ML17284A513

Amend 63 to License NPF-21,revising Tech Spec Sections 6.5.1.2 & 6.8.2 Re Changes of Position Titles & Responsibilities of Designated Positions

ML17284A513
Person / Time
Site:	Columbia
Issue date:	09/08/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
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ML17284A514	List: ML17284A513 ML17284A515
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NUDOCS 8809160179
Download: ML17284A513 (17)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

63 License No.

NPF-21 1.

The Nuclear Pegulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee),

dated April 21, 1987 as revised by letter dated Nay 10, 1988 complies with the standards and requirements of the Atomic Energy Act of

1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the. public, and (ii) that such activities will be'onducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

E.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

88092 601 79 8g09P8 PDR ADOCK 05000397 PDC 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No.

NPF-21 is hereby amended to read as follows:

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

63

, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COYiNISSION

Attachment:

Changes to the Technical Specifications George W. Knighton, Director Project Directorate V

Division of Reactor Projects

- III, IV, V and Special Projects Date of Issuance:

September 8,

1988

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September 8,

1988 ENCLOSURE TO LICENSE AMENDMENT NO. 63 FACILITY OPERATING LICENSE NO.

NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

REIIOVE XV111 INSERT XV111 XX xx(a) 6-1 6-2 6-3 6-4 6-5 6-14 XX xx(a) 6-1 6-2 6-3 6-14 Overleaf pages are also provided for your convenience.

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INDEX DESIGN FEATURES SECTION

'AGE

5. 1 SITE Exclusion Area.

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5-1 Low Population Zone.

5-1 Unrestricted Areas and Site Boundary for Radioacti Gaseous and Liquid Effluents.

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5.2 CONTAINMENT Configuration.

5-1 Design Temperature and Pressure...

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5.3 REACTOR CORE Fuel. Assembl ies.

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5-5 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature..

5"5 Volume

5. 5 METEOROLOGICAL TOWER LOCATION....

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5-5 5-6 5.6 FUEL STORAGE

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5"6 Drainage Capacity...

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5 6 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.....

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5 6 WASHINGTON NUCLEAR - UNIT 2 Xvii

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X INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY...........,.................................

6-1 6.2 ORGANIZATION...............................................

6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS......................

6-1

6. 2. 2 UNIT STAFF............................................

6"1 6.2.3 NUCLEAR SAFETY ASSURANCE GROUP.....................

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6 7 COMPOSITION.........

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6 7 RESPONSIBILITIES......................................

6-7 RECORDS....

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6 7

6. 2.4 SHIFT TECHNICAL ADVISOR..........

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6. 3 UNIT STAFF UALIFICATIONS..................................

6-7

6. 4 TRAINING.

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6. 5 REVIEW AND AUDIT..............

6-8 6.5.1 PLANT OPERATIONS COMMITTEE (POC)......................

6-8 FUNCTION...........

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COMPOSITION.

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ALTERNATES

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6 8 MEETING FREQUENCY.

6-8 QUORUMo

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o 6 8 RESPONSIBILITIES.................................

6"9 RECORDS.........................

6-10 6.5.2 CORPORATE NUCLEAR SAFETY REVIEW BOARD (CNSRB).........

6-10 FUNCTION............,........................,.

6 10 COMPOSITION ~

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6 10 ALTERNATES............................................

6-10:

WASHINGTON NUCLEAR - UNIT 2 XV111 Amendment No.

63

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE CORPORATE NUCLEAR SAFETY REVIEW BOARD (Continued)

CONSULTANTS o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

6 11 MEETING FREQUENCY....................................

6-11 UORUMo ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~

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RECORDS o ~ o ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ o o ~ o% ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

6 13 6o6 REPORTABLE OCCURRENCE ACTION..............................

6-13 6.7 SAFETY lIMITVIOLATION....................................

6-14

6. 8 PROCEDURES AND PROGRAMS...................................

6-14 6.9 REPORTING RE UIREMENTS....................................

6-16 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES...........

6-16 STARTUP REPORT.......................................

6-16 ANNUAL REPORTS......................,................

6"16 MONTHLY OPERATING REPORTS............................

6-17 REPORTABLE OCCURENCES..............................

PROMPT NOTIFICATION WITH 'WRITTEN FOLLOWUP..........

6-17 6-17 THIRTY DAY WRITTEN REPORTS...........................

6-19 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT...

6-20 SEMIANNUAl. RADIOACTIVE EFFLUENT RELEASE REPORT.......

6-21 6.9.2 SPECIAL REPORTS......................................

6-22

6. 10

6. 11 RECORD RETENTION.................

RADIATION PROTECTION PROGRAM...........................

6-22 6-24

6. 12 HIGH RADIATIONAREA............. - -. -.. -. -. -. - -.... -. -

6-24

6. 13 PROCESS CONTROL PROGRAM..................................

