ML20237F973

Amends 145 & 80 to Licenses DPR-57 & NPF-5,respectively, Modifying Tech Specs to Reflect Organization Changes

ML20237F973
Person / Time
Site:	Hatch
Issue date:	08/10/1987
From:	Youngblood B Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237F976	List: ML20237F973 ML20237F992
References
TAC-60982, TAC-60983, TAC-61637, TAC-61638, NUDOCS 8708130258
Download: ML20237F973 (48)

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>S E8CO UNITED STATES /

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NUCLEAR. REGULATORY COMMISSION l

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'j WASHINGTON, D. C. 20555

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GEORGIA POWER COMPANY OGLETFORFE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.145 License No. DPR p*

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1.

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

l' The applications' for amendment to the Edwin I. Hatch Nuclear Plant, l

A.

Unit 1 (the facility) Facility Operating License No. DPR-57 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municisal Electric Authority of Georgia, and City of' Dalton, Georgia, (tie licensee) dated February 17. May 16, August 27, October 27. and November 24. 1986, comply with the standards and i

requirements of the Atomic Energy Act of 1954, as amended (the Act)..

j and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility v:111 operate in conformity.with the application, the -

provisions of the Act, and the rules and regulations of the Comission;

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C.

There is reasonable assurance (1) that the activities authorized by 1

this amendment can be conducted without endangering the health and-i safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR l

Chapter I; l

l D.

The issuance of this amendment will not be inimical to the comon 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 Sli of the Commission's regulations and e.ll applicable requirements have been. satisfied.

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ADO OO 1

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- i 2.

Accordingly, the license is amended by changes to the Technical Specifi-i cations as indicated in the attachment to this license ~ amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is.hereby amended to read as follows:

(2)

Technical Specifications i

i The Technical Specifications contained in Appendices A and B, as revised through Amendment No.145, are hereby incorporated in the license. The licensee shall operate the facility in accordance with j

the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

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F0 THE NUCLEAR REGULATORY COMMISSION o-M B. J. Youngblood, Director U

Project Directorate II-3 Division of Reactor Projects-1/II

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Attachment:

l Changes to the Technical Specifications Date of Issuance: August 10, 1987 l

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ATTACHMENT TO LICENSE AMENDMENT NO.145 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 ReplacethefollowingpagesoftheAppendixATechnicalSpecificahionswith l

the enclosed pages. - The revised pages are identified by amendment number and J

contain vertical lines indicating the areas of change.

Remove Insert Page Page 6-1 6-1 6-la 6-la

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6-6 6-6 6-7 6-7 j

6-8 6-8 i

6-9 6-9 6-10 6-10 i

6-11 6-11 J

6-12 6-12 6-13 6-13 6-13a 6-13a Replace the following pages of the Appendix B Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and con-l tain vertical lines indicating the areas of change.

Remove Insert Page Page i

i 5-1 5-1

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l 5-2 5-2 5-3 5-3 5-4 5-4 l

5-5 5-5 5-7 5-7 5-6 5-6 5-9 5-9 l

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E 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.0. The Vice President-Plant Hatch shall provide direct executive oversight over all aspects of Plant Hatch.

6.1.1. The Plant Manager shall be responsible' for overall unit hperation, except for the Radiological Environmental. Monitoring Program as'-described below and for delegation in writing of the succession of this responsibility.

during his absence. Certain plant support functions shall be the responsibility of the Plant Support Manager.

6.1.2 The Manager Radiological; Safety shall be responsible for the Radiological Environmental Monitoring Program as described-in the-i Specification 3/4.16 of Unit I and for the writing of'the Annual Radiological 1

l Environmental Surveillance Report. The Manager Radiological Safety shall review the proposed changes to plant systems or equipment, provided that such.

changes are identified by the Plant Review Board (PRB) as having a potential radiological environmental impact.

6.1.3 Each of the above-mentioned individuals is responsible for the accuracy of the procedures needed to implement his responsibilities.

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6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support.

shall be as shown in Chapter 13 of the Plant Hatch Unit 2 updated Final Safety Analysis Report.

UNIT STAFF 6.2.2 The unit organization shall be as shown in Chapter 13 of the Plant Hatch Unit 2 updated Final Safety Analysis Report.

l a.

Each on duty shift shall be composed of at least the minimum shift L

crew composition shown in Table 6.2.2-1.

b.

At least one licensed Operators shall be in the control room for each reactor containing fuel.

c.

At least two licensed Operators shall be present in the control room for each reactor in the process of start-up, scheduled reactor shutdown and during recovery from reactor trips.

d.

An individual qualified to implement' radiation protection procedures shall be on site when fuel is f r. either reactor.

e.

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

HATCH - UNIT 1 6-1 Amendment No. 145.

6.0 ADMINISTRATIVE CONTROLS f.

A Fire' Team of at least five members shall be maintained onsite at all times. The Fire Team shall not include the minimu4 shift crew necessary for safe shutdown on Units 1 and 2 or any personnel required for other essential functions during a fire emergency.

g.

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

i auxiliary operators, health physicists, and key maintenance personnel, l

Adequate shift coverage shall be maintained without routine heavy

'i use of overtime.

The objective shall.be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems: require j

substantial amounts of overtime to be used or during extended i

periods of shutdown for refueling, major maintenance, or major plant modifications, the following guidelines shall be followed on-j a temporary basis:

(1) 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 seven day j

period, all excludine shift turnover time.

q (3) A break of at least eight hours should'be allowed between work' l

periods, including shift turnover time.

i (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 higher levels of management, in accordance with l

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 assigned. Routine deviation from the above guidelines is not authorized.

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l HATCH - UNIT 1 6-la Amendment No. 145 8

, uwwmum ma mmrmu 6.3 UNIT STAFF QUALIFICATIONS

6. 3.1.

Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor s degree or equivalerit in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients..and accidents.

6.4 TRAINING 6.4.1.

A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager-of Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2.

A training program for fire protection shall be maintained under the direction of-the Senior Regulatory Specialist and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except for fire protection training sessions which shall be held at least once per 92 days.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB) l I

FUNCTION i

6. 5.1.1.

The PRB shall function to advise the Plant Manager on all matters relcted to nuclear safety.

COMPOSITION I

6. 5.1. 2.

The PRB shall be composed of, as a minimum, a supervisor or higher level individual from each of the departments listed below:

Operations Maintenance Quality Control (QC)

Health Physics Nuclear Safety and Compliance Engineering Support i

The Chairman, his alternate, and other members of the PRB shall be l

designated by the Plant Manager.

The Chairman and his designated alternate shall both be managers of one of the six above listed departments or a higher level or. site manager.

ALTERNATES 6.5.1.3.

All alternate members shell be appointed in writing by the PRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PRB activities at any one time.

HATCH - UNIT 1 6-6 Amendment No. 145

ADMINISTRATIVE CONTROLS MEETING FREQUENCY

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6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate.

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QUORUM l

6.5.1.5 The minimum quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three voting members including alternates.

RESPONSIBILITIES 6.5.1.6 The Plant Review Board shall be responsible for:

a.

Review of all procedures required by Specification 6.8 and changes thereto, except those for the Radiological Environmental Monitoring Program, any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear safety.

1 c.

Review of all proposed changes to Appendix "A" Technical Specifications.

d.

Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

i e.

Investigation of all reportable violations of the Technical l

Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President-Plant Hatch, the Senior Vice President-Nuclear Operations, and to the Safety Review Board (SRB).

f.

Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commisrion.

l g.

Review of unit operations to detect potential nuclear safety hazards.

h.

