ML20236H915

Amends 9 to Licenses NPF-37 & NPF-66,respectively,revising Tech Specs to Reflect New Organization & to Add Requirements That High Energy Line Break Sensors Be Operable

ML20236H915
Person / Time
Site:	Byron
Issue date:	07/23/1987
From:	Muller D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236H919	List: ML20236H915 ML20236H921
References
NPF-37-A-009, NPF-66-A-009 NUDOCS 8708050392
Download: ML20236H915 (25)

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COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-454 BYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. NPF-37 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated September 10, 1986, supplemented October 7, 1986; and March 5, 1987 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and 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 rules and regulations of the Commission; C.

There is reasonable assurance (1) 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 conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon j

defense and security or to the health and safety of the public; and l

E.

The issuance of this amendment is in accordance with 10 CFR Part i

51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as i~dicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:

I B70B050392 870723 PDR ADDCK 05000454 P

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-.l. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendaent No. 9 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

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

3.

This license amendment is effective as of the date cf its issuance.

FOR THE NUCLEAR REGULATORY COM S ION k

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Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date e7 Issuance: July 23, 1987 i

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,h NUCLEAR REGULATORY COMMISSION l;

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%.....J COMMONWEALTH EDISON COMPANY

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1 DOCKET NO. STN 50;4,55 BYkONSTA30N, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No. 9 License No. NPF-66 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The applications for amendment by Commonwealth Edison Company (thelicensee)datedSeptember 10, 1986, supplemented October 7, 1986; and March 5, 1987 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;

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i B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the

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Commission; 1

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C.

There is reasonable assurance (1) that the activities authorized by this ameadment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i

D.

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 E.

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.

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-66 is hereby amended to read as follows:

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, (2). Technical' Specifications The Technical Specifications contained in Appendix A (NUREG-1113),

as revised through Amendment No. 9 and revised'by Attachment 2-to NPF-60, and:the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby' incorporated into this license. contains a revision to Appendix A which is hereby incorporated into this. license. The licensee shall operate'.the facility in accordance with the Technical Specifications and the-Environmental Protection Plan.

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3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATOP,Y COMMI SION k

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W Daniel R. Muller, Director

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Project Directorate III-2 Division of-Reactor Projects - III, IV, Y and Special. Projects j

Attachment:

Changes to the Technical Specifications Date of Issuance: July 23, 1987 j

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9 ATTACHMENT TO LICENSE AMENDMENT NOS. 9 AND 9 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET N05. STN-50-454 AND STN 50-455 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-80 3/4 3-81 B 3/4 3-5*

B 3/4 3-5*

B 3/4 3-6 B 3/4 3-6 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-Sa*

6-Sa*

6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-10*

6-10*

6-11*

6-11*

6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-16 6-16 l

I

• Overleaf pages added for convenience

INSTRUMENTATION HIGH ENERGY LINE BREAK ISOLATION SENSORS LIMITING CONDITION FOR OPERATION 3.3.3.11 The high energy line break instrumentation shown in Table 3.3-14

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shall be OPERABLE.

APPLICABILITY:

As shown in Table 3.3.-14.

ACTION:

With the number of OPERABLE auxiliary steam isolation instruments less a.

than the Minimum Channels OPERABLE as required by Table 3.3-14, restore the inoperable ir.struments(s) to OPERABLE status within 7 days, or suspr.nd i

the supply of auxiliary steam to the Auxiliary Building, or establish a continuous watch in the affected area (s) until the inoperable sensors are restored to OPERABLE status, b.

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With the number of OPERABLE steam generator blowdown line isolation instru-ments less than the Minimum Channels OPERABLE as required by Table 3.3-14, restore the inoperable instrument (s) to OPERABLE status within 7 days, or limit the total steam generator blowdown flow rate to less than or equal to 60 gpm or establish a continuous watch in the affected area (s) until the inoperable sensors are restored to OPERABLE status.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.3.3.12 Each of the above high energy line break isolation instruments shall be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL TEST AND CHANNEL CALIBRATION at least once per 18 months.

