by its symmetric 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 derived kp taking the square root of the average of the variances at nodal levels 5 through 22, where the nodal variance is obtained from the fractional deviations of the successive TIP values about their nodal mean value.

14. 2-116

WNP-2 AMENDMENT NO. 20 November 1981 The geometric component of TIP reproducibility is obtained by statistically subtracting the random noise component from the total TIP reproducibility.

14. 2.12. 3.18. 4 Criteria Level 1 Not applicable.

14.2-116a

BLANK WNP-2 AMENDMENT NO. 7 November 1979 Level 2 The total TIP uncertainty (including random noise and geo-metrical uncertainties) obtained by averaging the uncertain-ties for all data sets shall be less than 6.0%.

The data acquired for random noise uncertainty does not have specific acceptance criteria value and is used only to aid in the analysis of the TIP uncertainty.

14.2-117

I WNP-2 AMENDMENT NO. 26 July 1982 14.2.12.3.19 Test Number 19 Core Performance 14.2.12.3.19.1 Purpose The purposes of this test are a) to evaluate the core thermal power and b) to evaluate the following core perfor-mance parameters: 1) maximum linear heat generation rate (NLHGR), 2) minimum critical power ratio (NCPR) and 3) maxi-mum average planar linear heat generation rate (NAPLHGR).

14.2. 12.3. 19. 2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. System instrumentation installed and calibrated and test instrumentation calibrated.

14.2. 12.3. 19.3 Description The core performance evaluation is employed to determine the principal thermal and hydraulic parameters associated with core behavior. These parameters are:

Core flow rate Core thermal power level MLHGR NAPLHGR MCPR The core performance parameters listed above will be evaluated by manual calculation techniques described in Startup Test Instruction 19 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 2S on all thermal parameters (see Test Number 13), or the results must be corrected to do so. If the BUCLE and process computer results do not agree within 2% for any thermal parameter, the parameter calculated by the process computer will be corrected by a multiplication factor to bring it within the 2% criteria.

14. 2-1 18

WNP-2 AMENDMENT NO. 20 November 1981

14. 2.12. 3. 19. 4 Criteria Level 1 The Maximum Linear Heat Generation Rate (MLHGR) os any rod during steady-state conditions shall not exceed the limit specified by the Plant Technical Specifications.

The steady-state Minimum Critical Power Ratio (MCPR) shall not exceed. the limits specified by the Plant Technical Specifications.

The Maximum Average Linear Heat Generation Rate (MAPLHGR) shall not exceed the limits specified by the Plant Technical Specifications.

Steady-state reactor power shall be limited to rated MWT and values on or below the design flow control line. A core flow of 100 percent rated will not be exceeded.

Level 2 Not applicable.

14.2.12.3.20 Test Number 20 Electrical Output and Heat Rate 14.2.12.3.20.1 Purpose The purpose of this test is to demonstrate that the plant net electrical output and net,heat rate requirements are satisfied.

14.2.12.3.20.2 I

Prerequisites The Preoperatonal Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing.

14.2.12.3.20.3 Description The plant gross electrical output and net heat rate will be measured during sustained operation at rated conditions. The gross electrical output is defined as the gross electrical output mmeasured at the generator terminals and must be main-tainned for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. The net plant heat rate is defined as the thermal output from the reactor less the thermal content in the feedwater supplied to the reactro all divided by the net electrical output. All corrections for losses and auxi-liary loads will be agreed to prior to the start of the test.

14.2-119

WNP-2 ANENDblENT NO. 20 November 1981 The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> net plant heat rate test would normally be done although this is not necessary.

l4.2.12.3.20.4 Criteria Level l The guaranteed performance calls for a gross output af 1, 154,745 KWe at a reactor thermal power of 3322 NW and a net plant heat rate of 9,840 BTU/Kwhr.

14."2-119a

WNP, 2 BLANK

NNP-2 AMENDMENT NO. 12 November 1980

'14.2e12.3.21 Test Number 21 Core Power-Void Mode 14.2.12.3.21.1 Purpose The purpose of this test is to measure the stability of the core power-void dynamic response and to demonstrate that its behavior is within specified limits.

14.2.12.3.21.2 Prereguisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of, testing. System instrumentation installed and calibrated and test and instrumentation cali br ated.

14.2.12.3.21.3 Description The core power void loop mode, that results from a combina-tion of the neutron kinetics and core thermal hydraulic dynamics, is least stable near the natural circulation en/

of the rated 100 percent power rod line. A fast change in the reactivity balance is obtained by moving a very high worth rod only or 2 notches. The recorded response must 1

"be carefully examined for lower stability mode responses in the 0.4 Hz area. A special mid .pass filter is placed on the flux signals and dome pressure to emphasize this area, as well as to suppress noise in the signal background. The principal control systems will be in the normal modes for operating conditions at the test condition.

14.2.12.3.21.4 Criteria Level 1 The decay ratio must be less than 1.0 for each process variable that exhibits oscillatory response to control rpd movement.

Level 2 Not applicable 14.2-120

WNP-2 AMENDMENT NO. 7 November 1979 (DELETE) 14.2-121

WNP-2 AM ENDM ENT NO. 26 July 1982

14. 2. 12. 3. 22 Test Number 22 Pressure Regulator

14. 2. 12. 3. 22. 1 Purpose The purposes of this test are: a) 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, b) 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 and c) to demonstrate smooth pressure control transition between the control valves and bypass valves when reactor steam generation exceeds steam used by the turbine.

14.2. 12.3.22.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.22.3 Description The pressure set point will be decreased rapidly and then in-creased rapidly by about 10 psi (0.7 kg/cm2) and the response of the system will he measured in each case. It is desirable to accomplish the set point change in less than second. 1 At specified test conditions the load limit setpoint will be set so that the transient is handled by control valves, bypass valves and both. The backup regulator will be tested by simulating a failure of the operating pressure regulator so that the backup regulator takes over control. The response of the system will be measured and evaluated and regulator settings will be optimized. Because the near step transient occurs downstream of the log filter, this disturbance yields valuable stability data in the midfrequency range (i.e.,

0. 1-3. 0 Hz) .

The principal control systems w'ill be in their normal operating mode for the given test condition. In addition, at test conditions 3, 5, and 6 the test will be performed with the recirculation control system in the local manual control mode.

r

14. 2-122

WNP-2 AMENDMENT NO. 13 February 1981 14.2.12.3.22.4 Criteria Level 1 The decay ratio must be, less than 1.0 for each process variable that exhibits oscillatory response to pressure regulator changes.

Level 2 In all tests the decay ratio is expected to be less than or equal to 0.25 for each process variable that exhib'its oscillatory response to pressure regulator changes when the plant is operating above the lower limit setting of the Master Flow Controller.