6-25

6. 14 OFFSITE DOSE CALCULATIONMANUAL...........................

6-25 6.15 MAJOR CHANGES TO RADIOACTIVE LI UID GASEOUS AND SOLID WASTE TREATMENT SYS EMS............................

6-26 WASHINGTON NUCLEAR - UNIT 2 XIX Amendment Na.

16

LIST OF FIGURES INDEX FIGURE

3. 1. 5-1

3. 1. 5-2 SODIUM PENTABORATE TANK, VOLUME VERSUS CONCENTRATION, REQUIREMENTS.........................................

3/4 1-22 PAGE SODIUM PENTABORATE SOLUTION SATURATION TEMPERATURE...

3/4 1-21 3.2. 1"1 302.1 2

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR183........................

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR233........................

3/4 2-2 3/4 2-3 3.2.1-3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE BUNDLE EXPOSURE ANF 8x8 RELOAD FUEL..

3/4 2-4

3. 2. 1"4

3. 2. 1"5 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR183................................

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR233....................

3/4 2-4A 3/4 2-4B 3.2.3 1

3. 2. 4-1 3.2. 6-1 30207 1

3. 4. 1. 1-1 3.4. 6. 1-1 3.4.6.1-2

4. 7-1 3.9. 7-1 B 3/4 3-1 OPERATING REGION LIMITS OF SPEC.

3.2.7.

3/4 2-14 THERMAL POWER LIMITS OF SPEC.

3.4. 1.1-1..............

3/4 4-3a MINIMUM REACTOR VESSEL METAL TEMPERATURE VERSUS REACTOR VESSEL PRESSURE (INITIALVALUES)......

3/4 4-20 MINIMUM REACTOR VESSEL METAL TEMPERATURE VERSUS REACTOR VESSEL PRESSURE (OPERATIONAL VALUES).........

3/4 4-21 SAMPLE PLAN 2)

FOR SNUBBER FUNCTIONAL TEST..........

3/4 7-15 HEIGHT ABOVE SFP WATER LEVEL VS.

MAXIMUM LOAD TO BE CARRIED OVER SFP...

3/4 9-10 REACTOR VESSEL WATER LEVEL............

B 3/4 3"8 REDUCED FLOW MCPR OPERATING LIMIT....................

3/4 2-8 LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE ANF 8x8 RELOAD FUEL..........

3/4 2-10 OPERATING REGION LIMITS OF SPEC. 3.2.6...............

3/4 2-12 WASHINGTON NUCLEAR - UNIT 2 XX Amendment No.

63

LIST OF FIGURES INDEX GURE 1 374.4.6-1 FAST NEUTRON FLUENCE (E>lMeV) AT 1/4 T AS A FUNCTION OF SERVICE LIFE..............

AGE B 3/4 4-7

5. 1-1

5. 1-2

5. 1-3 EXCLUSION AREA BOUNDARY LOM POPULATION ZONE..................................

5-2 5-3 UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS.............

5-4 WASHINGTON NUCLEAR " UNIT 2 xx(a)

Amendment No.

63

6. 0 ADMINISTRATIVE CONTROLS

6. 1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6. 1.2 The Shift Manager (or during his absence from the control

room, a

designated individual) shall be responsible for the control room command func-tion.

A management directive to this effect, signed by the Director of Power Generation shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.

The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.

These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions.

These requirements are documented in the WNP-2 FSAR and updated in accordance with 10 CFR 50.71.

b.

The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary f'r safe operation and maintenance of the plant.

C.

d.

e.

The Assistant Managing Director for Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

The individuals who train the operating staff and those who carry out health physics functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

The organization responsible for the overall quality assurance functions shall report to the Supply System Managing Director.

6.2.2 UNIT STAFF a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; WASHINGTON NUCLEAR - UNIT 2 6-1 Amendment No. 63

ADMINISTRATIVE CONTROLS UNIT STAFF (continued) b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

In addition, while the unit is in OPERATIONAL CONDITION 1, 2, or 3, at least one licensed Senior Operator shall be in the control room.

c.

A Health Physics Technician" shall be on site when fuel is in the reactor and at least one fully qualified chemistry technician shall be on site in OPERATIONAL CONDITION 1, 2, or 3; d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; e.

A site fire brigade of at least five members shall be maintained on site at all times".

The fire brigade shall not include the Shift

Manager, the Shift Technical Advisor, nor the three other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a, fire emergency; and f.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions e.g.,

licensed Senior Operators, licensed Operators, health physi-

cists, chemistry technicians, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the unit is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shut-down for refueling, major maintenance,,or major unit modifications, on a temporary basis the following guidelines shall be followed:

l.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour

period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

3.

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work

periods, including shift turnover time.

he ea th hysscs Technician and fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected

absence, provided immediate action is taken to fill the required positions.