Performance of special reviews, investigations or analyses and i

reports thereon as requested by the Plant Manager or the SRB.

l HATCH - UNIT 1 6-7 Amendment No. 145 l

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i ADMINISTRATIVE CONTROLS RESP 0NSIBILITIES (Continued) 1.

Review of the Security Plan and implementing procedures and shall

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submit recommended changes to the SRB.

j. Review of the Emergency Plan and implementing procedures and shall j

submit recommended changes to the SRB.

k.

Review of any unplanned onsite release of radioactive material to the environs when such release is in excess of I C1, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 Ci of noble gases or 0.02 Ci of radiciodines for gaseous effloents. Also included is the preparing and forwarding to the Plant Manager and the SRB reports covering evaluation, recommendations l

and disposition of the corrective action to prevent recurrence.

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J' 1.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL (ODCM), except for the section on the Radiological Environmental Monitoring Program in the ODCM.

m.

Review of proposed change (s) to plant systems and equipment to determine whether the proposed change has a potential radiological i

environmental impact.

Such change (s) will be reported to the l

l Manager-Radiological Safety.

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AUTHORITY 6.5.1.7 The PRB shall:

a.

Recommend in writing to the Plant Manager approval or disapproval of items considered under 6.5.1.6(a) through (d) above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President-Plant Hatch, the Senior Vice President-Nuclear Operations, and the Safety Review Board of disagreement between the PRB and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The Plant Review Board shall maintain written minutes of each PRB' meeting that, at a minimum, document the results of all PRB activities performed under the responsibility and authority provisions of these Technical Specifications. Copics shall be provided to the Vice President-Plant Hatch, the Senior Vice President-Nuclear Operations, and the Safety Review Board.

HATCH - UNIT 1 6-8 Amendment No. 145-

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ADMINISTRATIVE CONTROLS 6.5.2.

SAFETY REVIEW BOARD (SRB) 1 FUNCTION j

6.5.2.1.

The SRB shall function to provide independent review and audit of designated activities in the areas.of:

a.

Nuclear power plant operations.

b.

Nuclear engineering, i

c.

Chemistry and radiochemistry, d.

Metallurgy.

j e.

Instrumentation and control.

1 f.

Radiological safety.

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l g.

Mechanical and electrical engineering, j

l h.

Quality assurance practices.

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l COMPOSITION 6.5.2.2.

The SRB shall be composed of a minimum of five persons who as a I

i group provide the expertise to review and audit the operation of a l

nuclear power plant.

The Chairman and other members shall be appointed by the Senior Vice President '- Nuclear Operations or such other person as j

he shall designate.

The composition of the SRB shall' meet the i

requirements of ANSI N18.7-1976.

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ALTERNATES 6.5.2.3.

All alternate members shall be appointed in writing by the SRB Chairman to serve on a temporary basis; however, no more than a minority of alternates shall participate as voting members in SRB activities at any one time.

However, in extenuating circumstances, the Senior Vice President Nuclear Operations may designate the use of additional i

alternates with voting authority when regular members are not available within necessary time constraints.

CONSULTANTS 6.5.2.4.

Consultants shall be utilized as determined by the SRB Chairman to provide expert advice to the SRB.

MEETING FREQUENCY 6.5.2.5.

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

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ADMINISTRATIVE CONTROLS i

QUORUM 6.5.2.6.

The minimum quorum of the SRB necessary for the perforknance of the SRB review and audit functions of these Technical Specif4 cations I

shall cor.sist of the Chairman or his designated alternate and at least a majority of the members.

No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEW l

6.5.2.7.

The SRB shall be responsible for the review of:

l a.

The safety evaluations for (1) changes to procedures, equipment, l

or systems and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions I

did not constitute an unreviewed safety question.

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b.

Proposed changes to procedures, equipment or systems which I

involve an unreviewed safety question as defined in Section l

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 to 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.

Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Conrnission.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation.of structures, systems, or l

components that could affect nuclear safety,

i. Reports and meeting minutes of the Plant Review Board.

HATCHa-UNIT 1 6-10 Amendment No. 145

1 ADMINISTRATE"E CONTROLS j

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AUDITS j

6.5.2.8.

Audits of unit activities shall be performed u0 der the j

cognizance of the SRB.

Each inspection or audit shall be performed within the specified time interval with:

1.

A maximum allowable extension not to exceed 25%

of the inspection or audit interval.

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2.

A total maximum combined interval time for any 3 consecutive

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inspection or audit intervals not to exceed 3.25 times the j

specified inspection or audit interval.

These audits shall encompass:

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a.

Tne conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions L'

at least once per 12 months.

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b.

The performance, training and qualifications of the entire unit staff at least once per 12 months.

c.

The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d.

The performance of activities required by the Operational l

Quality Assurance Program to meet the criteria of Appendix "B",

10 CFR 50, at least once 24 months.

The Emergency Plan and implementing procedures at least once per e.

12 months shall be performed by individuals who have no direct l

responsibility for implementation of this plan.

I f.

The Security Plan and implementing procedures at least once per 12 months shall be performed by individuals who have no direct responsibility for implementation of this plan.

g.

Any other area of unit operation considered appropriate by the SRB or the Senior Vice President - Nuclear Operations.

l h.

The Fire Protection Program and implementing procedures et least once per 24 months.

i. An independent fire protection and. loss prevention inspection and audit shall be performed annually utilizing either qualified offsite license personnel or an outside fire protection firm.

j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

During the year in which the inspection or audit

occurs, the requirements of 6.5.2.8.1. can be affected concurrently.

J HATCH - UNIT 1 6-11 Amendment No. 145 l

ADMINISTRATIVE CONTROLS

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k.

The Radiological Environmental Monitoring Program and the results thereof annually.

1.

The Offsite Dose Calculation Manual, Process Control Program, and implementing procedures at least once per 24 months.

i AUTHORITY j

l 6.5.2.9 The SRB shall report to and advise the Senior Vice President -

Nuclear Operations on those areas of. responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of SRB activities shall be prepared, approved and l

distributed as indicated below:

a.

Minutes of each SRB meeting shall be prepared, approved and forwarded to the Senior Vice President-Nuclear Operations l.

within 14 days following each meeting.

j, b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President-Nuclear Operations within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Executive Vice President, the Senior Vice President-Nuclear Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 rep 0RTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted

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pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE requiring notification.' to the Commission shall be reviewed by the PRB and submitted to the SRB, the Vice President-P; ant Hatch, and the Senior Vice President-Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated-1 a.

The unit shall be placed in at least HOT SHUTDOWN within two 1

hours.

I b.

,he Safety Limit violation shall be reported to the Commission, the Vice President-Plant Hatch, the Senior Vice President-Nuclear Operations, and the SRB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

HATCH - UNIT 1 6-12 Amendment No. 145

F.

i ADMlNTSTRATIVE CONTROLS' i

SAFETY LIMIT VIOLATION (Continued) c.

A Safety Limit Violation Report shall be prepared.

The! report shall be reviewed by the PRB. This report shall describe (1) applicable circumstances preceding the violation, (2)' effe, cts of the violation upon facility components, systems or structures, and (3) corrective action taken.to prevent recurrence.

i d.

The Safety Limit Violation Report shall be submitted to the Commission, the SRB, the Vice President-Plant Hatch, and the Senior Vice President-Nuclear Operations within 14 days of the violation.

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-l 6.8 PROCEDURES I

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 i

Guide 1.33, Revision 2, February 1978.

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b.

Refueling operations.

i c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

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f.

Fire Protection Program implementation.

I g.

PROCESS CONTROL PROGRAM implementation.

i h.

OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Each procedure of 6.8.1 and other procedures which the Plant Manager or Plant Support Manager has determined to affect nuclear safety, and changes thereto, shall be reviewed by the PRB and approved by the appropriate. member of plant management,- designated by the' Plant Manager or Plant Support Manager, prior to implementation. The Plant Manager or Plant Support Manager will approve administrative procedures, security plan implementing procedures, and changes thereto. The Manager Plant Training and Onsite Emergency Preparedness shall approve the emergency plan' implementing procedures and changes hereto. All other procedures of this specification and changes thereto will be approved by the department head designated by the Plant Manager or. Plant Support Manager.- The procedures of this specification shall be reviewed periodically as set forth in administrative procedures.

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

a.

The intent of the original procedure is not altered.

HATCH - UNIT 1 6-13 Amendment No. 145 9

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ADMINISTRATIVE CONTROLS l

l b.

The change is approved by two members of the plant management l

staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected, e

I c.

The change is documented, reviewed by the PRB and approved in writing by the Plant Manager or Plant Support Manager,-or his l

l designee as assigned by 6.8.2, within 14 days of implementation.

6.8.4 Proposed changes to procedures for implementing the responsibilities l

specified in section 6.1.2 shall be reviewed and approved by the Manager Radiological Safety or his designee.

When deemed appropriate by the Manager J

Radiological Safety, such proposed changes shall also be reviewed by the J

l Safety Review Board prior to implementation.

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HATCH - UNIT 1 6-13a Amendment No. 145

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TABLE OF CONTENTS Section M

1.0 Definitions 1-1 l

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2. 0 (Section Deleted) e, j-3.0 Bivironmental Monitoring - Deleted 1 l

4.0 Special Surveillance and Study Activities 4-1 1

4.1 Erosion Control Inspection 4-1 4.2 Unusual or Important Events' Requirements 4-1 4.3 Exceeding Limits of Other Relevant Permits 4 ~ 5. 0 Administrative Controls 5-1 5.1 Responsibility.

5-1 i

4 P

5.1.1 General Manager 5-1 1

5-1~

5.1.2 General Manager - Quality Assurance 5.2 Organization 5-1 i

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5.3 Review and Audit 5-2 5.3.1 Independent Review 5-2

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5.3.2 Audit Responsibility 5-3 5.4 State and Federal Permits and Certificates 5-3 i

5.5 Procedures 5-3 5.5.1 Quality Assurance of Program Results 5-4 5.5.2 Compliance with Procedures 5-4 5.5.3 Changes in Procedures and Station i

5-4 l

Design or Operation 5.5.4 NRC Authority to Require Revisions 5-6 i

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Amendment No. 145 O

1 5.0 Administrative Controls This section describes administrative and management controls established to implement the Environmental Technical Specifications (ETS). Measures specified in this section include assignments of responsibility, review and audit functions, procedures, and reporting requirements.

Corporate responsibility for implementing the ETS and for assuring that the station is operated in such a way as to provido protection for the environment rests with the Senior Executive Vice President.

Responsibilities 'for compliance with the ETS and for the environmental monitoring program required by the ETS are given below.

Independent audit shall be provided, as discussed in section 5.3.2, by the General Manager-Quality Assurance.

l 5.1 Responsibility 5.1.1 The Plant Manager is responsible for the environmental monitoring programs.

The Plant Manager is also responsible for implementing the special surveillance activities described in section 4.

5.1.2 The General Manager-Quality Assurance is responsible for assuring that the periodic audits of plant operations and the environmental

' monitoring activities to ensure conformance with the ETS are conducted.

5.2 Organization Company organization relative to environmental matters is presented in Chapter 13 of the Plant Hatch Unit 2 updated Final Safety Analysis Report.

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l HATCH - UNIT 1 5-1 Amendment No. 145 a

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I 5.3 Review and Audit i

5.3.1 Independent Review

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5.3.1.1' he Manager of Environmental Affairs shall review the following:

a.

Prox > sed changes to plant systems or equi nt, provided I

suca changes are identified by the Plant Review Board (PRB) as having a potential' adverse environmental impact.

b.

Proposed changes to the Environmental Technical l

Specifications (ETS).

l 5.3.1.2 he Safety Review Board (SRB) shall review the l

following:

)

a.

Proposed changes to the ETS.

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b.

Violations of ETS to detemine whether adequate l

corrective action is being taken to prevent recurrence.

c.

Procedures or changes hereto, which could affect the monitoring of station operation,, that may be considered by the Manager of Bivironmental Affairs or the PRB to be I

appropriate for SRB review.

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5.3.1.4 he PRB shall review the following:

Proceduresfor_ implementing'theresponsibilities a.

specified in section 5.1.1 and proposed changes j

thereto.

i b.

Proposed changes to the ETS.

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Amendment No. 145

5.3.2 Audit Responsibility 5.3.2.1 The General Manager-Quality Assurance is responsible for an audit, conducted annually, of the activities of the Plant Manager and the Manager-Environmental Affairs, related to compliance with ETS.

5.3.2.2 Audits of facility activities shall be performed annually under the cognizance of the SRB to ensure conformance of facility operation to provisions of the ETS.

5.4 State and Federal Permit and Certificates Section 401 of PL 92-500, the Federal Water Pollution Control Act Amendments of 1972 (FWPCA), requires any applicant for a Federal license or permit to conduct any activity that may result in any discharge into provisions of Sections 301, 302, 306, and 307 of the FWPCA. Section 401 of PL 92-500 further requires that any certification provided under this section shall set,any effluent limitations and other limitations and monitoring requirements necessary to assure that any applicant for a Federal license or permit will comply with the applicable limitations. Certifications provided in accordance with Section

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401 set forth conditions on the Federal license or permit for which the certification is provided.

Accordingly, the licensee shall comply with the requirements set forth in the currently applicable 401 certification and amendments thereto issued to the licuses by the Georgia Environmental Protection Division.

I In accordance with the provisions of the Georgia Water Quality

(

Control Act, the FVPCA and the rules and regulations promulgated J

pursuant to each of these acts, the Georgia Environmental l

Protection Division, under authority delegated by the U.S. EPA, I

issued NPDES permit No. GA 0004120 to the licensee. The NPDES permit authorizes the licensee to discharge from HNP Units 1 and 2 to the Altamaha River in accordance with effluent limitations, monito' ring requirements, and other conditions stipulated in the permit, effective August 1, 1983, through December 5, 1987.

Subsequent revisions to the certifications will be accommodated i

in accordance with the provisions of section 5.6.3.

1 5.5 Procedures Detailed written procedures, including applicable checklists and i

instructions, shall be prepared and followed for all activities involved in implementing the ETS. All procedures shall be l

maintained in a manner convenient for review and inspection.

l Procedures that are the responsibility of the Plant Manager shall be kept at the plant.

Procedures that are the responsibility l

of the Manager-Environmental Affairs shall be kept at the Georgia Power l

Company General Office.

HA1CH - UNIT 1 5-3 Amendment No. 145 1

l

5.5.1 Quality Assurance of Program Results I

Procedures shall be established to assure the_ quality of FIS program

results, including analytical measurements.

These l

procedures shall document the program in policy directives, designate responsible organizations or ind.viduals, describe purchased services (e.g., contractual laboratory or other I

contract services), and provide for audits of results and procedures by licensee personnel.

In addition, these quality

)

essurance procedures shall provide fer systems to identify and j

correct deficiencies in technical monitoring programs or related i

administrative activities, to investigate anomalous or suspect results, and to review and evaluate program results.

5.5.2 Compliance with Procedures 1

1 in addition to the. procedures specified.in Section 5.5, the.

station operating procedures shall include provisions to ensure l

that each Unit and all its systems and components are operated in compliance with the conditions established in the Environmental Technical Specifications (EIS).