I 1

BYRON - UNITS 1 & 2 3/4 3-80 AMENDMENT NO. 9

Table 3.3-14 HIGH ENERGY LINE BREAK INSTRUMENTATION Isolation Instrument Minimum Channels Applicable Function Channel Operable Modes 1.

Auxiliary Steam 0TS-A5031A 1

Isolation OTS-A5032A OTS-A5031B.

1 OTS-AS032B OTS-A5031C 1

OTS-A5032C OTS-AS0310 1

OTS-AS0320 OTS-A5031F 1

OTS-A5032F

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2.

Steam Generator TS-SD045A 1

1,2,3,4 Blowdown Line TS-SD045B Isolation TS-SD045A 1

1,2,3,4 TS-SD046B TS-SD045C 1

1,2,3,4 TS-SD0450 TS-SFW6C 1

1,2,3,4 TS-5UO46D J

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• Required when auxiliary steam is being supplied, from any source, to the Auxiliary Building.

BYRON - UNITS 1 & 2 3/4 3-81 AMENDMENT NO. 9

._:__=_===

INSTRUMENTATION BASES I

1 SEIS$1C INSTRUMENTATION (Continued)

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The response spectrum analyzer computes the response spectrum of the event for two sensor locations, compares it to the design response spectra of the

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plant, and indicates whether the event exceeded the operating basis earthquake criteria or the safe shutdown earthquake criteria.

1 This instrumentation is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earthquake," April 1974.

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3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Detign Criterion 19 of 10 CFR Part 50.

3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that

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i sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.' This capability is consistent i

with the recommendations of Regulatory Guide 1.97, Revision 3 " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," May 1983 and NUREG 0737, " Clarification of TMI Action Plan Requirements," November 1980.

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the detection instrumentation ensures that both adequate warning capability is available for the prompt detection of fires and that Fire Suppression Systems, that are actuated by fire detectors, will discharge extinguishing agents in a timely manner.

Prompt detection and suppression ~of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

The zone designations given in Table 3.3-11 are from electrical schematic diagrams.

SYRON - UNITS 1 & 2 B 3/4 3-5

- _=__ _ _ _ __ _ ____- _-___________-__-____- - -_-

i INSTRUMENTATION BASES Fire detectors that are used to actuate Fire Suppression Systems represent a more critically important component of a plant's fire protection program than detectors that are installed solely for early fire warning and notification.

Consequently, the minimum number of operable fire detectors must be greater.

The loss of detection capability for Fire Suppression Systems, actuated by fire detectors represents a significant degradation of fire protection for any area. As a result, the establishment of a fire watch patrol must be initiated at an earlier stage than would be warranted for the loss of detectors that provide only early fire warning.

The establishment of frequent fire patrols in the affected areas is required to provide Lection capability until the 1

inoperable instrumentation is restored to OPERABILITY.

3/4.3.3.8 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose part detection system ensures that sufficient

' capability is available to detect loose metallic parts in the Reactor Coolant System and avoid or mitigate damage to Reactor Coolant System components.

The dallowableout-of-servicetimesandSurveillanceRequirementsareconsistentwith the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

3/4.3.3.9 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive licaid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm /

Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.10 RADI0 ACTIVE Gt.CCGus EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

3/4.3.3.11 HIGH ENERGY LINE BREAK ISOLATION SENSORS The OPERABILITY of the high energy line break isolation sensors ensures that-the capability is available to promptly detect and initiate protective action in the event of a line break.

This capability is required to prevent the potential for damage to safety-related systems and structures in the auxiliary building.

BYRON - UNIT 1 B 3/4 3-6 AMENDMENT NO. 9

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager, Byron Station, shall be, responsible for overall l

unit operation and shall delegate in writing the succession to this respon-

-l sibility during his absence.