Pressure control deadband, delay, etc., shall be small enough that steady-state limit cycles, if any, shall produce turbine steam flow variations no larger than +0.5% of rated flow as measured by the gross generated electrical power.

Optimum gain values for the pressure control loop shall be determined to give the fastest return from the transient condition to the steady-state condition within the limits of the above criteria.

During the simulated failure of the controlling pressure regulator, if the setpoint of the backup pressure regulator is optimumly set, the backup regulator shall control the transient such that the peak neutron flux and/or peak vessel pressure remain below the scram settings by-7.5%,and 10 psi respectively.

Following a +10 psi (0.7 kg/cm2) pressure setpoint adjustment, the time between the setpoint change and the occurrence of the pressure peak shall. be 10 seconds or less when in the recir--

culation POS mode.

14.2-123

WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.3.23 Test Number 23 Feedwater System 14.2. 12.3.23. 1 Purpose The purposes of this test are a) to adjust the feedwater control system for acceptable reactor water level control, b) to demonstrate stable reactor response to subcooling changes, c) to demonstrate the capability of the automatic core flow runback feature to prevent low water level scram following the trip of one feedwater pump.

14.2. 12.3.23.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.23.3 Description Reactor water level set point changes of approximately 5 to 6 in'ches (12.5 to 15.3 cm) will be used to evaluate and adjust the feedwater control system settings for all power and feedwater pump modes. The level set point changes will also demonstrate core stability to subcooling changes.

Under normal operation with one feedwater loop in manual, a manual flow step will be initiated and each loop's flow response will be determined.

One of the operating feedwater pumps will be tripped and the automatic recirculation flow runback circuit will act to drop, power to within the remaining capacity of the system. Prior to the performance of this test a review of the recirculation flow limit or calibration and trip logic will be performed to ensure that the runback circuit will function properly.

The condensate/feedwater system will be studied to determine the single failure that will cause the largest loss in- feed-water heating. This event will then be performed at between 80 and 908 power with the recirculation flow near its rated value other principal control systems will be in their normal

'he operating mode for the given test condition. In addition, at test conditions 3, 5 and 6 the level setpoint changes will be performed with the recirculation control system in the local manual contol mode.

14. 2-124

WNP-2 AMENDMENT NO. 20 November 1981 Pressure, flow and controller data will be taken at as high a power level as necessary to allow the determination of the maximum feedwater flow runout capability. These data will be compared with the FSAR values and the impact on thermal limits determined.

14.2. 12.3.23.4 Criteria Level 1 The decay ratio must be less than 1.0 for each process vari-able that exhibits oscillatory response to feedwater system changes.

For the feedwater heater loss test, the maximum feedwater tem-perature decrease due to a single failure must be less than or equal to 100 F. The resultant MCPR must be greater than the fuel thermal safety limit.

The feedwater flow runout capability must not exceed the assumed value in Chapter 1S, "Transient Analysis".

For the feedwater heater loss test, the increase in simulated heat flux cannot exceed the predicted level 2 value by more than 2%. The predicted value will be based on the actual test values of feedwater temperature change and power level.

14. 2-124a

~ WNP-2 BLANK

~ I a

WNP-2 AMENDMENT NO. 13 February 1981 Level 2 The decay ratio is expected to be less than or equal to 0.25 for each process variable that exhibits oscillatory response to feedwater system changes when the plant is operating above the lower limit of the Master Flow Controller.

The automatic core flow runback feature will prevent a scram from low water level with a 3-inch margin following a trip of one of the operating feedwater pumps.

With the condensate system operating normally, the control system shall prevent pump damage due to cavitation.

For the loss of feedwater heater test, the increase in simu-lated heat flux cannnot exceed the predicted value referenced to the actual feedwater temperature change and power level.

The open loop dynamic flow response of each feedwater actuator (turbine or value) to small (>10%) step disturbances shall be:

~Maximum time to 10% of a step disturbance < 1.1 sec.

Maximum time from 10% to 90% of a step disturbance 1.9 sec.

Settling time to within + 5% of the based upon step size) 14.0 sec.

final'alue

(%

Peak overshoot (% of step disturbance) 15%

The average rate of response of the feedwater actuator to large (>20% of pump flow) step disturbances shall be between 10 and 25% rated feedwater flow/second. This average response rate will be assessed by determining the time required to pass linearly through the 10 and 90% response points.

14. 2-125

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3.24'est Number 24 Turbine Valve Surveillance 14.2.12.3. 24.1 Purpose The purpose of this test is to demonstrate the acceptable procedures and maximum power levels for periodic surveillance testing of the main turbine, throttle, governor, interceptor, reheat stop and bypass valves without producing a reactor scr am.

14.2.12.3.24.2 'rerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.24.3 Description Individual main turbine control, stop and bypass valves are tested routinely during plant operation as required for tur bine Surveillance testing. At several test points the response of the reactor will be observed, and although it is not required, it is recommended that *the maximum possible power level for performance of these tests along the 100% load line,be established. First actuation should be between 45 and 65% power; and used to extrapolate to the next test point be-tween 70 and 90% power and ultimately to the maximum power test condition with ample margin to scram. Note proximity to APRM flow bias scram point. Each valve test will be manually initiated and reset. Rate of valve stroking and timing of the close-open sequence will be such that. the minimum practical disturbance 'is introduced. "If thtroking and timing rates are changed the test will be repeated to ensure acceptable performance of the periodic surveillance test.

14.2.12.3.'24.4'riteria Level 1 The decay ratio of any oscillatory response must be less then 1,.0.

Level 2

a. Peak neutron flux must be at least 7.5% below the scram trip setting. Peak vessel pressure must remain at. least 10 psi below the high pressure scram setting.

14.2-126

b. Peak steam flow in each line must remain 10%

below the high flow isolation trip setting.

c. The decay ratio of any oscillatory response must be less than 0.25, when operating 'above the minimum core flow of the recirculation master manual mode.

14.2-127

WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.3.25 Test Number 25 Main Steam Isolation Valves 1 4. 2. 12. 3. 25. 1 Purpose The purposes o'f this test are a) to functionally check the main steam line isolation valves (MSIVs) for proper operation at selected power levels, b) to determine reactor transient behavior during and following simultaneous full closure of all MSIVs, c) to determine isolation valves closure time at rated conditions, and d) to determine maximum power at which a single valve closures can be made without scram.

14.2.12.3.25.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-aures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.25.3 Description At 5% power or greater, both slow and fast single valve closure will be performed. A test of the simultaneous full closure of all MSIVs will be performed at greater than 75%

rated thermal power. Correct performance of the RCIC and relief valves will be shown. Reactor process variables will be monitored to determine the transient behavior of the system during and following the Main Steam Line (MSL) isolation. The maximum power conditions at which individual valve full closure tests can be performed without a reactor scram is to be established, and one individual valve full closure test will be performed on the 100% power load line to check ability to perform surveillance tests on this load line.

