ML20097F611

Amends 132 & 114 to Licenses NPF-9 & NPF-17,respectively, Revising Administrative Controls Section of TSs to Reflect Reorganization of DPC & Changes to QA Rept

ML20097F611
Person / Time
Site:	McGuire, Mcguire
Issue date:	06/02/1992
From:	Matthews D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20097F614	List: ML20097F611
References
NUDOCS 9206150407
Download: ML20097F611 (22)

Text

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n UNITED STATES 5,

aE NUCLEAR REGULATORY COMMISSION I

WASHINoTON, D C. 20t46 o,

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QUKE POWER COMPANY DOCKET NO. 50-369 lkGUIRE NUCLEAR STATION. UNIT 1 tsMENDMENT TO FACILITY OPERATING llCENSE Amendment No. 132 License No. NPF-9 1.

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

A.

The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated January 8, 1992, as supplemented February 13, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 Commission's regulations set forth in 10 CFR Chapter 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.

9206150407 920602 ADOCK0500g9 DR

. 2.

Accordingly, the license is hereby amended by page 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-9 is hereby amended to read as follows:

Technical Specifications The Technical Specification.s contained in Appendix A, as revised through Amendment No. 132, 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 its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 9 ft]h)ttv$&

-Osvid B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of issuance:

June 2, 1992

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3" UNITED STATES n

i NUCLEAR REGULATORY COMMISSION 3

8 WASHINGTON, D C,20%6 o%

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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCtEAR STATION. UNIT 2 AMEN 0 MENT TO FACillTY OPERATING LI G GE Amendment No.

114 License No. NPF-17 1.

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

A.

The application for amendment to the McGuire Nuclear Station, Unit 1 i

(the facility), facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated January 8, 1992, as supplemented February 13, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in confo mity with the application, the provisions of the Act, and the rt,es 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 Commission's regulations set forth in 10 CFR Chapter 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.

4

-2 2.

Accordingly, the license is hereby amended by page 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-17 is hereby amended to read as follows:

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.114, 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 its date of issuance.

FOR THE NUCLEAR REGULA'ORY COMMISSION Un& f N)O' S i

id B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-l/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

June 2,1992 t

l

1 l

ATTACHMENT TO LICENSE AMENDMENT NO. 132 FAClllTY OPERATING LICENSE NO. NPF-9 DOCKET N0, 50-369 MD TO LICENSLMENDMENT NO. 114 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO, 50-370 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.

Egmove Paae.1 Insert Paaes 6-1 6-1 6-2 6-2 6-5 6-5 6-6 6-6 6-7 6-7 6-7a 6-7a 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 6-23 6-23 6-24 6-24 6-26 6-26

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station 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 Shif t Supervisor (or during his absence from the control room, a designated individual) shall be responsible for the control room command function.

A management directive to this effect, signed by the Vice-President McGuire Nuclear Site.shall be reissued to all McGuire Nuclear Site personnel l

on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 0FFSITE 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 relationship, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the FSAR.

b.

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

c.

The Vice President of McGuire Nuclear Site shall have 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, d.

The Senior Vice President Neclear Generation Department will be the Senior Nuclear Executive and have corporate responsibility for overall nuclear safety, e.

The individuals who train the operating staff and those who carry out radiation protection and quality assurance functions may report to the appropriate onsite manager; however, they a

shall have sufficient organizational freedom to ensure their independence from operating pressures.

McGUIRE - UNITS 1 and 2 6-1 Amendment No.132(Unit 1)

Amendment No,114(Unit 2)

_ _ _ ~

ADMINISTRATIVE CORTROLS UNIT STAFF 6.2.2 The unit organization shall be as shown in the FSAR, Chapter 13, and:

a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; b.

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

In addition, while either unit is.n MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room; c.

A Radiation Protection Technician shall be on site when fuel is in l

either reactor; 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 responsibil-ities during this operation; and e.

Administrative procedures shall be developed and implemented to limit the working hours of station staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, radiation protection te e,aicians, non-licensed operators, and key l

maintenance personnel.