5.5.3 01anges in Procedures and Station Design or Operation Changes in the procedures and

ation design or operatior, may be made.in accordance with Section 3.3 and subject to the conditions described below:

)

i a.

The licensee may make changes in the stations design. and operation and conduct tests and experiments without prior NRC l

approval, unless the proposed change, test or experiment involves either a change in the objectives of the ETS, an unreviewed environmental question of substantive impact.

l

!L 5-4 l

i Amendment No. 145

b.

A-proposed change, test, or experiment shall be deemed

.to involve an unreviewed environmental question if it concerns:

1.

A matter which may result in a significant increase in any adverse environmental impact previously evaluate

1. - the final environmental statement, as e

modified uy staff's testimony at the hearing, supplements thereto, environmental impact appraisals, or in initial or final adjudicatory decisions.

2.

A significant change in effluents or power level.

3.

A matter not previously reviewed and evaluated in the documents specified above which may have a significant adverse environmental impact.

]

l c.

The licensee shall maintain records of changes to facility l

design or operation made pursuant to this section. The l

c' licensee also shall maintain records of tests and experiments

)

carried out pursuant to paragraph'(a) of this section.

These q

records shall include a written evaluation which provides the bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question of substantive impact, or does not constitute a change in the objectives of the ETS. The licensee shall l

furnish to.the NRC, annually or at such shorter intervals as may be specified in the. license, a report.containing descriptions, analyses, interpretations, and evaluations of such changes, tests, and experiments.

1 d.

Proposed changes or modifications to plant systems or l

l equipment shall be reviewed in accordance with Section 5.3.

e.

Proposed changes to procedures for implementing the l

responsibilities specified in Section 5.1.1 shall be.

reviewed and approved by the Plant Review Board (PRB).

Temporary changes to the procedures that do not change the intent of the original procedure may be made with the concurrence of two members of the plant management staff, at leest one of whom holds a Senior Reactor Operators license I

on the unit af"ected.

Such changes shall be documented and subsequently reviewed by the PRB.and approved by the Plant Manager within 34 days of implementation.

i l

HATCH - UNIT 1 5-5 Amendment No. 145

7--------.--

5.5.4 NRC Authority to Require Revisions j

i The NRC may require modification or revision of changes made by the licensee I

in accordance with section 5 5.3, as a result of NRC reviews of the results l

l of these programs, if.such modifications or revisions are judged necessary to maintain consistency with the initially approved program descriptions or L

with the intent of the ETS.

The NRC also may require modifications or revisions because of changes in plant operation or changes in! environmental conditions or concerns associated with plant operation.

I

~

5.6 Plant Reporting Requirements 5.6.1 Rodtine Reports Annual Environmental Surveillance Report 1

A report on the environmental surveillance program for the previous calendar year shall be submitted to the NRC within 90 days after January 1 of each year.

The report shall include i

I l

e 5-6 Amendment No. 145

(

summaries., analyses, and interpretations or statistical evaluations, where appropriate, of the results of the environmental monitoring activities for the report period.

l The Annual Environmental Surveillance Report also will include the following:

a.

Comparison with preoperational studies, with operational-controls (as appropriate), and with previous environmental mor,itoring reports.

b.

An assessment of the observed impacts of plant operation on the environment.

c.

A summary of:

1.

All instances of Environmental Technical Specifications (EIS) noncompliance and corrective actions taken to remedy them.

2.

Changes to Federal and State permits and

[

certificates made in accordance with 5.6.3.

3.

Ganges in station design or operation that could I

involve an environmental impact or change in the findings of the final environmental statement.

(

4.

Ganges in the EIS.

l 5.

Copies of all reports regarding station discharges l

made in accordance with NPDES permit No GA 0004120 (and subsequent revisions); these shall include i

reports made in accordance with Parts IB and III of l

the NPDES permit.

If harmful effects or evidence of irreversible damage are detected by monitoring, the Jicensee shall provide a further analysis of the problem and a proposed course of action to l

alleviate the problem.

l Results of analysis of all nonradiological environmental data collected shall be summ&rized and tabulated on an annual basis.

In the event that some results are not available within 90 days ~

after January 1, the report shall be submitted, noting and explaining the missing results. The missing data shall be submitted as soon thereafter as possible in a supplementary report.

5-7 l

Amendment No. 145 o

i J

Proposed changes to the ETS shall be reviewed and approved by the Manager-Environmental Affairs, the Plant Review Board, and

)

the Safety Review Board.

Prior to approval, the possible impact j

of the proposed changes will be evaluated.

5.6.3.2 01anges in Pemits and Certificates

~

01anges or additions to required Federal, State, local..and regional authority permits and certificates for the protection j

of the environment that pertain to the requirements of the ETS shall be reported to the NRC wi. thin 30 days.

In the event that the ' licensee initiates.or becomes mare of a request for changes to any water quality requirements, limits, or values stipulated in any certificate or pemit issued pursuant to Section 401 or-402 of PL 92-500, which are also the subject of an EIS reporting requirement, t.he NRC shall be notified concurrently with the authorizing agency. The notification to the NRC shall include

)

an evaluation of the environmental impact of the revised requirement, limit, or value being sought.

If, during the NRC's review of the proposed change, it is

}

detemined that a potentially severe environmental impact could result from the change, the NRC will consult with the authorizing agency to detemine the appropriate action to be taken.

5.7 Records Retention F.

5. 7.1 Records and logs relative to the following areas shall be made and retained for the life of the plant in a manner convenient for review and inspection.

These logs shall be made available to the NRC on request. ;

l Records and drawings detailing plant design changes and a.

modifications made to systems and equipment as described i

in secti'on 5.5.3.

b.

Records of all data fram environmental monitoring.and surveillance programs required by the E15.

5.7.2 All other records and logs relating to the ETS shall be retained, in a manner convenient for review and inspection, for 5 years following logging or recording.

5.7.3 1hese records shall be stored at the plant or at the Georgia Power Company General Office, as appropriate, under the control of the responsible organization.

l S-9 Amendment No. 145 a

o UNITED STATES i

g

[

g NUCLEAR REGULATORY COMMISSION l

E

<j WASHINGTON, D. C. 20555'

\\...../

GEORGIA POWER COMPANY i

OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 502366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 I

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 c

License No. NPF-5 l

l 1.

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

A.

The applications for. amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No.'NPF-5 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated February 17, May 16 August 27, October 27, and November 24. 1986, 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.

I provtsfons of the Act, and the rules and regulations of the l

Comission, j

C.

There is reasonable assurance (1) that the activities authorized by l

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted 1

in ccapliance with the Comission's regulations set forth in 10_CFR Chapter I; D.

The issuance of this amendment will not be inimical'to the l

common defense and security or to the health.and safety of the-public; and E.

The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comission's regulations end all cpplicable requirements have.

been satisfied.

l l 2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is Kereby amended to read as follows:

'. ~

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 80, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i'

,/

LS-B. J. Youngblood, Director Project Directorate II-3 Division of Reactor Projects-I/II

Attachment:

l Changes to the Technical Specifications Date of Issuance: August 10, 1987 l

i 6

i

i ATTACHMENT TO LICENSE AMENDMENT NO. 80 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO.- 50-366 Replace the following pages of the Appendix A. Technical Specificalidns with the. enclosed pages.. The revised pages are identified by amendment number and contain vertical lines indicating the. areas of change.

Remove Insert Page Page_

j 5-1 5-1:

5-2 5-2 i

5-3 5-3 6-1 6-1 6-la 6-la 6-5 6-5 g.

6-6 6-6 i

6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 l

6-11 6-11 6-12 6-12 6-12a 6-12a Replace the following pages of the Appendix B Technical Specifications with the enclosed pages.