The MSIV closure times will be determined from the MSL iso-lation data by determining the time interval from de-energization of the MSIV pilot solenoids to the 90%, closed position plus 1/8 of the period of time between 10% closed and 90% closed positions.

14. 2-1 28

WNP-2 AMENDMENT NO. 7 November 1979 14.2.12.3.25.4 Criteria Level 1 Individual Valve Closure MSIV closure time, exclusive of electrical delay shall be no faster than 3.0 seconds (average of the fastest valve in each steam line) and no slower than 5.0 seconds, (each valve, not.

averaged). The electrical time delay at 100% open shall be

'less than or equal to 0.5 second and the fastest valve closure time shall be >2.5 seconds.

Full Reactor Isolation The positive change in vessel dome pressure occurring within 30 seconds after closure of all MSIV valves must not exceed the Level 2 criteria by more than 25 psi. The positive change in simulated heat flux shall not exceed the Level 2 criteria by more than 2% of rated value.

Feedwater 'control system settings must prevent flooding of the steam lines.

Level 2 Individual Valve Closure'uring full closure of individual valves peak vessel pressure must be 10 psi (0.7 kg/cm ) below scram, peak neutron flux must be 7.5% below scram, and steam, flow in individual lines must be 10$ below the isolation trip setting. The peak heat flux must be 5% less than its trip point.

Full Reactor Isolation The RCIC system shall adequately maintain water level. The re-lief valves must reclose properly (without leakage) following the pressure transient.

- The positive. change in vessel dome pressure and simulated heat flux occurring within the first 30'-seconds after the

'closure of all, MSIV must not" exceed the predicted values.

These 'values will be referenced to actual test conditions of initial power level and dome pressure and wi'll use BOL nuclear data. In addition, it will be corrected for the measured con-trol rod insertion speed and the time from the start of MSIV motion to the start of control rod motion.

14.2-129

WNP-2 AMENDMENT NO. 12 November 1980 14.2. 12.3. 26 Test Number 26 Relief U alves 14.2.12.3.26.1 Purpose The purposes of this test are a) to verify the proper oper-ation of the main system relief valves, b) to verify that the discharge piping is not blocked, c) to verify their proper seating following operation, d) to obtain signature infor-mation of relief valve response for subsequent comparisons, and e) to determine their capacities.

14.2.12.3.26.2 Prerequisites The Preoperational Tests have been completed, the POC has "

reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been .,

checked or AI cali br ated as appropri ate.

1-4'.2.12;3.26.3 Description C

The main steam relief valves will each be opened using the "manual" control mode so that at any time only one is open.

During heatup at 250 psig (17 5 kg/cm2), each valve will

~

be opened and closed to demonstrate proper functioning.

Plow verification of each relief valve will be determined at rated pressure ky observing bypass or control valve motion and by observing a change in discharge T/C readings.

Proper reseating of each relief valve will be verified by o bserv ation of temper atures in the relic f valve disch arge piping. At selected test conditions each valve will be manually actuated and appropriate system parameters recorded during the transient. Data analysis will include a com-parison of the system response during each of the valve actuations. Capacity of each relief valve will be deter-mined at rated pressure ky the amount of bypass or control valve closure required to maintain reactor pressure.

14.2.12.3.26.4 Criteria Level 1 There should be positive indication of steam discharge during the manual actuation of each valve.

h Q 14.2-130

The sum of capacity measurements from all relief valves shall be equal to or greater than rated,'2% corrected for inlet pressure of 1112 psig.

Level 2 Relief valve leakage shall be low enough that the temperature measured by the thermocouples in the discharge side of the valves returns to within 10 F (5.6oC) of the temperature recorded before the valve was opened. The thermocouples are expected to be operating properly.

The pressure regulator must, satisfactorily control the reactor transient and close the control valves or bypass valves by an amount, equivalent to the relief valve discharge.

The valve transients recorder signatures for each valve must be returned to San Jose for relative system response com-parison.

Each relief valve shall have a capacity between 90% and 135%

of its expected value 'corrected to an inlet pressure of 1112 psig.

No more than 25% of the relief valves may have an individual corrected flow rate that is less than expected.

The transient recorder signatures for each valve must be analyzed for relative system response comparison.

14.2-131

WNP-2 AMENDMENT NO. 20 November 1981 14.2. 1.3.27 Test Number 27 Turbine Trip and,Generator I

Load Rejection 14.2.12.3.27.1 Purpose The purpose of this test is to demonstrate the response of the reactor and its control systems to protective trips in the turbine and generator.

14.2. 12.3.27.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. All controls and interlocks are checked and instrumentatiog calibrated. The plant electrical- system will be aligned in the normal mode for the operating condition at which the test is performed.

14.2.12.3.27.3 Description Both the turbine and the main generator will be tripped at selected power levels. Several reactor and turbine operating parameters will be monitored to evaluate the response of the bypass valves, relief valves, and reactor protection system (RPS). Additionally, the peak values and change rates of reactor steam pressure and heat flux will be determined. The effect of recirculation pump overspeed, if any, will. be checked during the generator load rejection. The ability to ride through a load rejection within bypass capacity without a scram will also be demonstrated.

14.2.12.3.27.4 Criteria Level 1 For Turbine and Generator trips there should be a delay of less than 0.1 second following the beginning of control or stop valve closure before the beginning of bypass valve oening. The bypass valves should be opened to a point corresponding to greater than or equal to 80 percent of their capacity within 0.3 second from the beginning of control or stop valve closure motion.

14. 2-132

WNP-2 AMENDMENT NO. 13 February 1981 Feedwater system settings must prevent flooding of the steam line following these transients.

The two pump drive flow coastdown transient during the first three seconds must be equal to or faster than that specified in Test 30.

The positive change in vessel dome pressure occurring within 30 seconds after either generator or turbine trip must not exceed the Level 2 criteria by more than 25 psi.

The positive change in simulated heat flux shall not exceed the Level 2 criteria by more than 2% of the rated value.

14. 2-132a

BLANK AMENDMENT NO. 7 November 1979 Level 2 The MSIU shall not be tripped closed at anytime during the test transients.

The positive change in vessel dome pressure and in simulated heat flux which occur within the first 30 seconds after the initiation of either generator or turbine trip must not ex-ceed the predicted values.

Predicted values will be referenced to actual test conditions of initial power level and dome pressure and will use BOL (Beginning of Life) nuclear data. In addition, the predic-tions will be corrected for the measured control rod inser-tion time and the delay from beginning of turbine control valve or stop valve motion to the generation of the scram signal. The predicted pressure and heat flux will be cor-rected for the actual measured values of these two parameters.