WASHINGTON NUCLEAR - UNIT 2 6-2 Amendment No.

63

ADMINISTRATIVE CONTROLS UNIT STAFF (continued) 4.

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Plant Manager or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assiqned.

Routine deviation from the above guidelines is not authorized.

g.

The Operations Manager, Assistant Operations Manager, Shift Hanagers and Control Room Supervisors shall hold a senior reactor operator license.

The Reactor Operators shall hold either a senior reactor operator license or a reactor operator license.

b/ASHINGTON NUCLEAR " UNIT 2 6-3 Amendment No. 63

THIS PAGE INTENTIONALLYBLANK WASHINGTON NUCLEAR - UNIT 2 6-4 Amendment No.

63

THIS PAGE INTENTIONALLYBLANK WASHINGTON NUCLEAR - UNIT 2 6"5 Amendment No. 63

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TABLE 6.2.2-1 MINIHUH SHIFT CREW COMPOSIT ON POSITION SH CRS RO EO STA NUMBER OF INDIVIDUALS RE UIRED TO FILL POSITION CONDITION 1 2

or 3 CONDITION 4 or 5 1

1 1

Nohe 2

~1 2

1 1

None TABLE NOTATION SM - Shift Manager with a Senior Operator license on WNP - Unit 2.

CRS - Individual with a Senior Operator license on WNP - Unit 2.

RO

- Individual with a Operator license on WNP - Unit 2.

EO

- Equipment Operator STA - Shift Technical Advisor Except for the Shift Hanager, the shift crew composition may be one less than the minimum requirements of Table 6,2.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table

6. 2,2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Manager from the control room while the unit is in OPERATIONAL CONDITION 1, 2 or 3, an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the control room command function.

During any absence of the Shift Manager from the control room while the unit is in OPERATIONAL CONDITION 4 or 5, an individual with a valid Senior Operator license or Operator license shall be designated to assume the control room command function.

WASHINGTON NUCLEAR - UNIT 2 6-6

ADMINISTRATIVE CONTROLS AUDITS (Continued) h.

The fire protection equipment and program implementation, at least once.per 12 months utilizing either a qualified offsite licensee fire protection engineer(s) or an outside independent fire protection consultant.

An outside independent fire protection consultant shall be utilized at least once every third year; and Any other area of unit operation considered appropriate by the CNSRB or the Managing Director.

j. 'he radiological environmental monitoring program and the results thereof at least once per 12 months.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once 'per 24 months.

The performance of activities required by the guality Assurance Program for effluent and environmental monitoring at least once per 12 months.

RECORDS 6.5.2.9 Records of CNSRB activities shall be prepared,

approved, and distri-buted as indicated below:

a.

Minutes of each CNSRB meeting shall be prepared,

approved, and forwarded to the Managing Director 14 days following each meeting.

b.

Reports of reviews encompassed by Specification 6.5.2.7 above, shall be prepared,

approved, and forwarded to the Managing Director within 14 days following completion of the review.

C.

Audit reports

'encompassed by Specification 6.5.2.8 shall be forwarded to the Managing Director and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6 6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

b.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and I

Each REPORTABLE EVENT shall be reviewed by the (POC), and'the results of this review shall be submitted to the CNSRB and the Assistant Managing Director for Operations.

WASHINGTON NUCLEAR - UNiT 2 6-13 Amendment No.

6

ADMINISTRATIVE CONTROLS

6. 7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

b.

C.

d.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Assistant Managing Director for Operations and the CNSRB shall be notified.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the POC.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components,

systems, or structures, and (3) corrective action taken to prevent recurrence.

The Safety Limit Violation Report shall be submitted to the Commission, the

CNSRB, and the Assistant Managing Director for Operations.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6. 8 PROCEDURES AND PROGRAMS 6.8. 1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b.

The applicable procedures required to implement the requirements of NUREG-0737.

C.

d.

e.

g.

h.

k.

Refueling operations.

Surveillance and test activities of safety-related equipment.

Security Plan implementation.

Emergency Plan implementation.

Fire Protection Program implementation.

PROCESS CONTROL PROGRAM implementation.

OFFSITE DOSE CALCULATION MANUAL implementation.

guality Assurance Program for effluent and environmental monitoring.

Health Physics/Chemistry Support Program.

6.8.2 Each procedure of Specification 6.8.la.

through j., and changes

thereto, shall be reviewed by the POC and shall be approved by the Plant Manager prior-to implementation and reviewed periodically as set forth in administrative procedures.

In addition, the review and approval of the implementing procedures supporting item k. in Specification 6.8.1 will be coordinated by the Hanager of Support

Services, who will provide review and approval control.

The WNP-2 Health Physics/Chemistry Support Program procedure will be reviewed by POC and approved by, the Plant Manager.

WASHINGTON NUCLEAR " UNIT 2 6-14 Amendment No. 63