6.1.2 The Shift Engineer (or during his absence from the control room, a function.

A manogement directive to this effect, signed by the Assistant Vice l

J designated individual) shall be responsible for the control room command President and General Manager-Nuclear Stations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in Figure 6.2-1.

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UNIT STAFF 6.2.2 The unit organization shall be as shown in Figure 6.2-2 anct:

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; and 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 MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room; c.

A Radiation Chemistry Technician,* qualified in radiation protection procedures, shall be on site when fuel is in the reactor; d.

All CORE ALTERGIONS shall be observed and directly supervised by I

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 onsite at all times.

The Fire Brigade shall not include the Shift Engineer, and the two 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 j

• The Radiation Chemistry 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.

BYRON - UNITS 1 & 2 6-1 Amendment No. 9

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ADMINISTRATIVE CONTROLS J

UNIT STAFF (Continued)

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Administrative procedures shall be developed and implemented to

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limit the working hours of unit staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance personnel.

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The amount of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance.with the NRC Policy Statement on working hours (Generic Letter No. 82-12).

1 6.2.3 ONSITE NUCLEAR SAFETY GROUP (ONSG)

FUNCTION 6.2.3.1 The ONSG serves as an independent safety engineering group and shall i

function to examine plant operating characteristics, NRC issuances, industry I

advisories, REPORTABLE EVENTS and other sources of plant design and operating experience'information, including plants of similar design, which may indi.cate

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areas for improving plant safety. The ONSG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, opera-tions activities or other means of improving plant safety to the Manager of Nuclear Safety, and the Station Manager, Byron Station.

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COMPOSITION 6.2.3.2 The ONSG shall be composed of at least four, dedicated, full-time engineers located on site.

RESPONSIBILITIES 6.2.3.3 The 0NSG shall be responsible for maintaining surveillance of plant activities to provide independent verification

• that these activities are performed correctly and that human errors are reduced as much as practical.

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6.2.3.4 Records of activities performed by the ONSG shall be prepared, main-tained, and forwarded each calendar month to the Manager of Nuclear Safety, and the Station Manager, Byron Station.

l 6.2.4 SHIFT TECHNICAL ADVISOR The Station Control Room Engineer (SCRE) may serve as the Shift Technical Advisor (STA) during abnormal operating or accident conditions.

During these conditions the SCRE or other on duty STA shall provide technical support to the Shif t Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

• Not responsible for sign-off function.

l BYRON - UNITS 1 & 2 6-2 Amendment No. 9

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Amendment No. 9 57RON - UNITS 1 & 2.t'._.i.e.t

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L__J Amendment No. 9 E BYRON - UNITS 1 & 2 g

i CTABLE 6.2-la MINIMUM SHIFT CREW COMPOSITION

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POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SE 1

1 SF 1-None R0 2

1 A0 2

1 SCRE 1

None or, whenever a SCRE (SR0/STA) is not included in the shift crew composition, the minimum shift crew shall be as follows:

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION

)

l MODES 1, 2, 3 & 4 MODES 5 & 6 SE 1

1 SF 1

None RO 2

1 A0 2

1.

STA 1

None Shift Supervisor (Shift Engineer) with a Senior Operator SE license on Unit 1 Shift Foreman with a Senior Operator license on Unit 1 SF Individual with a Reactor Operator license on Unit 1 R0 Auxiliary Operator AO SCRE -

Station Control Room Engineer with a Senior Reactor Operator's License on Unit 1 Shift Technical Advisor STA The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-la 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 t

of Table 6.2-la.

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 Supervisor from the control room while the Unit is in MODE 1, 2, 3 or 4, an individual with a valid Senior Operator license shall be designated to assume the control room command function.

During any.

absence of the Shift Supervisor from the control room while the Unit is in MODE 5 or 6, an individual with a valid Operator license shall be designated to assume the control room command function.