For the Generator trip within the bypass valves capacity, the reactor shall not scram for initial thermal power values with-in that bypass valve capacity.

14.2-133

WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.3.28 Test Number 28 Shutdown From Outside The Main Control Room 14.2.12.3.28.1 Purpose To demonstrate that the reactor can be brought from a normal initial steady-state power level to the point where cooldown is initiated and under control with reactor vessel pressure and water level controlled from outside the main control room. In addition, the operation of the shutdown cooling/suppression pool cooling modes of the RHR system from the remote shutdown panel will be demonstrated.

14.2.12.3.28.2 Prerequisites The Preoperational Tests have been completed, the POC has =

reviewed and the Plant Manager has approved the test proce-

'dures and initiation of t'esting. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.28.3 Description The test will simulate the reactor shutdown following a main control room evacuation. The reactor will be scrammed from a normal steady-state condition and the MSIVs closed prior to evacuation in compliance with plant emergency operating procedures. However, the capability exists to manually scram the reactor and close the MSIVs from outside the control room. Following this event, the vessel water level and pressure will be controlled from the remote shutdown panel. During the test the control room staff will be at full strength to perform actions on systems not required for an emergency shutdown. Reactor pressure will be reduced via relief valve actuation and suppression pool cooling will be placed in service. When reactor pressure falls below 135 psig, RHR shutdown cooling will be placed in service in a controlled manner to reduce reactor coolant temperature by at least 50'F.

14. 2. 12. 3. 28. 4 Criteria Level 1 Not applicable.

Level 2 During a simulated main control room evacuation, the reactor must be brought to the point where cooldown is

14. 2-134

WNP-2 AMENDMENT hlO. 20 November 1981 initiated and under control. The reactor vessel pressure and water level are controlled using equipment and con-trols outside the main control, room.

14.2-134a

WNP-2 AMENDMENT NO. 12 Nov ember 1 980 14.2.12.3.29 Test Number 29 - Recirculation Flow Control 14.2.12.3.29.1 Purpose The purposes of this test are a) to demonstrate the core flow system's control capability over the entire flow control range, including valve position, core flow, neutron flux and load following modes of operation, and b) to determine that all electrical compensators and controllers are set for desired system performance and stability.

14.2.12.3.29.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. All controls are checked and i ns trumentat ion cali br ated.

14.2.12.3.29.3 Description The testing of the Recirculation Flow Control System follows a "build~ing block" approach while the plant is ascending from flow to high power levels. Components and inner control loops are tested first, followed by drive flow control and plant power maneuvers to adjust and then demonstrate the outer loop controller performance. By far the most extensive testing will be performed along the mid power load line where most of the systems final adjustments are determined. The core power distribution will be adjusted by control rods to permit broader range of maneuverability with respect to Preconditioning Cladding Interim Operating Management Recommendation (PCIOMR). In general, the controller dials and gains will be raised to meet the maneuvering performance objectives. Thus the system will be set to be the slowest that will perform satisfactorily, in order to maximize stabil-ity margins and to minimize equipment wear by avoiding controller overactivity. The other principal control systems will be in their normal operating mode for the given test condition.

Because of PCIOMR power maneuvering rate restrictions, the fast flow maneuvering adjustments are performed along a mid power rod line, and an extrapolation made to the expected results along the 100 percent rod.

14.2-135

WNP-2 AMENDMENT NO. 13 February 1981 The utility has the option to decide to:

a. Perform .the faster power changes on the 100 percent rod line that are greater than what the PCIOMR allow, or

b. To accept the mid power load line demonstrations as acceptable proof of maneuverability.

For immediate commercial operation, the Auto modes will be set slower, and the operator will limit Manual mode. If PCIOMR's 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.

14.2.12.3.29.4 Criteria Level 1 The transi'ent response of any recirculation system-related variables to any test input must 'not diverge.

Level 2 Recirculation 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.

The maximum rate of change of valve. position is 10 + 1%/sec.

The overshoot after a small position demand input (1 to 5%)

step shall be <10% of magnitude of input.

Gains shall be set to give as fast a response as possible to achieve a rise time of <0.45 seconds for small position demand inputs of to 5%. The delay time should be <0.15 seconds.

1 Flow loops are for the purpose, of maintaining equal steady state in the two loops. Flow loop gains should be set to correct a flow unbalance in about 15 seconds.

Flux overshoot to a flux demand step shall not exceed 2% of full power.

Flux controller time constants and gain shall be adjusted to give fastest possible response within the overshoot limit given in'4.2.12.3.29.3.a.'he response time shall be <2.8 seconds, when the magnitude of the demand step is within the setting of the flux error limiter. Nominal flux error setting is +20% of full power.

14.2-136

AMENDMENT NO. 13 February 1981 The master controller time constants and gains and steam pressure level setpoint parameters shall be set to give the response necessary to meet plant load following requirements as stated in the contract.

The response to a step input of less than 10% in load demand spall be such that the load demand error is less than 10% of magnitude of step within 10 seconds.

When a load demand step of greater than 10% is applied (N%),

error must be less than 10% of step in N seconds.

14.2-1)7

WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.3.30 Test Number 30 Recirculation. System I

14. 2. 12. 3. 30. 1 Purpose The purposes of this test are a) to determine transient responses and steady-state conditions following,recirculation pump trips at selected reactor power levels, b) to obtain recirculation system performance data, c) to verify .that no recirculation system cavitation occurs on the operable region of the power/flow map, and d) to verify that the feedwater control system can satisfactorily, control water level without a resulting turbine trip scram following single recirculation pump trips.

14.2.12.3.30.2 Prereguisites The Preoperational Tests have been completed and the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate. All control systems will be in their normal operating mode for the given test conditions.

14.2.12.3.30.3 Description Single recirculation pump trips with LFMG set breaker locked open will be made at near rated flow at 7SS and 100% power levels, by opening 6190 VAC breaker. Simultaneous trip of both recirculation pumps without transfer to LFMG set power supply will be made at near rated flow in Test Condition 3 by using the RPT two pump circuit trip system. Reactor operating parameters will be recorded during the transient and at steady-state conditions to experimentally determine the power and flow coastdown rates.

Both the jet pumps and the recirculation pumps will cavitate at conditions of high flow and low power where NPSH demands are high and little feedwater subcooling occurs. However, the recirculation flow will automatically runback upon sensing a decrease in feedwater flow, to lower the reactor power. The maximum recirculation flow is limited by appropriate stops which will run back the recirculation flow from the possible cavitation region. It will be verified that these limits are sufficient to prevent operation where recirculation pump or jet pump cavitation occurs.