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

.ne cojective shall be to have operating personnel work a normal 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> day with alternating 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> work week while the unit is operating.

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

1)

An inJividual 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 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 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; and 4)

Except during extMded shutdown pericds, the use of overtime should be considered on an individual p 'is and not for the entire staff on a shift.

Any deuiation from the above guidelines shall be authorized by the Station Manager or his deputy, or higher levels of management, in

-accordance with establi n d 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 Station Manager or his designee to as;ure that excessive hours have not been assignd.

Routine deviation from the above guidelines is not authorized.

1 Amendment No.132 ((Unit 1)

McGUIRE - UNITS 1 and 2 6-2 Amendment No.114 Unit 2)

I-2 TABLE 6.2-1 nO 5.

MINIMUM SHIFT CREW COMPOSITION 2

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION C

h BOTH UNITS IN BOTH UNITS IN ONE UNIT IN MODE 1, 2, 3 or 4 MODE 1, 2, 3, MODE 5 or 6 AND I

or 4 OR DEFUELED ONE UNIT IN MODE 5 or 6 or DEFUELED E

i j

SS 1

1 1

b 1

SRO 1

none s

a a

RO 3

2" 3

i cn i

a a

a j

J, A0 3

3 3

SM 1

none 1

l I

i a

i gg SS - Shift Supervisor with a Senior Operator license gg SR0 - Individual with a S for Operator license 1

1 gg RO - Individual with an

'erator license l

gg AO - Auxiliary operator SM - Shift Manager l

NN a/ At 1 cast one of the required individuals must be assigned to the designated position for

~w each unit.

^"

b/ At 7 east one licened Senior Operator or licensed Senior Operator Limited to Fuel Handling must i.

gg be present during CORE ALTERATIONS on either unit, who has no other concurrent responsibilities.

oo i

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t l

mv r

I 1.

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TABlf 6.2-1 (Continued)

Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 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 tha Shift Crew Composition to within the minimum requirements of Table 6.2-1.

1his 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 t

unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Manager *)

l with a valid Senior Operator license shall be designated to assume the control room command function.

During any absence of the Shift Supervisor i

from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the control room command function.

• On occasions when there is a need for both the Shift Supervisor and the SRO to be absent from the control room, the Shift-Manager shall be allowed to l

assume the control room command function and serve as the 3R0 in the control room provided that: (1) the Shift Supervisor is available to return to the control room within 10 minutes, (2) the assumption of SRO duties by the Shift Manager be limited to periods not in excess of 15 minutes duration and l

a total time not to exceed I hour during any 8-hour shift, and (3) the l

Shift Manager has an SRO license on the unit.

-McGUIRE 1&2 - UNITS 1 and 2 6-6 Amendment No. L32(Unit 1)

Amendment No.~14(Unit 2)

ADMINISTRATIVE CONTROLS 6.2.3 McGUIRE SAFETY REVIEW GROUP FUNCTION 6.2.3.1 The McGuire Safety Review Group (SRG) shall function to provide the l

review of plant design and operating experience for potential opportunities to improve plant safety; evaluation of plant operations and maintenance activities; and, to advise management on the overall quality and safety of plant operations.

The SRG shall make recommendations for revised procedures, equipment modifica-l

.)

tions, or other means of improving plant safety to appropriate station / corporate management.

COMPOSITION 6.2.3.2 The SRG shall be composed of at least five individuals and at least three of these shall have a bachelor's degree in engineering or related science and at least 2 years professional level experience in his/her field, at least 1 year of which experience shall be in the nuclear field.

The remaining individuals in the SRG shall have either (1) at least 5 years of nuclear experience and hold or have held a Senior Reactor Operator license; or (2) at least 8 years of professional level experience in his/her field, at least 5 years of which experience shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The SRG shall be responsible for:

l a.

Review of selected plant operating characteristics and other appro-priate sources of plant design and operating experience information for awareness and incorporation into the performance of other duties, b.