1 Table 6.2-la will be replaced by Table 6.2-1 when Unit 2 receives an operating license.

BYRON - UNITS 1 & 2 6-Sa

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ADMINISTRATIVE CONTROLS I

6.2.4 SHIFT TECHNICAL ADVISOR (Continued)

To assure capability for performance of-all STA functions:

'f (1) The shift foreman (SRO) shall participate in the SCRE shift relief turnover.

i l During the shift, the shift engineer and the shift foreman (SRO) shall.be (2) l made aware of any significant changes in plant status in a timely manner I

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'by the SCRE.

(3) During the shift, the shift engineer and the shift foreman (SRO) shall'

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remain abreast of the current' plant status. The shift foreman (SRO) shall

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return to the control room two or three times per shift, where practicable, to' confer with the SCRE regarding plant status. Where not practicable to return to the control room, the shift foreman (SRO) shall periodically check with the SCRE for a plant status update.

The. shift foreman (SRO) shall not abandon duties original to reactor operation, unless specifically ordered by the shift engineer.

6.3 UNIT STAFF QUALIFICATIONS Each member of the unit staff shall meet or exceed the minimum qualifi-6.3.1 l

cations of ANSI N18.1-1971, except for the Rad / Chem Supervisor or Lead Health.

Physicist, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, for a Radiation Protection Manager. The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.

6.4 TRAINING A retraining and replacement training program for the unit staff.shall 6.4.1 be maintained under the direction of the Production Training Department and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /.

ANS 3.1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry' l

operational experience identified by the Department of Nuclear Safety.

6.5 REVIEW INVESTIGATION AND AUDIT

.j The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below.

BYRON - UNITS 1 & 2 6-6 Amendment No. 9

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s ADMINISTRATIVE CONTROLS 6.5 REVIEW INVESTIGATION AND AUDIT (Continued) 0FFSITE The Supervisor of the Offsite Review and Investigative Function shall be 6.5.1 appointed by the Manager of Nuclear Safety responsible for nuclear activities.

The audit function shall be the responsibility of the Manager of Quality i

Assurance and shall be independent of operations, Offsite Review and Investigative Function j

l a.

l The Superintendent of the Offsite Review and Investigative Function (1) provide directions for the review and investigative j

shall:

function and appoint a senior participant to provide appropriate direction, (2) select each participant for this function, (3) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) independently review and approve the findings and recommendations developed by personnel performing the review-and investigative function, (5) approve and report in a timely manner all findings of non-compliance with NRC requirements to the Station Manager, Assistant Vice President and General Manager -

l Nuclear Stations, Manager of Quality Assurance, and the Vice President -

Nuclear Operations.

During periods when the Supervisor of Offsite' Review and Investigative Function is unavailable, he shall designate this responsibility to an established alternate, who satisfies the formal training and experience for the Supervisor of the Offsite Review and Investigative Function. The responsibilities of the per-sonnel performing this function are stated below.

The Offsite Review and Investigative Function shall review:

1)

The safety evaluations for:

(1) changes to procedures, equip-ment, or systems as described in the safety analysis report, and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute 1

an unreviewed safety question.

Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of Quality Assurance; Proposed changes to procedures, equipment or systems which 2) involve an unreviewed safety question as defined in 10 CFR 50.59; 3)

Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; 4)

Proposed changes in Technical Specifications or this Operating License; BYRON - UNITS I & 2 6-7 Amendment No. 9

1 ADMINISTRATIVE CONTROLS OFFSITE (Continued)

Noncompliance with Codes, regulations, orders, Technical Speci-5) fications, license requirements, or of internal procedures, or instructions having nuclear safety significance; Significant operating abnormalities or deviation from normal 6) and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function; 7)

All REPORTABLE EVENTS; All recognized indications of an unanticipated deficiency 8) in some aspect of design or operation of safety-related structures, systems, or components; 9)

Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change; and Review and report findings and recommendations regarding 10) all items referred by the Technical Staff Supervisor, Station l

Manager, Assistant Vice President and General Manager -

Nuclear Stations, and Manager of Quality Assurance.

I b.