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

l Remove Insert l

Page Page-i 1

5-1 5-1 5-2 5-2 5-3 5-3 5-4 5-4 5-5 5-5 5-6 5-6 5-7 5-7 5-9 5-9 A

l 5.0 DESIGN FEATURES l

1 5.1 SITE

,QCLUSIONAREA e -

5.1.1 The exclusion area shall be as shown in Figure 3.11-1.

LOW POPULATION ZONE 5.1.2 The low population zone coincides with the exclusion area and is also shown in Figure 3.11-1.

5.2 CONTAINMENT c

CONFIGURATION 5.2.1 The primary

• containment is a steel structure composed of a series of vertical right cylinders and truncated cones which form a drywell.

This drywell is attached to a suppression chamber through a series of vents.

The suppression chamber is a steel pressure vessel in the shape of a torus. The primary containment has a total minimum free air volume of 255,978 cubic feet.

DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:

Maximum design internal pressure 56 psig. '

a.

b.

Maximum allowable internal pressure 62 psig.

S.'d c.

Maximum internal temperature 340*F.

i e

d.

Maximum external pressure 2 psig.

,[

I 1

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall consist of.not more than 560 fuel assemblies and shall be limited to those fuel assemblies which have been analyzed with NRC approved l

codes and methods and have been shown to comply with all Safety Design Bases in the Final Safety Analysis Report (FSAR).

i 1

1

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HATCH - UNIT 2 5-1 Amendment No. 80 L

3, o

l I

i l

l l.

I e.

i l

l l

1 i

1 l

l (This page intentionally blank)

I i

I i

BATCH - UNIT 2 5-2 Amendment No. 80 9*

l 1 4

DESIGN FEATURES CONTPOL ROD ASSEMBLIES 5.3.2 The reactor core chall contcin 137 cruciform-shaped controi rod

^

l.

assemblies.

t 5.4 REACTOR COOLANT SYSTEM l

DESIGN PRESSURE ~ APO TEMPERATURE 5.4.1 The reactor coolant system is' designed and shall be maintained:

a.

In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal. degradation pursuant to the applicable Surveillance Requirements,.

b.

For a pressure of 1250 psig, and c.

For a temperature of 5750F.

VOLLNE ll 5.4.2 The total water and steam volune of the reactor vessel and recirculation system is approximately 17,050 ctbic feet at a nominal Teve of 5400F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The primary and backup meteorological towers shall be located as shown on Figure 3.11-1.

i 5.6 FUEL STORAGE CRITICALITY 5.6.1 The.new and spent fuel storage racks are. designed and shall be maintained with sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a kerf eouivalent to 4.0.95 when flooded with unborated water.

The. kerr of 4 0.95 includes.

~

conservative allowances for uncertainties.

4 HATCH - UNIT 2 5-3 Amendment No. 80 6

6.0 ADMINISTRATIVE CONTROLS 6.1 Resp 0NSIBILITY 6.1.0 The Vice President-Plant Hatch shall provide direct executive oversight over all aspects of Plant Hatch.

~

6.1.1 The Plant Manager shall be responsible for overall unit 6peration, except for the Radiological Environmental. Monitoring Program as,de, scribed below and for delegation in writing.of the succession of this responsibility during his absence.

Certain plant support functions shall be the responsibility of the Plant Support Manager, i

6.1.2 The Manager Radiological Safety shall be responsible for the Radiological Environmental Monitoring Program as described in the 1

Specification 3/4.16 of Unit I and for the writing of the Annual-Radiological Environmental Surveillance Report..The Manager Radiological Safety shall review the proposed changes to plant systems or equipment, provided that such I

changes are identified by the Plant Review Board (PRB) as having a potential _

radiological environmental impact.

J 6.1.3 Each of the above-mentioned individuals is responsible-for the accuracy i

p of the procedures needed to implement his responsibilities.

l 6.2 ORGANIZATION 0FFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in Chapter 13 of the Plant Hatch Unit 2 updated Final Safety Analysis Report.

UNIT STAFF i

6.2.2 The unit organization shall be as shown in Chapter 13 of the Plant Hatch Unit 2 updated Final Safety Analysis Report.

a.

Each on duty shift shall be composed of at least the minimum shift i

crew composition shown in Table 6.2.2-1.

b.

At least one licensed Operators shall be in the control room for each reactor containing fuel.

c.

At least two licensed Operators shall be present in the control roon for each reactor in the process of start-up, scheduled reactor shutdown and during recovery from reactor trips.

d.

An individual qualified to implement radiation protection procedures shall be on site when fuel is in either reactor, All CORE ALTERATIONS shall be directly supervised by either a e.

licensed Senior Reactor Operator-or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

HATCH - UNIT 2 6-1 Amendment No. 80 3

I ADMINISTRATIVE CONTROLS f.

A Fire Team of at least five members shall be maintained onsite at all times. The Fire Team shall not include the minimum shift crew necessary for safe shutdown on Units 1 and 2 or any personnel i

required for other essential functions during a fire emergency.

i l

g.

AdministrativeproceduresshallbedevelopedandimpleEen'tedto l

limit the working hours of Unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating l

personnel work a normal 8-hour day, 40-hour week while the plant is l

operating. However, in the event that unforeseen problems require j

l substantial amounts of overtime to be used or during extended l

l-periods of shutdown for refueling, major maintenance, or major j

l plant modifications, the following guidelines shall be followed on l

I a temporary basis:

l (1) An individual should not be permitted to work more than 16

)

hours straight, excluding shift turnover time.

l I

(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 i

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 seven day l

period, all excluding shift turnover time.

(3) A break of at least eight hours should be allowed between work periods, including shift turnover time.

l (4) Except during extended shutdown periods, the use of overtime thould 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 higher levels of management, in accordance with l

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 dssigned. Routine deviation from the above guidelines is not authorized.

Amendment N, 80 RATCH - UNIT 2 6-la

, uwemnaam stwnne 6.3 UN8T STAFF QUALIFICATIONS 6.3.1.

Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1< 1971 for comparable positions, except for the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Shift

{

Technical Advisor who shall have a bachelor s degree or equiva'ient in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients. and accidents.

6.4 TRAINING

)

6.4.1.

A retraining and replacement training program for the unit staff

)

l shall be maintained under the direction of the Manager of Training and l

shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and. Appendix "A" of 10 CFR Part 55.

{

6.4.2.

A training program for fire protection shall be maintained under the direction of the Senior Regulatory Specialist and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except for fire protection training sessions which shall be held at least once per p

92 days.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB) l FUNCTION l

6. 5.1.1.

The PRB shall function to advise the Plant Manager on all

{

matters related to nuclear safety.

COMPOSITION 6.5.1.2.

The PRB shall be composed of, as a minimum, a supervisor or i

higher level individual from each of the departments listed below:

j Operations Maintenance Quality Control (QC)

Health Physics Nuclear Safety and Compliance Engineering Support The Chairman, his alternate, and other members of the PRB shall be designated by the Plant Manager.

The Chairman and his designated alternate shall both be managers of one of the six above listed departments or a higher level onsite manager.

ALTERNATES 6.5.1.3.

All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PRB activities at any one time.

HATCH - UNIT 2 6-5 Amendment No. 80

~ = =

• ~ *

-_.-________._-_J-

j ADMINISTRATIVE CONTROLS MEETING FREQUENCY 1

6.5.1.4 The PRB shall meet at least once per calendar month and as convened I

by the PRB Chairman or his designated alternate.

r QUORUM 6.5.1.5 The minimum quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three voting members including alternates.