-Review of the effectiveness of corrective actions taken as a result of the evaluation of selected plant operating characteristics and other appropriate sources of plant design and operating experience information.

c.

Review of selected programs, procedures, x p m activities, includ-ing maintenance, modification, operational problems, and operational analysis.

d.

. Surveillance of selected plant operations and maintenance activities to provide independent verification

• that they are performed correctly and that human errors are reduced to as low as practicable, e.

Investigation of selected unusual events and othe c,currences as assigned by Station Management or the Manager of barety Assurance.

l

• Not responsible for sign-off function.

McGUIRE - UNITS 1 and 2 6-7 Amendment No.132(Unit 1)

Amendment No.ll4(Unit 2)

ADMINISTRATIVE CONTROLS McGUIRf A ETY REVIEW GROUP (Continued)

F S.2.3 AUThoi<"

6.2.3.4 fhe SRG shall report to and advise the Manager of Safety Assurance, l

on those areas of respohsibility specified in Section 6.2.3.

RECOP/y

'L. 3 activities performed by the SRG shall be prepar. and l

aiat!

life of the station.

Summary reports of activities C4 shall be forwarded eacn calendar month to the Manager l

3 orts.

Satcty

.s-

e.

b.2.4 E'

iAGER l

6.2.4.1

[he U

Manager, whose functk ns include those of a Shift Technical Advisor, sMll c rve in an advisory capacity to the Shif t Superviso.

6.3,f'1 STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tion; of ANSI N18.1-1971 for comparable positions and the supplemental require-meats specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licemees, except for the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replacement training p reram for the unit staff shall be maintained under the direction of the Training Manager and shall meet or l

exceed the requircments J recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified s'

in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to a'.1 licensees. and ; hail include familiarization with relevant industry operational experience identified by the SRG.

I McGUIRE - UNITS 1 and 2 6-7a Amendment No. l7 Unit 1)

Amendment No. 1 W init 2) l

ADMINISTRATIVE CONTROLS

6. 5 REVIEW AND AUDIT 6.5.1 -TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.1.1 Each procedure and program required by Specification 6.8 and other procedures wnich affect nuclear safety, and changes thereto, shall be prepared by a qualified individual / organization.

Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual /

group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual / group which prepared the procedure, or changes thereto.

6.5.1.2 Proposed changes to the Appendix A Technical Specifications shall be prepared by a qualified individual / organization.

The preparation of each proposed Technical Specifications change shall be reviewed oy an individual /

group other than the individual / group which prepared the proposed change, but who may be from the same organization as the individual / group which prepared the proposed change.

Proposed changes to the Technical Specifications shall be approved by the Station Manager.

- 6. 5.1. 3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual /orga n ation.

Each such modification shall be reviewed by an individual / group other tnan the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modification.

Proposed modificatiors to nuclear safety related structures, systems, and components shall be approved prior to implementation by the Station Manager; or for the Station Manager by the Mechanical Superintendent, the Operations Superintendent, and I and E Superintendent, or the Work Control Super-intendent, as previously designated by the Station Manager.

6.5.1.4 Individuals responsible for reviews performed in accordance with Specifications 6.5.1.1, 6.5.1.2, and 6.5.1.3 shall be members of the site I

supcrvisory staff, previously designated by the Site Vice President to perfona l

such reviews.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.

If deemed necessary.

such review shall be performed by the appropriate designated site review l

personnel.

6. 5.1. 5 Proposed tests and experiments which affect sWtion nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager; or for the Station Manager by the Mechanical Superintendent, the Operations %perintendant, the I and E Superintendent, or the Work Control Superintendeat, as previcusly designated by the Station Manager.

l-l l

McGUIRE - UNITS 1 and 2 6-8 Amendment No.132(Unit 1) i Amendment No.114(Unit 2)

1 ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) 6.5.1.6 ALL REPORTABLE EVENTS and all violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations te prevent recurrence.

Such reports shall be approved by the Manager, Safety Assurance and transmitted to the Site Vice l

President, and to the Director of the Nuclear Safety Review Board.