14. 2-"138

WNP-2 AMENDMENT NO. 13 February 1981 14.2.12.3.30.4, Criteria Level 1 The two pump drive flow coastdown transient during the first 3 seconds must be equal to or greater than that specified on Figure 14.2-6.

Level 2 The reactor water level margin to avoid a higher level trip shall be >3.0 inches during the one pump trip.

The simulated heat flux margin to avoid a scram shall be >5.0%

both during the one pump trip and also during the recovery.

The APRM margin to avoid a scram shall be >7.5% during the one pump trip recovery.

Runback logic shall have settings adequate to prevent opera-tion in areas of potential cavitation.

Xf the Level 1 criterion for the two pump trip coastdown tran-sient is not met, the data shall be analyzed as soon as possible to insure compatibility with the safety analysis.

14. 2-138a

8 WNP-2 AM ENDM ENT NO. 26 July 1982

14. 2. 12. 3. 31 Test Number 31 Loss of Turbine-Generator and Offsite Power

14. 2. 12. 3. 31. 1 Purpose The purpose of this test is to determine the reactor trans-ient performance during the loss of the main generator and all offsite power, and to demonstrate acceptable performance of the station electrical supply system.

14. 2. 12. 3. 31. 2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-.

dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate. The plant electrical system will be aligned in the normal mode for the operating condition at which the test is performed.

14. 2. 12. 3. 31. 3 Description The loss of auxiliary power test will be performed at 20 to 30% of rated power. The proper response of reactor plant equipment, automatic switching equipment, and the proper sequencing of the diesel generator load will be checked.

Appropriate reactor parameters will be recorded during the resultant transient. The trip will be initiated by tripping the main turbine and opening the breakers supplying offsite power or preventing the closure of breakers supplying offsite power. The loss of offsite power conditions will be main-tained for a minimum of 30 minutes to demonstrate proper D-G system performance.

14. 2. 12. 3. 31. 4 Criteria Level 1 a ~ Reactor protection system actions shall prevent violation of full thermal limits.

b. All safety systems, such as the Reactor Protection System, the diesel generators, and HPCS must function properly without manual assistance, and HPCS and/or RCIC system action, if necessary, shall keep the reactor water level above the initiation level of the Low Pressure Core Spray, LPCI and ADS systems.

Level 2 Not applicable.

14.2-139

NNP-2 AMENDMENT NO. 25 June 1982 14.2.12.3.32 Not Applicable 14.2.12.3.33 Test Number 33 Piping Vibration 14.2.12.3.33.1 Purpose The purpose of this test is to verify that the reactor recirculation, feedwater, SRV discharge, and RCIC main'team, piping vibration are responding as predicted.

14. 2. 12. 3. 33. 2 Prequis ites The Preoperational Tests have been completed, the POC has reviewed, and the Plant Mahager has approved the test pro-cedures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.33.3 Description During reactor operation, it is desirable to show that de-structive level piping vibrations do not occur by at steady state and during various planned measuring'ibration transients.

14.2.12.3.33.4 Criteria Level 1 The measured amplitude (peak-to-peak) of main steam and re-circulation line vibration shall not exceed the maximum allowable displacements.

Level 2 The measured amplitude (peak-to-peak) of vibration shall not exceed the expected values.

14.2-140

WNP-2 'MENDMENT NO. 7 November 1979 (DELETED) 14.2-'141

NNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3.34 Test Number 34 'RPV Internals Vibration 14.2.12.3.34.1 Purpose The purpose of this test is to,provide information needed to confirm the similarity between the reactor internals 'design and the prototype with respect to flow induced vibration.

Testing is in response to NRC Regulatory Guide 1.20 for a vibration measurement program for nonprototype, Category IV reactor internals.

14.2.12.3.34.2 Prerequisites The Preoperational Tests have been comple'ted, the POC has reviewed and the Plant Manager has approved 'the test proce-dures and initiation of testing. Instrumentation has been checked or cali brted as appropriate.

14.2.12.3.34.3 Description During reactor operation, it is desirable to show that destructive levels of vibrations do not occur by measuring vibrations levels as steady-state and during various planned transients.

Sensors used for the measurements are resistance wire strain gages and accelerometers with double integrating output signal conditioning. Sensors will be installed in a manner to sense the most probable mode of vibration as indicated ky'nalysis.

The test program consists of hot power tests performed with the system at normal operating pressure and temperature.

During the vibration test the vibration amplitudes and fre-quencies obtained from the sensors mounted on the various will be monitored.- and recorded. The measured com-'onents amplitudes and frequencies are then compared to the 'cceptance criteria to assure that all measured vibration amplitudes are .

within acceptable levels.

14.2.12.3.34.4 Criteria Level 1 The peak stress intensity may exceed 10,000 psi (single amplitude) when the component deformed in a manner corresponding to one of its normal or natural modes but the fatigue usage factor must not exceed 1.0.

14.2-142

WNP-2 AMENDMENT NO. 12 November 1980 Level 2 The peak stress intensity shall not exceed 10,000 psi (single amplitude) when the component is deformed in a manner corresponding to one of its normal or natural modes. This is the low stress limit which is suitable for sustained vibration in the reactor environment for the design life of the reactor components.

14.2-142a

WNP-'2 BLMK

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3.35 Test Number 35 Recirculation System Flow C ali br ation 14.2. 12.3. 35. 1 Purpose The purpose of this test is to perform complete calibration of the installed recirculation system flow instrumentation.

14.2.12.3.35.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.35.3 Description During the testing program at operating conditions which allow the recirculation system to be operated at rated flow at rated power, the jet pump flow instrumentation will be adjusted to provide correct flow indication based on the jet pump flow. After the relationship between drive flow and core flow is established, the flow biased APRM/RBM system will be adjusted to match this relationship.,

14.2.12.3.35.4 Criteria Level 1 Not applicable.

Level 2 Jet pump flow instrumentation shall be adjusted such that the jet pump total flow'recorder will provide a correct core flow indication at rated conditions.

The APRM/RBM flow-bias instrumentation shall be adjusted to function properly at rated conditions.

14.2-143

WNP-2 AMENDMENT NO. 12 November 1980 14.2.12.3.36 Test Number 70 Reactor Water Cleanup System 14.2.12.3.36.1 Purpose The purpose of this test is to demonstrate specific aspects of the mechanical operability of the Reactor Water Cleanup System. (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. )

14.2.12.3.36.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

~ ~

14.2.12.3.36.3 Description With the reactor at rated temperature and pressure process variables will be recorded during steady state operation in three modes as defined ky the System Process Diagram:

Blowdown, Hot Standby, and Normal.

14.2.12.3.36.4 Criteria Level 1 Not applicable.

Level 2 The temperature at the tube side outlet of the non-regenerative heat exchangers shall not exceed 130'F in the blowdown mode and shall not exceed 120'F in the normal mode.