RESPONSIBILITIES 6.5.1.6 The Plant Review Board shall be responsible for:

a.

Review of all procedures required by Specification 6.8 and l

changes thereto, except those for the Radiological Environmental

(.

Monitoring Program, any other proposed procedures or changes thereto as determined by the Plant Manager to af feet nuclear safety.

[

l b.

Review of all proposed tests and experiments that sffect nuclear safety.

l c.

Review of all proposed changes to Appendix "A" Technical Specifications.

d.

Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

Investigation of all reportable violations of the Techn'ical

]

e.

Specifications including the preparation and forwarding of reports' covering evaluation and recommendations to prevent recurrence to the Vice President-Plant Hatch, the Senior Vice President-Nuclear Operations, and to the Safety Review Board (SRB).

f.

Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.

g.

Review of unit operations to detect potential nuclear safety hazards.

h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Manager or the SRB.

l HATCH - UNIT 2 6-6 Amendment Nc. 80

l ADMINISTRATIVE CONTROLS 1

l l

l RESPONSIBILITIES (Continued) l 1.

Review of the Security Plan and implementing procedures and shall submit recommended changes to the SRB.

J.

Review of the Emergency Plan and implementing procedures and shall submit recommended chcnges to the SRB.

k.

Review of any unplanned onsite release of radioactive material to the environs when such release is in excess of 1 C1, excluding dissolved i

and entrained gases and tritium for liquid effluents, and in excess j

l of 150 Ci of noble gases or 0.02 C1 of radiofodines for gaseous l

effluents. Also included is the preparing and forwarding to the Plant Manager and the SRB reports covering evaluation, recommendations l l

and disposition of the corrective action to prevent recurrence.

I 1.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE h

DOSE CALCULATION MANUAL (ODCM), except for the section on the

[

Radiological Environmental Monitoring Program in the ODCM.

I Review of proposed change (s) to plant sy' stems and equipment to m.

determine whether the proposed change has a potential radiological environmental impact.

Such change (s) will be reported to the Manager-R.;diological Safety.

AUTHORITY l

6.5.1.7 The PRB shall:

Recommend in writing to the Plant Manager approval or disapproval a.

of items considered under 6.5.1.6(a) through (d) above.

b.

Render determinations in writing with regard to whether or not each' i

item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President-Plant Hatch, the Senior Vice President-Nuclear Operations, and the Safety Review Board of disagreement between the PRB and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1-above.

RECORDS 6.5.1.B The Plant Review Board shall maintain writtr., minutes of each PRB meeting that, at a sinimum, document the results of a ll PRB activities performed under the responsibility and authority provisions of these Technical Specifications. Copies shall be provided to the Vice President-Plant Hatch, the Senior Vice President-Nuclear Operations, and the Safety Review Board.

HATCH - UNIT 2 6-7

' Amendment No. 80 a

f.

l l

)

i ADMINISTRATIVE CONTROLS j

{

l 6.5.2.

SAFETY REVIEW BOARD (SRB)

FUNCTION

)

t 6.5.2.1.

The SRB shall function to provide independent review and audit l

of designated activities in the areas of:

a.

Nuclear power plant operations.

b.

Nuclear Engineering.

l c.

Chemistry and radiochemistry.

?

1

(

d.

Metallurgy.

]

{

e.

Instrumentation and control.

j f.

Radiological safety.

]

g.

Mechanical and electrical engineering.

h.

Quality assurance practices.

COMPOSITION j

6.5.2.2.

The SRB shall be composed of a minimum of five persons who as a l

group provide the expertise to review and audit the operation of a nuclear power plant.

The Chairman and other members shall be appointed by the Senior Vice President - Nuclear Operations or such other person as he shall designate.

The composition of the SRB shall meet the t

requirements of ANSI N18.7-1976.

ALTERNATES 6.5.2.3.

All alternate members shall be appointed in writing by the SRB Chairman to serve on a temporary basis; however, no more than a minority

^

l of alternates shall participate as voting members in SRB activities at any one time.

However, in extenuating circumstances, the Senior Vice President Nuclear Operations may designate the use of additional l

alternates with voting authority when regular members are not available within necessary time constraints.

CONSULTANTS 6.5.2.4.

Consultants shall be utilized as determined by the SRB Chairman to provide expert advice to the SRB.

MEETING FREQUENCY 6.5.2.5.

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

l HATCH,- UtlIT 2 6-8 Amendmat No. 80

~

l ADMINISTRATIVE CONTROLS l

I QUORUM 6.5.2.6.

The minimum quorum of the SRB necessary for the performance of the SRB review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and.at.least a l

majority of the memoers.

No more than a minority. of the quorum shall have line responsibility for operation of the unit.

REVIEW

6. 5. 2. 7.

The SRB shall be responsible for the review of:

a.

The safety evaluations for (1) changes to procedures,- equipment, l

~

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 systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR. 1 c.

Proposed tests or experiments which involve an unreviewed safety j

question as defined in Section 50.59, 10 CFR.

j d.

Proposed changes to 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.

i f.

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

g.

Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission, i

h.

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

1.

Reports and meeting minutes of the Plant Review Board.

HATCH ~- UNIT 2 6-9 Amendment No. 80 o

f.

l ADMIflISTRATIVE CONTROLS 1

AUDITS 6.5.2.8.

Audits of unit activities shall be performed urider the H

cognizance of the SRB.

Each inspection or audit shall be gerformed within the specified time interval with:

1.

A maximum allowable extension not to exceed 25%

of the inspection or audit interval.

2.

A total maximum combined interval time for any 3 consecutive i

inspection or audit intervals not to exceed 3.25 times the l

specified inspection or audit interval.

j I

These audits shall encompass:

a.

The conformance of unit operation to provisions contained within

[

the Technical Specifications and applicable license conditions J

at least once per 12 months.

b.

The performance, training and qualifications of the entire unit staff at least once per 12 months.

l

?

l c.

The results of actions taken to correct deficiencies occurring J

l in unit equipment, structures, systems or method of operation l

that affect nuclear safety at least once per 6 months.

i l

d.

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

10 CFR 50, at least once 24 months, e.

The Emergency Plan and implementing procedures at least once per 12 mtnths shall be performed by individuals who have no direct responsibility for implementation of this plan.

f.

The Security Plan and implementing procedures at least once per 12 months shall be performed by individuals who have no direct responsibility for implementation of this plan, g.

Any other area of unit operation considered appropriate by tne SRB or the Senior Vice President - Nuclear Operations.

l h.

The Fire Protection Program and implementing procedures at least once per 24 months.

i. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite license personnel or an outside fire protection firm,

j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

During the year in which the inspection or audit

occurs, the requirements of 6.5.2.8.i. can be affected concurrently.

l HATCH - UNIT 2 6-10 Amendment No. 80 o

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Lmeuna samm I

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The Radiological Environmental Monitoring Program and the results thereof annually, i

1.

The Offsite Dose Calculatf ori Manual, Process Control Program,

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and implementing procedures at least once per 24 months.

AUTHORITY

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6.5.2.9 The SRB shall report to and advise the Senior Vice President -

Nuclear Operations on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

4 RECORDS 6.5.2.10. Records of SRB activities shall be prepared, approved and distributed as indicated below:

a.

Minutes of each SRB meeting shall be. prepared, approved and forwarded to the Senior Vice President-Nuclear Operations l

within 14 days following each meeting.

b.

Report's of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to'the Senior Vice. President-Nuclear-Operations within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be-forwarded to the Senior Executive Vice President, the Senior-Vice President-Nuclear Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.-

b.

Each REPORTABLE OCCURRENCE requiring notification to the Commission shall be reviewed by the PRB and submitted to the SRB,.

the Vice President-Plant Hatch,' and the Senior Vice President-Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit' is violated:

a.