6. 5.1. 7 The Manager, Safety Assurance shall assure the perfarmance of special-reviews l

and investigations, and the preparation and submittal of reports thereon, as requested by the Site Vice President.

l 6.5.1.8 Deleted

6. 5.1. 9 Deleted 6.5.1.10 The Manager, Safety Assurance shall assure the performance of a review by a l qualified individual / organization of every umlanned onsite release of radio-active material to the environs including the preparation and forwarding of reports covering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence to the Site Vice President, and to the Nuclear l

.i Safety Review Board.

6.5.1.11 The Manager, Safety Assurance shall assure the performance of a review by al qualified individual / organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems.

6.5.1.12 The Manager, Safety Assurance shall ensure the performance of a review by a l qualified individual / organization of the Fire Protection Program and implement-ing pro:.edures and submittal of recommended channes to the Nuclear Safety Review Board and Manager, Human Resources.

l

-6.5.1.13 Reports documenting each of the activities performed under Specifi-cations 6.5.1.1 through 6.5.1.12 hall be maintained.

Copies shall be provided to the Site Vice President, and the Nuclear Safety Review Board.

l 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)

FUNCTION 6.5.2.1 The NSRB shall function to provide independent review and audit of

-designated activities in the areas of:

a.

Nuclear power plant operations, b.

Nuclear engineering, c.

Chemistry and radiochemistry, McGUIRE - UNITS 1 and 2 6-9 AmtJmentNo.g(Unit 1)

Amendment No.

(Unit 2)

ADMINISTRATIVE CONTROLS FUNCTION (Continued) d.

Metallurgy, e.

Instrumentation and control, f.

Radiological safety, g.

Mechanical and electrical engineering, and h.

Administrative control and quality assurance practices.

ORGANIZATION 5.5.2.2 The Director, members and alternate members of the NSRB shall be appointed in writing by the Executive Vice President, Power Generation and l

shall have an academic degree in an engineering or physical science field; and in addition, shall have a minimum of 5 years technical experience, of which a minimum of 3 years shall be in one or more areas given in Specification 6.5.2.1.

In special cases, candidates for appointment without an academic degree in engineering or physical science may be qualified with a minimum of ten years experience in one of the areas in Specification 6.5.2.1.

No more than two alternates shall participate as voting members in NSRB activities at any one time.

6.5.2.3 The NSRB shall be composed of at least five members, including the Director. Members of the NSRB may be from the Nuclear Generation Department, l

from other departments within the Company, or from external to the Company.

A maximum of one membec of the NSRB may be from the McGuire Nuclear Site l

staff.

6.5.2.4 Consultants shall be' utilized as determined by-the NSRB Director to provide expert advice to the NSRB.

6.5.2.5 Staff assistance may be provided to the NSRB in order to promote the proper, timely, and ex;:editious performance of its functions.

6.5.2.6 The NSRd shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.

6.5.2.7 The quorum of the NSRB necessary for the performance of the NSR8 review and audit functions of these Technical Specifications shall consist of the Director, or his designated alternate, and at least four other NSRB members including alternates.

No more than a minority of the quorum shall have line responsibility for operation of McGuire Nuclear Station.

McGuire - UNITS 1 and 2 6-10 Amendment No.132(Unit 1)

Amendment No.114(Unit 2)

ADMINISTRATIVE CONTROLS REVIEW 6.5.2.8 The NSRB shall review:

a.

The safety evaluations for:

(1) changes to procedures, equipment, or systems, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR to verify that such actions did not constitute an unreviewed safety question; b.

Proposed changes to procedures, equipment or syste.s which involve an unreviewed safety question as defined in Section 50.59, 10 CFR; c.

Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR; d.

Proposed changes in Technical Specifications or this Operating License; e.

Violations of Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; f.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; g.

All REPORTABLE EVENTS; h.

All recognized indicatinns of an unanticipated deficiency in some aspect of design or operation of structures, systems or components that could affect nuclear safety; i.

Quality Verification Department audits relating to station operations l

and actions taken in response to these audits; and j.