The pump available NPSH will be 13 feet or greater during the hot standby mode defined in the process diagrams.

The cooling water supplied to the non-.regenerative heat exchangers shall be within the flow and outlet temperature limits indicated in the process diagrams. (This is applicable to "normal" and "blowdown" modes.)

14.2-144

WNP-2 AHENDMENT NO. 33 November 1983 14.2.12.3.37 Test Number 71 Residual Heat Removal System 14.2.12.3.37.1 Purpose The purpose of this test is to demonstrate the ability of the Residual Heat Removal (RHR) System to remove heat from the reactor system so that the refueling and nuclear system ser-vicing can be performed.

14.2.12.3.37.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.37.3 Description During the- first suitable reactor cooldown, the shutdown cooling mode of the RHR system will be demonstrated. Unfor-tunately, 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 cooldown rate of the vessel if both RHR heat exchangers are used simultaneously, therefore, the demonstration is limited by the cooldown rate.

14.2-145

WNP-2 AMENDMENT.NO. 33 November 1983 14.2.12.3.37.4" Criteria Level 1 The transient response of any system-related variable to any test input must not diverge.

Level 2 The RHR system shall be capable of operating in the suppres-sion pool cooling and shutdown cooling modes (with both one and two heat exchangers). System-related variables may con-tain 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.

14.2-146

NIP-2 AMENDMENT NO. 26 July 1982 l4.2.12.3.38 .Test Number 72 Drywell Atmosphere Cooling System 14.2.12.3.38.1 "

Purpose The purpose of .this test is to verify the ability of the Drywell Atmosphere Cooling System to maintain design condi-tions in the drywell during operating conditions and post scram conditions.

14.2.12.3.'38.2 Prerequisites The Preoperational Tests have been completed,-the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.3.38.3 Description During heatup and power operation, data will'e taken to ascertain that the drywell atmospheric conditions are within design limits.

14.2.12.3.38.4 .Criteria Level 1 Not Applicable Level 2 The drywell cooling system shall maintain drywell air temperatures and humidity at or below the design values as specified for the NSSS equipment.

14. 2-147

WNP-2 AMENDMENT NO ~ 30 June "1983

14. 2 ~ 12. 3. 39 'Test Number 73 Cooling Water Systems

14. 2. 12. 3. 39.1 Pur pose The purpose of this test is to verify that the heat removal per formance of the standby service water (SW) system, the reactor building -closed cooling water (RCCW) system, and t'e turbine building service water (TSW) system is adequate ~

14. 2.12 3. 39

~ ~ 2 Prerequisites The preoperational tests have been completed, the POC has reviewed and the plant manager has approved the test proce-dures and initiation of testing., Instrumentation has been checked or calibrated as appropriate ~

14. 2 12. 3. 39- 3

~ Description The SW, the RCCW, and the TSW systems'eat exchanger heat transport capabilities will be verified. Verification will be conducted in the following manner. The system water flow rate through each heat exchanger will be measured. The system water temperature drop across each heat exchanger will also be m asured. From these acquired water flow rates and temperature drop data, the heat transport rates will be calculated. Where available, the calculated heat transport data will be compared directly with design calculations to determine acceptability. For those systems in which no design calculations of the heat transport rate have been directly calculated, the heat removal performance of the particular heat exchanger will be considered acceptable if the components serviced by the cooling system exhibit proper operation. If proper performance is.not experienced, adjustments in the heat transport capability (i.e., increased flow to the heat exchanger or increased flow to a particular load) would be made. In addition to the heat exchanger heat transport rate verification, the actual SW pump head will be determined for all three SW pumps. This actual SW pump head wi11 be compared to the design requirements for acceptability.

14. 2. 12. 3. 39. 4 Criteria La v'el 1 Not applicable.

14 2- 148

~

WNP-2 AHENlMENT NO. 30 June 1983 Level 2 The system heat transport parameters either meet the require-ments of the design specifications, or provide adequate cool-ing to the components serviced such that they operate satisfactorily.

14. 2-148a

WNP-2 WNP-2 AMENDMENT NO. 20 November 1981 14.2.12.3.40 Test Number 74 Off-gas System 14.2.12.3.40.1 Purpose The purposes o'f this test are to verify the proper operation of the Offgas System over its expected operating parameters and to determine the performance of the activated carbon adsorbers.

14.2.12.3.40.2 Prerequisites The Preoperational Tests have been completed, the POC has reviewed and the Plant Manager has approved the test proce-dures and initiation of of testing. Instrumentation has been checked or calibrated as appropriate. The Carbon Adsorber Vault Refrigeration System is available to the extent necessary to conduct the test.

14. 2. 12. 3. 40. 3 Description The pressure, temperature, relative humidity, system flow, and percentage of radiolytic hydrogen in the off-gas are periodi-cally monitored during startup and at steady-state conditions.

Prior to initial steam flow to the main condenser, charcoal bed hold-up times will be measured experimentally using a pulsed Kr-85 gas injection technique. The charcoal bed dynamic absorption coefficient will then be determined by established analytical methods. The performance of the cata-lytic recombiner will be compared with the Catalyt;ic Recombiner Guaranteed Performance Curve.

14.2.12.3.40.4 Criteria Level 1 The release of radioactive gaseous and particulate effluents must not exceed the limits specified in the site technical specifications. There shall be no loss of flow of dilution steam to the noncondensing stage when the steam jet air ejec-tors are pumping.

14.2-149

Level 2 The system flow, pressure, temperature, and relative humidity shall comply with design specifications. The catalytic recombiner, the hydrogen analyzer, the activated carbon beds, and the filters shall be performing their required function.

14.2-150

WNP-2 AMENDMENT NO. 7 November 1979 TABLE 14. 2-1 PREOPERATIONAL TESTS Subsection Reference Test Title 14.2.12.1.1 Reactor Feedwater System Preoperational Test 14.2.12.1.2 Condensate System Preoperational Test 14.2.12.1.3 Fire Protection System Preoperational Test.

14. 2. 12. l. 4 Reactor Water Cleanup System Preoperational Test 14.2.12.1.5 Standby Liquid Control System Preoperational Test

14. 2. 12. l. 6 Nuclear Boiler System Preoperational Test 14.2.12.1.7 Residual Heat, Removal System Preoperational Test

14. 2. 12. 1. 8 Reactor Core Isolation Cooling System Preoperational Test

14. 2. 12. 1. 9 Reactor Recirculation System and Control Preoperational Test

14. 2. 12. 1. 10 Reactor Manual Control System Preoperational Test

14. 2. 12. l. 11 Control Rod Drive Hydraulic System Preoperational Test 14.2.12.1.12 Fuel Handling and Vessel Servicing Equipment Preoperational Test 14.2.12.1.13 Low Pressure Core Spray System Preoperational Test, 14.2-151

AMENDMENT NO. 7 WNP-'2 November 1979 TABLE 14.2-1 (Continued)

Subsection Reference Test Title

14. 2. 12. l. 14 High Pressure Core Spray Preoperational Test 14.2.12.1.15 Fuel Pool Cooling and Cleanup System Preoperational Test

14. 2. 12. l. 16 Leak Detection System Preoperational Test.

