Text

Reissued Amends 109 & 47 to Licenses DPR-57 & NPF-5, Respectively,Reflecting Corporate & Plant Staff Reorganization & Deleting Senior Reactor Operator License Requirement for Plant Manager
	ML20134A118
Person / Time
Site:	Hatch
Issue date:	06/27/1985
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20134A099	List: ML20134A097; ML20134A118; ML20134A133; ML20134A144;
References
	TAC-08043, TAC-08095, TAC-8043, TAC-8095, NUDOCS 8508150194
	Download: ML20134A118 (46)
	v • d • e

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1 ff UNITED STATES y

g NUCLEAR REGULATORY COMMISSION

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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.109 License No. DPR-57 1.

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

I A.

The applications for amendment by Georgia Power Company, et al.,

(the licensee) dated July 9,1982. October 24 and December 20, 1983, and April 24, 1984, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Connission; C.

Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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; D.. The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the 4

i public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

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

8508150194 050002 i

PDR ADOCK 05000321 P

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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.109, 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.

FOR THE NUCLEAR REGULATORY COPti!SSION Jjhh F. Sto z, Chief sperating Reactors ranch #4

' ' Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 27,1985 6

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ATTACHMENT TO LICENSE AMEN 0 MENT 40.109

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FACILITY OPERATING LICENSE NO. OPR-57 DOCKET N0. 50-321

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i Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

Remove Insert 6-1 6-1 6-la 6-la 6-2 6-2 1

6-3 6-3 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-11 6-11 6-12 6-12 6-13 6-13 6-21 6-21 Replace the following pages of the Appendix "B" Environmental Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

Remove Insert 5-1 5-1 5-2 5-2 5-3 5-3 5-4 5-4 5-5 5-5 4

5-6 5-6 5-9 5-9 5-11 5-11

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I 6.0 AtxMrmtATIVE CtWNTS 6.1 ESPONSIBILITY 6.1.1 The General Manager-Plant, Hatch shall be responsible for overall unit l

operation and shall delegate in writing the succession to this responsibility durirg his absence.

6.2 CICANI2ATION i

CrT5r!E 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2.1-1.

UNIT STAFT 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and a.

Each cn duty shift shall be composed of at least the minian shift crew composition shown in Table 6.2.2-1.

I b.

At least one licensed Operator shall be in the control room for 1

i ead reactor containing fuel.

I At least two licensed operators shall be present in the control c.

room for and reactor in the process of start-up, scheduled reactor shutdown and &aring recovery from reactor trism.

j d.

An individual qualified to implement radiation protection procedures shall be on site then fuel is in either reactor.

All CDE ALTERTICIS shall be directly supervised by either a e.

licensed Senior peactor operator or senior maactor operator Limited to Fuel Handling tho has no other concurrent responsibilities during this operation.

t f.

A Fire 14mn of at least five members shall be maintained onsite at all times. The Fire tune shall not include the minima shift crew necessary for safe shutdown of Units 1 and 2 or any personnel required for other essential functions during a fire energency.

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MA2QI UNIT 1 6-1 Anendment No. $5,109 i

o AtP'INTFNAmT CCWmnS g.

Administrative procedures shall be developed and ingEshanted to 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. 'Ihe 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 substantial amounts of overtime to be used or during extended periods of shutdown for refueling, major maintenance, or major plant modifications, the following guidelines shall be followed on a tarporary basis (1) An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

(2) An individual should not be permitted to work sore than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nc; more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period, all awM Ming shift turnover time.

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

(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 frem the above guidelines shall be authorized by the General Manager-Plant Hatch or his deputy of higher levels of l

management, in accordance with established procedures and with docunentation of the basis for granting the deviation.

Controls shall be incita3ed in the procedures such that individual overtirre shall be reviewed monthly by the General Manager-Plant Hatch or his l

desipee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

Hmo! CtCT 1 6-la Amend.nent No. 101, 109

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l mm a 1 6-3 Amendrwnt No. $),109

i A NIVTFNATIVF CCNNr" 6.3 tEIT 9:M T QUALIFICATIONS

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6.3.1 Each menber of the unit staff shall seet or exceed the minima qualifications of ANSI N18.1-19'11 for camparable positions except for the Health Physics Superintendent who shall meet or exceed the q' alifications of Degulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and respo nse and analysis of the plant for transients and accidents.

6.4 TRINDC 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

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exceed the requirements and roccanendations 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 tne 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 MVIDs AND AUDIT 6.5.1 PIRFT REVIDi BCARD fPRB)

Pt)CTICN 6.5.1.1 Se PRS shall function to advise the General Manager-Plant Hatch on j

all matters related to nuclear safety.