Reports of activities performed-under the provisions of Specifi-cations 6.5.1.1 through 6.5.1.12.

I AUDITS 6.5.2.9 Audits of site activities shall be performed under the cognizance of I

the NSRB.

These audits shall encompass:

a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions; l

b.

The performance, training, and qualifications of the entir station staff; McGuire - UNITS 1 and 2 6-11 Amendment No.132(Unit 1)

Amendment No.ll4(Unit 2)

l ADMINISTRATIVE CONTROLS AUDITS (Continued)

The results of actions taken to correct deficiencies occurring in c.

unit equipment, structures, systems, or method of operation that Jfect nuclear safety; I

d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B,10 CFR i

Part 50; I

e.

The Emergency Plan and implementing procedures; j

f.

The Security Plan and implementing procedures; g

g.

The Facility Fire Protection programmatic controls including the implementing procedures; l

h.

The fire protection equipment and program implementation utilizing l

either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.

An outside inde-pendent fire protection consultant shall be used at least every third year; i.

The Radiological Environmental Monitoring Program and the results thereof; I

j.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures; I

k.

The PROCESS CONTROL PROGRAM and implementing procedures for SOLIDIFICATION of radicactive wastes; I

1.

The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring; and l

m.

Any other area of site operation considered appropriate by the NSRB or the Executive Vice President, Power Generation.

AUTHORITY 6.5.2.10 The NSRB shall report to and advise the Executive Vice President, Power Generation on those areas of responsibility specified in Specific-ations 6.5.2.8 and 6.5.2.9.

McGuire - UNITS 1 and 2 6-12 Amendment No.13ZUnit 1)

Amendment No.11(Unit 2)

l 4

ADMINISTRATIVE CONTROLS RECORDS 6.5.2.11 Records of NSRB activities shall be prepared, approved, and distributed as indicated below:

Minutes of each NSRB meeting shall be prepared, approved, and forwarded a.

to the Senior Vice President, Nuclear Generation and to the Executive Vice President, Power Generation, within 14 days following each meeting; b.

Reports of reviews encompassed by Specification 6.5.2.8 above, shall be prepared, approved and forwarded to the Senior Vice President, Nuclear Generation, and to the Executive Vice President, Power Generation within 14 days following completion of the review; and Audit reports encompassed by Specification 6.5.2.9 above, shall be c.

forwarded to the Senior Vice President, Nuclear Generation and to the Executive Vice President, Power Generation, and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall tie taken for REPORTABLE EVENTS:

The Commission shall be notified and a report submitted pursuant to a.

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

Each REPORTABLE EVENT shall be reviewed by the Station Manager; or for the Station Manager by:

(1) the Operations Superintendent, (2) the I and E Superintendent, (3) the Mechanical Superintendent, or (4) the Work Control Superintendent, as previously designated by the Station Manager, and the results of the review shall be submitted to the NSRB and the Site Vice President.

6. 7 SAFETY LIMIT VIOLATION l

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

a.

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 Site Vice President, l

&nd the NSRB 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 Operations Superintendent and the Station l

Manager.

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 l

to prevent recurrence; McGuire - UNITS 1 and 2 6-13 Amendment No.132(Unit 1)

Amer.dment No. ll4(Unit 2)

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c.

The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Site Vice President, within 14 days of l

the violation; and d.

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.

Deleted d.

Deleted l

e.

PROCESS CONTROL PROGRAM implementation; f.

OFFSITE DOSE CALCULATION MANUAL implementation; and g.

Quality Assurance Program for effluent and environmental monitoring.

h.

Fire Protection Program implementation, i.

Commitments contained in FSAR Chapter 16.0 6.8.2 Each procedure of Specification 6.8.1 above, and changes thereto, shall be reviewed and approved by a group manager, superintendent / manager, or one of their designated direct reports prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

For procedures I

which implement offsite environmental, technical, and laboratory activities, the above review and approval may be performed by the General Manager, l

Environmental Services or designee.