Audit Function The audit function shall be the responsibility; of the Manager of Such Quality Assurance independent of the Production Department.

responsibility is delegated to the Director of Quality Assurance (0perations) and the Director of Quality Assurance (Maintenance).

l Either shall approve the audit agenda and checklists, the findings and the report of each audit.

Audits shall be performed in accord-ance with the Company Quality Assurance Program and Procedures.

Audits shall be performed to assure that safety-related functions are covered within the period designated below:

The conformance of facility operation to provisions contained 1) within the Technical Specifications and applicable license conditions at least once per 12 months; 2)

The adherence to procedure, training, and qualification of the station staf f at least once per 12 months; The results of actions taken to correct deficiencies occurring 3) in facility equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 mo'nths; The performance of activities required by the Operational 4)

Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months; Amendment No. 9 6-8 BYRON - UNITS 1 & 2

ADMINISTRATIVE CONTROLS OFFSITE (Continued) 5)

The Facility Emergency Plan and implementing procedures at least once per 12 months; 6)-

The Facility. Security Plan and implementing procedures at least once per 12 months; 7)

Onsite and offsite reviews; 8)

The Facility Fire Protection programmatic controls including, the implementing procedures at least once per 24 months by qualified QA personnel; 9)

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

An outside independent fire pro-tection consultant shall be used at least every third year;

10) The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months;

11) The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months;

12) The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months; and

13) The performance of activities required by the Company Quality i

Assurance Program for effluent and environmental monitoring at least once per 12 months.

Report all findings of noncompliance with NRC requirements and recommendations and results of each audit to the Station Manager, Manager of Nuclear Safety, the Assistant Vice President and' General Manager - Nuclear Stations, Manager of Quality Assurance, 1

the Vice Chairman, and the Vice President - Nuclear Operations.

c.

Authority The Manager of Quality Assurance and the Manager of Nuclear Safety report to the Chairman and President.

Either the Manager of Quality Assurance or the Manager of Nuclear Safety has the authority to order I

unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.

i BYRON - UNITS 1 & 2 6-9 Amendment No. 9

(

ADMINISTRATIVE CONTROLS OFFSITE (Continued) d.

Records 1)

Reviews, audits, and recommendations shall be documented and distributed as covered in Specification 6.5.la. and 6.5.lb. ;

and 2)

Copies of documentation, reports, and correspondence shall be kept on file at the station.

t e.

Procedures Written administrative procedures shall be prepared and maintained for the offsite reviews and investigative functions described in Specification 6.5.la. and for the audit functions described in Specification 6.5.lb.

Those procedures shall cover the following:

1)

Content and method of submission of presentations to the Supervisor of the Offsite Review and Investigative Function, 2)

Use of committees and consultants, 3)

Review and approval, 4)

Derailed listing of items to be reviewed, 5)

Meth0d of:

(1) appointing personnel, (2) performing reviews, investigations, (3) reporting findings and recommendations of reviews and investigations, (4) approving reports, and (5) distribut*ng reports, and 6)

Determining satisfactory completion of action required based on approved findings and recommendations reported by personnel performing the review and investigative function.

f.

Personnel 1)

The persons, including consultants, performing the review and investigative function, in addition to the Supervisor of the Offsite Review and Investigative Function, shall have expertise in one or more of the following disciplines as appropriate for 1

the subject or subjects being reviewed and investigated:

a)

Huclear power plant technology, b)

Reactor operations, c)

Utility operations, d)

Power plant design, e)

Reactor engineering, f)

Radiological safety, i

g)

Reactor safety analysis, l

BYRON - UNITS 1 & 2 6-10 l

I

J ADMINISTRATIVE-CONTROLS OFFSITE (Continued) h)

Instrumentation and control,.

i)

Metallurgy, and j)

'Any other appropriate disciplines required by unique characteristics of the. facility.