14.2.12.1.17 Liquid and Solid Radwaste System Preoperational Test

14. 2. 12. 1. 18 Reactor Protection System Preoperational Test 14.2.12.1.19 Neutron'Monitoring System Preoperational Test

14. 2. 12. l. 20 Traversing In-Core Probe System Preoperational Test 14.2.12.1.21 Rod Worth Minimizer System Preoperational Test 14.2.12.1.22 Process Radiation Monitoring System Preoperational Test

14. 2. 12. l. 23 Area Radiation Monitoring System Preoperational Test 14.2.12.1.24 Process Computer Interface System Preoperational Test 14.2.12.1.25 Rod Sequence Control System (RSCS)

-Preoperational Test 14.2.12.1.26 Remote Shutdown Preoperational Test 14.2-152

WNP-2 AMENDMENT NO ~ 7 November 1979 TABLE 14.2-1 (Continued)

Subsection Reference Test Title 14.2.12.1.27 Offgas System Preoperational Test 14.2.12.1.28 Environs Radiation Monitoring System Preoperational Test 14.2.12.1.29 Main Steam System 14.2.12.1.30 Radwaste Building HVAC System Preoperational Test 14.2.12.1.31 Closed Cooling Water System Preoperational Test

14. 1. 12. 1. 32 Primary, Containment Atmospheric Control System 14.2.12.1.33 Primary Containment Cooling System

14. 2. 12. 1. 34 Primary Containment Instrument, Air System

14. 2. 12. 1. 35 Primary Containment Atmospheric Monitoring System 14.2.12.1.36 Standby Gas Treatment System 14.2.12.1.37 Loss of Power and Safety Testing 14.2.12.1.38 Deleted 14.2.12.1.39 Deleted 14.2.12.1.40 Deleted 14.2.12.1.41 Instrument Power System 14.2.12.1.42 Emergency Lighting 14.2.12.1.43 Standby AC Power System 14.2-153

WNP-,2 AMENDMENT NO- 7 November 1979 TABLE 14.2-1 (Continued)

Subsection Ref erence Test Ti't'le 14.2.12.1.44 250 Vdc Distribution System 14.2.12.1.45 125 Vdc Distribution System 14.2.12.1.46 24 Vdc Distribution System 14.2.12.1.47 Plant Service Water System 14.2.12.1.48 Standby Service Water System 14.2.12.1.49 Plant Communication System

14. 2. 12. 1. 50 Reactor Building Emergency Cooling System 14.2.12.1.51 Control Cable and Critical Switchgear Rooms HVAC System 14.2.12.1.52 Standby Service Water pumphouse HGV System 14.2.12.1.53 Reactor Building Crane

14. 2. 12. 1. 54 Primary Containment integrated leakrate test

14. 2. 12. l. 55 Secondary Containment integrated leakrate test 14.2.12.1.56 Diesel Generator Building H&V System Preoperational Test 14-2-154

TABLE 14.2-2 MAJOR PLANT TRANSIENTS TEST CONDITION APPROXIMATE POWER (4 Rated) 20-25 60-75 95-100 APPROXIMATE CORE TEST NO. TEST TITLE FLOW (8 Rated) 37 100 100 23 Feedwater Pump Trip 23 Loss of Feedwater Heating 25 MSIVs (All valves, Full Isolation) 27 T-G Stop Valve Fast Close 27 T-G Control Valve Fast Close 28 Shutdown from Outside Control Room 30 .Recirc. Pump Trips 31 Loss of Gen. & Offsite Power Test Condition 1r2

TABLE 14 ~ 2-3 STABILLITY TESTS TEST CONDITION APPROXIMATE POWER (8 Rated) 20 40 60-75 60-75 95-100 40-50 APPROXIMATE CORE TEST NO. TEST TITLE FLOW (8 Rated) 37 50 100 55 100 NC 21 Core Power Void Mode Response X X X 22 Press. Reg. Setpoint Changes X X X X X X 22 Press. Reg. Backup Regulator X X X X X X 23 FW System: Water Level Setpoint Change X X X X X 23 FW System: 'Heater~.Loss X 24 Turbine Valve Surveillance X 29 Recirculation Flow Control System X X X Test Condition 1 2 0

TABLE 14,2-4 STARTUP TEST PROGRAM COLO I

ST I TEST OR HEAT TEST CONDITIONS No, TEST NAME OPEN RPV UP I 2 3 4 5 6 WARRANTY I Chemical 4 Radiochemical X X X 2 Radiation Measurements 3 Fuel Loading 4 - Full Core Shutdown Margin X" X2 X2 X2 X

6 SRM Perf. 4 Control Rod Seq.

7 Not Applicable 8 Not Applicable 9 Water Level Reference Leg Temp.

jleasurements IG IRM Performance 11 LPRM Calibration 12 APRM Calibration X X X X 13 Process Computer X3 14 >CICS -X 15 Not Applicable 16 Selected Process Temperatures X X X

TABLE 14.2-4 (Continued)

COLD STI I TEST CR HEAT TEST CONDITIONS No, TEST NAME OPEN RPV UP I 2 4 5 17 System Expansion X X 18 Core Power Distribution 19 Core Performance 20 Electrical Output and Heat Rate 21 Core Power-Void Mode Response 22 Pressure Regulator: Setpoint Changes X,BP X,BP X,no M,BP X,BP X,BP,M X,M,BP Backup Regulator X,BP X,BP X,no M,BP X,BP X,no BP,M X,M,BP 25 FW System: FW Pump Trip M 14 Water Level Setpolnt Change X,M X,M Heat Loss x>>

Maximum Runout Capabll.ity 24 Turbine Valve Surveillance X4 X5,SP X7i8,SP 25 MS I Vs: Each -Va I ve x x>s-One Valve X4,SP X5iBi7,SP Full Isolation X2,10,13 S 26 Relief Valves: Flow Demonstration X4,13 Operational X4 O

TABLE 14.2-4 (Continued)

COLO I

STI TEST OR HEAT TEST CONDITIONS No TEST NAME OPEN RPV UP I 2 3 4 5 WARRANTY 27 Turbine Stop Valve Trip X2~13 SO Generator Load Rejection X,BP X2~13~15~SO 28 Shutdown From Outside C Room 29 Recirculation Flow Control System M4,X4 X4'4 M5~A5,X5 L4,A4 L4,M4 A4 30 Recirc. System: X13, 15 X13 15 Trip One Pump Trip Two Purrps X13, 15 X4, 13 X5, 13,15 X X'3 System Performance X'5 Non~vlt. Veri f.