The unit shall be placed in t,t least HOT SHUTDOWN within two

hours, b.

The Safety Limit violation shall be reported to the Commission, the Senior Vice President-Nuclear Operations,and the SRB l

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

HATCH - UNIT 2 6-11 Amendment No. 80 t

e

ADMINISTRATIVE CONTROLS

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SAFETY LIMIT VIOLATION (Continued)

A Safety Limit Violation Report shall be prepared.

The report c.

shall be reviewed by the PRB.. 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.

I d.

The Safety Limit Violation Report shall be submitted to the Commission, the SRB, the Vice President-Plant Hatch, and the Senior Vice President-Nuclear Operations within 14 days of the violation.

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J 6.8 PROCEDURES 6.8.1 Written procedures shall be es'ablished, implemented and maintained t

covering the activities referenced below:

The applicable procedures recommended in Appendix'"A" of Regulatory a,

Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

I g.

PROCESS CONTROL PROGRAM implementation.

h.

OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Each procedure of 6.8.1 and other procedures which the Plant Manager or Plant Support Manager has determined to affect nuclear safety, and changes thereto, shall be reviewed by the PRB and approved by the appropriate member of plant management, designated by the Plant Manager or Plant Support Manager, prior to implementation. The Plant Manager or Plant Support Manager will approve administrative procedures,. security plan implementing procedures, and changes thereto.

The Manager Plant Training and Onsite Emergency Preparedness shall approve the emergency plan implementing procedures and changes theretc.. All other procedures of this specification and changes thereto will be approved by the department head designated by the Plant Manager or Plant' Support Manager. The procedures of this specification.

shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedure's of 6.8.1 above may be made provided:

a.

The intent of the original procedure is not altered.

i HATCH - UNIT 2 6-12 Amendment No. 80

ADMINISTRATIVE CONTROLS

b. 'The change is approved by two members of the plant management staff, at'least one of whom holds a Senior Reactor Operator's

- License on the unit affected.

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c.

The change is documented, reviewed by the PRB and approved in writing by the Plant Manager or Plant Support Manager, or.his designee as assigned by 6.8.2, within 14 days of implementation.

6.8.4 Proposed changes to procedures for implementing the responsibilities specified in section 6.1.2 shall be reviewed and approved by the Manager Radiological Safety or his designee. When deemed appropriate by the Manager Radiological Safety, such proposed changes shall also be reviewed by the Safety Review Board prior to implementation.

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HATCH - UNIT 2 6-124 Amendment No. 80 9

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1 TABLE OF CONTENTS Section Page 1.0 Definitions 1-1 i

j' 2.0 (Section Deleted) e -

t 3.0 Ihvironmental Monitoring - Deleted 3-1 4.0 Specisi Smveillance and Study Activities 4-1 4.1 Erosion Control Inspection 4-1 4.2 linusual or Important Events Requirements 4-1 4.3 Exceeding Limits of Other Relevant Permits 4-1 5.0 Administrative Controls 5-1 5.1 Responsibility 5-1 I

5.1.1 General Manager 5-1 5.1.2 General Manager - Quality Assurance 5-1 1

5.2 Organization 5-1

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5.3 Review and Audit 5-2 b..-

5.3.1 Independent Review, 5-2 5.3.2 Audit Responsibility 5-3 5.4 State and Federal Permits and Certificates 5-3 l

5.5 Procedures 5-3 f

5.5.1 Quality Assurance of Program l-Results 5-4 5.c.2 Compliance with Procedures 5-4 5.5.3 Changes in Procedures and Station Design or Operation 5-4 5.5.4 NRC Authority to Require Revisions 5-6 i

I i

Amendment No. 80 Q_--_-_-_--__.___-_-_----__-

5.0 Administrative Controls This section describes administrative and management controls established to implement the Environmental Technical l,

Specifications (ETS). Measures specified in this section l

include assignments of responsibility, review and audit L.

functions, procedures, and reporting requirements.

Corporate responsibility for. implementing the ETS and for assuring that the station is operated in such a way as to provide protection for the environment rests with the Senior Executive Vice President.

Responsibilities 'for compliance with the ETS and for the environmental monitoring program required by the ETS are given below.

Independent audit shall be provided, as discussed in section 5.3.2, by the General Manager-Quality Assurance.

l 5.1-Responsibility 5.1.1 The Plant Manager is responsible for the environmental monitoring programs.

The Plant Manager is also responsible for implementing the special surveillance activities described in section 4.

5.1.2 The General Manager-Quality Assurance is responsible for. assuring that the periodic audits of plant operations and the environmental monitoring activities to ensure conformance with the ETS are conducted.

5.2 Organization Company organization relative to environmental matters is presented in Chapter 13 of the Plant Hatch Unit 2 updated Final Safety Analysis Report.

HATCH-UNIT 2 5-1 Amendment No. 80 o-e

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5.3 Review and Audit 5.3.1 Independent Review 5.3.1.1 he Manager of Environmental Affairs shall review the following:

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a.

Prowsed changes to plant systems or equip nt, provided' such changes are identified by the Plant Review Board (PRB) as having a potential adverse environmental impact.

b.

Proposed changes to the.

Environmental Technical l

l l

Specifications (ETS).

i 1

5.3.1.2 The Safety Review Board (SRB) shall review the l

following 1

a.

Proposed changes to the EIS.,

P-b.

Violations of ETS to detemine whether adequate corrective action is being taken to prevent recurrence.

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c.

Procedures or changes hereto, which could affect the

)

monitoring of station operation, that may be considered by the Manager of Ehpironmental Affairs or the PRB to' be appropriate for-SRB review.

r..-

5.3.1.4 1he PRB shall review the following:-

a.

Procedures for implementing the responsibilities l

specified in section 5.1.1 and proposed changes thereto.

b.

Proposed changes to the ETS.

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l 5-2 Amendment No. 80 o

w- -

5.3.2 Audit Responsibility 5.3.2.1 The General Manager-Quality Assurance is responsible for an audit, conducted annually, of the activities of the Plant Manager and the Manager-Environmental Affairs, related to compliance with ETS.

5.3.2.2 Audits of-facility activities shall be performed annually under the cognizance of the SRB to ensure conformance,,

of facility operation to provisions of the ETS.

5.4 State and Federal' Permit and Certificates Section 401 of PL 92-500, the Federal Water Pollution Control Act Amendments of 1972 (FWPCA),. requires any applicant for a Federal license or permit-to conduct any activity that may result in any discharge into provisions of Sections 301, 302, 306, and 307 of the FWPCA. Section 401 of. PL 92-500 further requires that any certification provided under this section shall. set any effluent. limitations and other limitations and

?-

monitoring requirements necessary to assure that any applicant i

-for a Federal license or permit w111 comply with the applicable j

limitations. Certifications provided in accordance.with Section 401 set forth conditions on the Federal license or permit for which the certification is provided. Accordingly, the licensee shall comply with the requirements set forth in the currently applicable 401 certification and amendments.thereto issued to j

the licensee by the Georgia' Environmental P.rotection. Division.

In accordance with the provisions of the Georgia Water Quality-Control Act, the FWPCA and the rules and regulations promulgated pursuant to each of these acts, the Georgia Environmental Protection Division, under authority delegated by the U.S. EPA, issued NPDES permit No. GA 0004120 to the licensee. The NPDES j

permit authorizes the licensee to discharge from HNP Units 1 and l

2 to t,he' Altamaha River in accordance with effluent limitations, monitoring requirements, and other conditions stipulated in the permit, effective August 1,1983, through December 5,1987.