6.8.3 Temporary changes to procedures of Specification 6.8.1 above may be made provided:

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 McGuire-- UNITS 1 and 2 6-14 Amendment No.132(Unit 1)

Amendment No.114(Unit 2)

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) c.

The change is approved by a group manager, superintendent / manager, or one of their designated direct reports within 14 days 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 containment that could contain highly radioactive fluids durin,q a serious transient or accident to as low as practical levels.

the systems include RHR, Boron Recycle, Refueling Water, Liquid Waste, Waste Gas, Safety Injection, Chemical and Volume Control, Contain-ment Spray, and Nuclear Sampling.

The program shall include the following:

1)

Preventive maintenance and periodic visual inspection requirements, and 2)

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

b.

In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

1)

Training of personnel, 2)

Procedures for monitoring, and 3)

Provisions for maintenance of sampling and analysis equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.

This program shall include:

1)

Identification of a sampling schedule for the critical variables and control points for these variables, 2)

Identification of the procedures used to measure the values of the critical variables, 3)

Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, l

l McGuire - UNITS 1 and 2 6-15 Amendment No.132 (Unit 1)

Amendment No.ll4 (Unit 2)

ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) g.

Records of training and qualification for current members of the unit staff; h.

Records of inservice inspections performed pursuant to these Technical Specifications; i.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; j.

Records of meetings of the NSRB and reports required by Specification 6.5.1.12; k.

Records of the service lives of all snubbers including the date at which the service life commences and associated installation and maintenance records; 1.

Records of secondary water sampling and water quality; and i

m.

Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date.

This should include procedures effec-tive at specified times and QA records showing that these procedures were followed, n.

Records of reviews performed for changes made to the ODCM and the PCP.

6.10.3 Records of quality assurance activities required by the QA Manual shall be retained for a period of time required by ANSI N45.2.9-1974.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mrem /hr at 45 CM (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Individuals qualified in radiation protection procedures (e.g.. or ation Protection Technician) or personnel continu-l ously escorted by such individonis may be exempt from the RWP issuance require-ment during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mrem /hr provided they are other-wise following plant radiation protection procedures for entry into high radiation areas.

McGUIRE - UNITS 1 and 2 6-23 Amendtr. ant No.132 (Unit 1)

l I

i ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area; or b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them; or c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the RWP.

l 6.12.2 In addition to the requirements of Specification 6.12.1, areas acces-sible to personnel with radiation levels greater than 1000 mrem /hr at 45 CM (18 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision.

Doors shall remain locked except during periods of access by personnel under c, approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

For individual areas accessible to personnel with radiation levels greater than 1000 mrem /hr* that are located witN m acge areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, that area shall be bar-ricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee-initiated changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n.

This documentation shall contain:

AMeasurement made at 18 inches from source of radioactivity.

McGUIRE - UNITS 1 and 2 6-24 Amendment No.132 (Unit 1)

Amendment No.114 (Unit 2) l

ADMINISTRATIVE-CONTROLS 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASE0US, AND SOLID WASTE TREATMENT SYSTEMS

• 6.15.1 Licensee initiated major changes to the Radioactive Waste Systems (liquid, gaseous and solid) a.

Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was.

reviewed by the Station Manager.

The discussion of each change shall cet.ain:

1)

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59; 2)

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; 3)

A detailed description of the equipment, components, and processess involved and the interfaces with other plant-c systems; 4)

An cvaluation Of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments thereto; 5)

An evaluation of the change, which shows expected maximum exposures to individual in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in tne License application and amendments thereto; 6)

A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; 7)

An estimate of the exposure to plant operating personnel as a result of the change; and 8)

Documentation of the. fact that the change was reviewed and found acceptable by the Station Man 1ger or the Chemistry Manager.

b.

Shall become effective upon review and acceptance by a qualified individual / organization.

^ Licensee 3 may choose to submit the information called for in this specification as part of the annual FSAR update.

McGUIRE - UNITS 1 and 2 6-26 Amendment No.132(Unit 1)

Amendment No.114(Unit 2) 1

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