31 Loss of T-G Offsite Power X2'b SD 32 Not Applicable 33 Piping Vibration 34 RPV Internals Vibration X4 X4 X5 X5 35 Recirc. System Flow Calibration 36-69 Not Applicable 70 Reactor Water Cleanup System 71 Residual Heat Renaval System

TABLE 14.2-4 (Continued)

COLD 1

ST I TEST OR HEAT TEST CONDITIONS No, TEST NAME OPEN RPV UP I 2 3 4 5 WARRANTY 72 Drywell Atmosphere Cooling 73 Cooling Water System 74 Off Gas System I See Figure 14.2-3 for Test Conditions region map. L = Local Position Coamand Mode Operation, POS 2 Perform Test 5, timing of 4 slowest control rods M = Flux Command Mode Operation, FLX in conjunction with these scrams.

X = Combined Flow Command tiode Operation, FLO

BLANK TABLE 14.2-4 (Continued)

STARTUP TEST PROGRAM 3 Between Test Conditions 1 and 3 A = Automatic Load Following Mode Operation, ALF 4 Between Test Conditions 2 and 3 SP = Scram Possibility 5 Between Test Conditions 5 and 6 6 DELETED SD = Scram Definite 7 Future maximum power test point BP = Bypass Valve Response 8 Determine maximum power without scram

• = Do either Stop Valve or Control 9 DELETED Valve Trip 10 DELETED 11 DELETED 12 80 90 8 Power.

13 Do STI 33 in conjunction with this test.

14 Demonstrate Recirculation System Runback Feature.

15 Perform STI 34 in conjunction with this Test.

0

AMENDMENT NO. 7 NOVEHBER, 1979 ASSISTANT DIRECTOR ASSISTANT DZRECTOR ASSISTANT DIRECTOR TECHNOLOGY PROJECTS GENERATION QUALITY ASSURANCE ENGINEERING PROJECT PLANT TEST 6 STARTUP DIVISION MANAGER DIVISION MANAGER MANAGER MANAGER PROGRA'%ANAGER I

I

• OPERATIONAL QUALITY STARTUP PLANT OPERATIONS ASSURANCE J I SUPERINTENDENT ADMINZSTRATIVE SUPERINTENDENT DEPT MANAGER PROJECT (NNP-2) I SUPERVISOR 4

ENGINEERING MANAGER TEST GROUP SUPERVISOR STARTUP SUPPORT TEST GROUP I SUPERVISOR TEST GROUP SUPERVISOR

---

-MATRIX MANAGEMENT QA AUDIT FUNCTION

• REPORTS ADMINISTRATIVELYTO TEST AND STARTUP PROGRAMS MANAGER HASHIHGTON PI8LIC PONER SUPPLY SYSTEM TEST ANO STARTUP RELATION TO FIGURE NUCLEAR PRMECT HO. 2 OTHER MPPSS OEPARTHEHTS

t i

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AMENDMENT NO. 7 November 1979 ASSISTANT DIRECTOR GENERATION TEST 8, STARTUP PLANT PROGRAMS MANAGER MANAGER (T'ERAT I ONS GAL ITY ASSURANLE OTHER WPPSS WtP-2 TEST II STARTUP TEST It STARTUP SUPERINTENDENTS SUPERINTENDENT AEp NSSS i, PROJECT STARTUP SUPPORT TEST GROUP TEST GROUP TEST GROUP SUP ERV I SOR SUPERVISOR SUPERVISOR TEST TEST TEST ENGI NEER ENG I NEER ENGINEER STARTUP SUPPORT gA AUDIT FUNGI'ION

" REPORTS ADMINISTRATIVELYTO TEST AND STARTUP PROGRAMS MANAGER FIGURE WASHINGTON PUBLIC POWER SUPPLY SYSTEH TEST AND STARTUP ORGANIZATION 1%,2-2 NUCZZAR PRMECT NO~ 2

rr S I

~gDMENT MO. 20 goveinber 1981 130 A. NATURALCIRCULATION 120 B. LOW RECIRCULATION PUMP SPEED VALVEMINIMUMPOSITION (fltQNCkTE p)ulled)

Q )oooo C. LOW RECIRCULATION PUMP SPEED VALVEMAXIMUMPOSITION 40ILG PLOu) PHD D. RATED RECIRCULATION PUMP SPEED VALVEMINIMUMPOSITION 110 E. ANALYTICALLOWER LIMITOF MASTER POWER FLOW CONTROL F. ANALYTICALUPPER LIMITOF MASTER POWER FLOW CONTROL NO. 6 100 90 105% ROD LINE /QTS) biota PION 100% ROD LINE 80 NO. 5 75% ROD LINE NO. 3 o 70 60 C D

8 50 A NO. 4 so'/o 8'ING 40 NO. 2 30 MINIMUMFLOW CONTROL LINE FOR TRANSFER TO 100'YQ SPD 20 CAVITATIONREGION RECOMMENDED STARTUP PATH 10 NO. 1 10 20 30 40 50 60 70 80 90 100 110 PERCENT CORE FLOW CONDITION (TC) 1 BEFORE MAIN GENERATOR SYNCHRONIZATION AND RECIRC PUMPS OPERATING ON LOW FREQUENCY POWER SUPPLY PEDA hl'ROCII4ATG4'f 5 tO 20 8~61 TH601oiIL P>I BETWEEN 50% AND 75% CONTROL ROD LINES, AT OR BELOW THE ANALYTICAlLOWER LIMITOF MASTER FLOW CONTROL MODE FROM 50% TO 75% CONTROL ROD LINES AND CORE FLOW BETWEEN 80% AND MAXIMUMALLOWABLE NATURALCIRCULATION AND WITHIN 5% OF THE INTERSECTION WITH 100% ROD LINE MID.POWER RANGE WITHIN 5% OF 100% CONTROL ROD LINE AND 0 TO+5% CORE FLOW OF THE MINIMUMFLOW LINE, FOR MASTER FLOW CONTROL IN MANUALMODE, AND FOR AUTOMATICPOWER CONTROL IN AUTO MODE WITHIN 0 TO -5% OF RATED THERMAI. POWER, AND WITHIN 5% OF RATED CORE FLOW RATE WASHINGTON PUBLIC POWER SUPPLY SYSTEM FIGURE TEST CONDITION REGION DEFINITION NUCLEAR PROJECT NO. 2 '14.2-3

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