Subsequent revisions to the certifications will be accommodated in accordance with the provisions of section 5.6.3.

- i i

5.5 procedures i

s Detailed written procedures, including applicable checklists and Instructions, shall be prepared and followed-for all activities i

involved in implementing the ETS. All procedures shall be maintained in a manner convenient for review and inspection.

Procedures that are the responsibility of the Plant Manager

-shall be kept at the plant.

Procedures that are the responsibility of the Manager-Environmental Affairs shall be kept at.the Georgia Power Company General Office.

4 i

HATCH-UNIT 2 5-3 Amendment No. 80 1

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5.5.1 Quality Assurance of Program Results Procedures shall be -established to assure the quality of EIS program.results,-

including analytical measurements.

These procedures shall document the program inindi.plicy directives, designate responsible organizations or

viduals, describe purchased services.(e.g., contractual laboratory or qther-contract services), and provide for audits of results and procedures-by licensee personnel.. In addition, these quality assurance procedures shall provide for systems to identify and correct. deficiencies in technical monitoring programs or related administrative activities, to investigate anomalous or suspect results, and to review and evaluate program results.

5.5.2 Compliance with Procedures in addition to the procedures specified in Section 5.5, the station operating procedures shall include provisions to ensure.

L that each Unit and all its systems and com>onents are operated in compliance with the conditions established in.the Environmental y

J Technical Specifications (ETS)..

5.5.3 Qianges in Procedures and Station Design or Operation-Otanges in the procedures and station design or operation may be made.in accordance with Section 5.3 and subject to the conditions described below:

i L[

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L a.

The licensee may make changes in the stations design and operation and conduct tests and experiments without prior NRC approval, unless the proposed change, test or experiment involves either a change in the. objectives of the EIS, an unreviewed environmental question of substantive impact.

I t

i 5-4 l

Amendment No. 80

l l

1 b.

A proposed change, test, or experiment shall be deemed to involve an unreviewed environmental question if it concerns:

I 1.

A matter which may result in a significant increase s,

1 in any adverse environmental' impact previously evaluated in the final environmental statement, as i

modified by staff's testimony at the hearing, 1

i supplements thereto, environmental impact appraisals, or in initial or final adjudicatory decisions.

2.

A signifi: ant change in effluents or power level.

j

3.. A matter not previously reviewed and evtluated in the documents specified above which m y.have'a significant adverse environmental impact'.

The licensee shall maintain records of changes to facility l

]

c.

design or operation made pursuant to this section.

The 1

licensee also shall.! maintain records of tests and experiments carried out pursuant to paragraph (a) of this section. These records shall include a written evaluation which provides the bases for the determination that the chang'e, test, or experiment does not hvolve an unreviewed environmental question of substantive impact, or does;not constitute a-change in the objectives of the ETS.

The licensee shall furnish to the NRE, annually or at such shorter intervals' as may be specified in'the license, a report containing 6

i descriptions, analyses, interpretations, and evaluations of such changes, tests, and experiments.

.. i d.

Proposed changes or modifications' to plant systems or equipment shall be reviewed in acc;ordance with Section 5.3.

[.

Proposed changes to procedures for implementing the 1l' i

e.

I responsibilities specified in Section 5.1.1 shall be reviewed and approved by the Plant Review Board (PRB).

1 Temporary changes to the procedures that do not/changr.

V the intent of the original probedure nay be aiade?with the concurrence of two members of the plant management staff, at least one of whom holds a Senior Reactor Operators license on the unit affected.. Such changes shall be documented and subsequently reviewed by the PRB and approved by the Plant i

Manager within 14 days of. implementation.4 t

c 9

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A k.

HATCH-UNIT 2 5-5 Amendment No. 80-k

l 5.5.4 NRC Authority to Require Revisions.

De NRC may require modification or revision of changes made by the licensee i

in accordance with section 5.5.3, as a result of NRC reviews of the results i

of these programs, if.such modifications or revisions are judged necessary to maintain consistency with the initially approved program descriptions or.

with the intent of the. ET3.

He NRC also may require modifications ' or revisions because of changes in plant operation or changes inIenvironmental conditions or concerns associated with plant operation.

5.6 Plant Reporting Requirements _

l 5.6.1 Routine Reports Annual Bivironmental Surveillance Report A report on the environmental surveillance program for the previous calendar year shall be submitted to the hRC within 90 days after January 1 of each year. De report shall include L

l

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o h.-

I i

i 5-6 1

l Amendment No.'80 l

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i

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o stmaries, analyses, and interpretations or statistical evaluations, where appropriate, of the results of the environmental monitoring activities for the report period.

'Ihe Anr.ual Environmental Surveillance Report also will include the following:

a.

Comparison with preoperational studies, with operational-l controls (as appropriate), and with previous

~

environmental monitoring reports.

l b.

An assessment of the observed impacts of plant operation on the environment.

c.

A summary of:

r l

1.

All instances of Environmental Technical l

Specifications (ETS) noncompliance and corrective actions taken to remedy them.

2.

Changes to Federal and State permits and certificates made in accordance with 5.6.3.

3.

manges in station design or operation that could I

involve an environmental impact or change in the findings of the final environmental statement.

4.

Ganges in the ETS.

l 5.

Copies of all reports regarding station discharges l

made fn accordance with NPDES permit No GA 0004120 (and subsequent revisioas); these shall include reports made in accordance with Parts 1B and III of the NPDES permit.

i l

If harmful effects or evidence of irreversible damage are detected by monitoring, the licensee shall provide a further analysis of the problem and a proposed course of action to alleviate the problem.

l l

Results of analysis of all nonradiological environmental data l

collected shall be summarized and tabulated on an annual basis.

I In the event that some results are not available within 90 days l

after January 1, the report shall be submitted, noting and

)

explaining the missing results.

The missing data shall be submitted as soon thereafter as possible in a supplementary report.

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i I

l 5-7 l

Amendment No. 80 o

4

l Proposed changes to the ETS shall be reviewed and approved by the Manager-Environmental Affairs, the Plant Review Board, and the Safety Review Board.

Prior to approval, the possible impact of the proposed changes will be evaluated.

l 5.6.3.2 Ganges in Pemits and Certificates

=

Changes or additions to required Federal, State, local, and j

regional authority pemits and certificates for the protection of the environment that pertain to the requirements of the ETS l

shall be reported to the NRC wi. thin 30 days.

In the event that the licensee initiates or becomes aware of a request for changes i

to any water quality requirements, limits, or values stipulated in any certificate or permit issued pursuant to Section 401 or j

402 of PL 92-500, which are also the subject of an ETS reporting

)

requirement, the NRC shall be notified concurrently with the I

l authorizing agency. The notification to the NRC shall include l

an evaluation of the environmental impact of the revised requirement, limit, or value being sought.

l If, during the NRC's review of the proposed change, it is determined that a potentially severe environmental impact could j

result from the change, the NRC will consult with the l

l authorizing agency to detemine the appropriate action to be l _

taken.

S.7 Records Retention

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5.7.1 Records and logs relative to the following areas shall be made and retained for the life of the plant in a manner convenient for review and inspection.

These logs shall be made l

available to the NRC on request.

a.

Records and drawings detailing plant design changes and modification made to systems and equipment as described i

I in section 5.5.3.

l b.

Records of c11 data from environmental monitoring.and surveillance programs required by the ETS.

l 5.7.2 All other records and logs relating to the EIS shall be retained, in a manner convenient for review and inspection, for 5 years following logging or reconfing.

l 5.7.3 These records shall be stored at the plant or at the Georgia Power Company General Office, as appropriate, under the i

control of the responsible organization.

1 5-9 Amendment No. 80 J