2)

Individuals performing ~the Review and Investigative Function shall possess a minimum formal training and experience as

-listed below for each discipline.

a)

Nuclear Power Plant Technology Engineering graduate or equivalent with 5. years. experience in the nuclear power field design'and/or operation.

b)

Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear power plant operations.

c)

Utility Operations Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering.

d)

Power Plant Design Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or operation, e)

Reactor Engineering Engineering graduate or equivalent.

In addition, at least 5 years of experience in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.

f)

Radiological Safety Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.

g)

Reactor Safety Analysis Engineering graduate or equivalent with at least 5 years of experience in nuclear engineering.

i BYRON - UNITS 1 & 2 6-11

=

.~

ADMINISTRATIVE CONTROLS OFFSITE (Continued) h)

Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instrumentation and control design and/or operation.

I i)

Metallurgy Engineering graduate or equivalent with at least 5 years of experience in the metallurgical field.

The Supervisor of the Offsite Review and Investigative Function 3) shall have experience and training which satisfy ANSI N18.1-1971 requirements for plant managers.

ONSITE The Onsite Review and Investigative Function shall be supervised by 6.5.2 l

the Station Manager.

Onsite Review and Investigative Function a.

The Station Manager shall:

(1) provide directions for the Review and l

Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as the senior participant to provide appropriate directions; (2) approve participants for this function; (3) assure that at least two participants who collectively possess background and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the findings and recommendations developed by personnel performing the Review and Investigative Function; (5) report all findings of noncompliance with NRC requirements, and provide recommendations to l

the Assistant Vice President and General Manager - Nuclear Stations and the Supervisor of the Offsite Review and Investigative Function; and (6) submit to the Offsite Review and Investigative Function for concurrence in a timely manner, those items described in Speci-fication 6.5.la which have been approved by the Onsite Review and Investigative Function.

b.

Responsibility The responsibilities of the personnel performing this function are:

Review of:

(1) station specific portions of all procedures 1) required by Specification 6.8.1 and changes thereto, (2) all programs required by Specification 6.8.4 and changes thereto, and (3) any other proposed procedures or changes thereto as.

determined by the Station Manager to affect nuclear safety; l

2)

Review of all proposed tests and experiments that affect l

nuclear safety; i

BYRON - UNITS 1 & 2 6-12 Amendment No. 9 l

ADMINISTRATIVE CONTROLS t

DNSITE (Continued) 3)

Review of all proposed changes to the Technical Specifications; 4)

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety; 5)

Investigation of all v'iolations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Assistant Vice President and General Manager - Nuclear Stations l

j and to the Supervisor of the Offsite Review and Investigative Function; 6)

Review of all REPORTABLE EVENTS; 7)

Performance of special reviews and investigations and reports thereon as requested by the Supervisor of the Offsite Review and Investigative Function; 8)

Review of the Station Security Plan and implementing procedures and submittal of recommended changes to the Assistant Vice l

President and General Manager - Nuclear Stations; 9)

Review of the Emergency Plan and station implementing procedures and submittal of recommended changes to the Assistant Vice l

President and General Manager - Nuclear Stations;

10) Review of Unit operations to detect potential hazards to nuclear safety;

11) Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, l

recommendations and disposition of the corrective action to j

prevent recurrence and the forwarding of these reports to the Assistant Vice President and General Manager - Nuclear Stations l

and the Supervisor of the Offsite Review and Investigative Function; and i

12) Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment Systems.

c.

Authority The Technical Staff Supervisor is responsible to the Station l

Manager and shall make recommendations in a timely manner in all areas of review, investigation, and quality _ control phases of plant maintenance, operation, and administrative procedures rela, ting to facility operations and shall have the authority to request the action necessary to ensure compliance with rules, regulations, and The Station procedures when in his opinion such action is necessary.

Manager shall follow such recommendations or select a course l

BYRON - UNITS 1 & 2 6-13 Amendment No. 9

l

• l ADMINISTRATIVE CONTROLS ONSITE (Continued) q of action that is more conservative regarding safe operation of the facility.

All such disagreements shall be reported immediately to

{

the Assistant Vice President and General Manager - Nuclear Stations l

]

and the Supervisor of the Offsite Review and Investigative Function.

d.

Records

)

1)

Reports, reviews, investigations, and recommendations shall l

be documented with copies to the Assistant Vice President and General Manager - Nuclear Stations, the Supervisor of the Offsite 4

Review and Investigative Function, the Station Manager, and the l

Manager of Quality Assurance.

2)

Copies of all records and documentation shall be kept on file at the station.

e.

Procedures Written administrative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigative Function. These procedures shall include the following:

1)

Content and method of submission and presentation to the Station-Manager, Assistant Vice President and General Manager - Nuclear l

Stations, and the Supervisor of the Offsite Review and Investigative Function, 2)

Use of committees, 3)

Review and approval, 4)

Detailed listing of items to be reviewed, 5)

Procedures for administration of the quality control activities, and 6)

Assignment of responsibilities.

f.

Personnel 1)

The personnel performing the Onsite Review and Investigative Function, in addition to the Station Manager, shall consist of l

l

)

persons having expertise in:

a)

Nuclear power plant technology, b)

Reactor operations, c)

Reactor _ engineering, d)

Chemistry

]

e)

Radiological controls, f)

Instrumentation and control, and g)

Mechanical and electrical systems.

BYRON - UNITS 1 & 2 6-14 Amendment'No. 9 1

ADMINISTRATIVE CONTROLS ONSITE (Continued) 2)

Personnel performing the Onsite Review and Investigative Function shall meet minimum acceptable levels as described in ANSI N18.1-1971, Sections 4.2 and 4.4.

/

6.6 REPORTABLE EVENT ACTION 3

6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

The Commission shall be notified and a report submitted pursuant i

a.

to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by the Onsite Review and

~

l Investigative Function and the results of this review shall be submitted to the Offsite Review and Investigative Function and the Assistant Vice President and General Manager - Nuclear Stations.

l l

6.7 SAFETY LIMIT VIOLATION

{

6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

The NRC Operations Center shall be notified by telephone as soon as a.

possible and in all cases within I hour.

The Assistant Vice President l

and General Manager - Nuclear Stations and the Offsite Review and 1

J Investigative Function shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the Onsite Review and Investigative Function. This report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence; The Safety Limit Violation Report shall be submitted to the Commission, c-the Offsite Review and Investigative Function and the Assistant Vice l

President and General Manager - Nuclear Stations within 14 days of the violation; and d.

Critical operation of the Unit shall not be resumed until authorized k

by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below; The applicable procedures recommended in Appendix A, of Regulato'ry a.

Guide 1.33, Revision 2, February 1978, BYRON - UNITS 1 & 2 6-15 Amendment No. 9

= _ _ _. -

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) b.

The emergency operating procedures required to implement the require-ments of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Sec-tion 7.1 of Generic Letter No. 82-33; c.

Plant ' Security Plan implementation, d.

Radiological Emergency Response Plan implementation, e.

PROCESS CONTROL PROCRAM implementation, f.

OFFSITE DOSE CALCULATION MANUAL implementation, and g.

Quality Assurance Program implementation for effluent and environ-mental monitoring.

6.8.2 Each procedure of Specification 6.8.1 above, and changes thereto, shall be reviewed prior to implementation as set forth in Specification 6.5 above.

6.8.3 Temporary changes to procedures of Specification 6.8.1 above, may be made providedi a.

The intent of the original procedure is not altered; b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the Unit affected; and c.

The change is documented, reviewed by the Onsite Review and Investi-gative Function, and approved by the Station Manager within 14 days l

J of implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

a.

Reactor Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside i

containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include the recirculation portion of the Containment Spray

)

System, Safety Injection System, Chemical and Volume Control System, and RHR System.

The program shall include the following:

1)

Preventive maintenance and periodic visual inspection requirements, and 2)

Integrated leak test requirements for each system at refuel.ing cycle intervals or less.

BYRON - UNITS 1 & 2 6 Amendment No. 9

-