CINPOSITION 6.5.1.2 D e Plant Review Board shall be ocuposed of the:

Chairman *:

General Manager-Plant Hatcf:

Manber t Deputy General Manager Manber:

Superintendent of Operations Monber:

Superintendent of Maintenance i

Member Health Physics Superintendent Monber:

a g erintendent of Quality Control Manbert Superintendent of Plant Engineering and Service 5 Monber Superintendent of Regulatory Conpliance Manber (non-voting):

Representative of site Quality Assurance T,eneral Manager-Plant Hatch to designate chairman from voting PPB inantership as necessary, i

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRa Chairman to serve on a tenporary basist however, no more than two alternates shall participate as voting meeers in PRB activities at any one time.

HA% H = UNIT 1 6-4 Amendnent No. 55, 77,109 i

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

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6. 5.1. 5 The minimum porum of the FRB necessary for the perfdmance of the FRB responsibility and authority provisions of these Technical Specifications shall consist of the Qiairman or designated Chairman and four l

voting asebers including alternates.

3 RESPONSIBILITIE5 6.5.1.6 The Flant Review Board shall be responsible for:

a.

Review of (1) all procedures required by Specification 6.3 and changes thereto, (2) any other proposed procedures or changes thento as determined by the General Manager-Plant Hatch to affect l

inaclear safety.

b.

Review of all proposed tests and experiments that affect nuclear 1

safety.

1 c.

Review of all proposed changes to Appendix "A"

Technical j

Specifications.

d.

Review of all proposed changes or modifications to unit systems or 4

equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications e.

including the preparation and forwarding of reports covertrig evaluation and recommendations to prevent recurrence to the Manager of Nuclear Generation or the Vice Frosident and General Manager i

Nuclear Operations and to the Safety Review Board (SRA).

I f.

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

4 g.

Review of unit operations to detect potential teaclear safety hasards.

h.

Performance of special reviews, investigations or analyses and reports thereon as rupested by the General Manager-Flant Match or i

the 3RB.

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HATQbUN!T 1 6-7 Mendnent No. H,109 i

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J AININISTRATI\\T CONTR01S RESPONSIBII.ITIES (Continued) 1.

Review of the Security Plan and laplementirig procedures and shall submit recomended charges to the SRB, J.

Review of the Bnergency Plan and implementing procedums and shall submit recomended charges to the SRB.

Atm ORITY 6.5.1.7 The PRB shall a.

Recomend in writig to the General Manager-Plant Hatch approval I

or disapproval of items considered under 6 5.1.6(a) through (d) abw.

b.

Render determinations in writirig with agard to whether or not each ites considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety gaestion.

c.

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

RECORDS 6.5.1.3 The Plant Review Board shall maintain written minutes of each PRB setting that, at a minleum, docment the results of all PRB activities performed under the responsibility and authority provisions of these Technical Specifications. Copies shall be provided to the Manager of Nuclear Generation or the Vice President and General Marnger Nuclear Operations and the Safety Review Board.

6.5.2 SMTIY REVIBt 30AAD (SRA)

FUNCTION 6.5.2.1 The SRB shall function to provide independent review and audit of designated activities in the areas of t s.

Nuclear power plant operations, b.

Nuclear egineering, c.

Chemistry and radiochemistry.

HATQ! - UNIT 1 68 Amendment flo.45.109

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f, AININI!mtAmT CCWMrTM PtDCTION (Continued) d.

Metallurgy, e.

Instrissentation and control, f.

Radiological safety, 9

Mechanical and electrical engineering, h.

Quality assurance pcactices.

CDOCSITION I

6.5.2.2 The SRB shall be composed of a minisman of seven persons who as a grow provide the expertise to review and audit the operation of a nuclear power plant.

Se Chairman and Vice Chairman and other morters shall be appointed by the hecutive Vice President - Power Supply or such other l

person as he shall designate. Se composition of the 3RR shall meet the requirements of AME! N18.7-1976.

A L*T M a m i 4.5.2.3 All alternate representatives shall be appointed 'in writing by the absent meeer to serve on a tenporary basist however, no more than two alternates shall participate in SRs activities at any one time and alternate representatives shall not have voting privileges.

W 6.5.2.4 consultants shall be utilized as determined by the SRB Chairman or

. Vice-Chainaan to provide empert advice to the 3Rs.

M22'DC PMOUDCY 6.5.2.5 ne SRs shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per l

six months thereaf ter.

RN!CH = LNIT 1 0*I Amndment No. #J.100

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AINNISMmT CC*mer e 6.5.2.8 Audits of unit activities shan be performed under the' cognizance of the SRB. Each inspection or audit shan be perfonned within the specified time interval with:

1.

A maxima allodle extension not to exceed 25% of the inspection or audit interval.

2.

A total maxima contined interval time for any 3 consecutive inspection or audit intervals not to exceed 3.25 times the specified inspection or audit interval.

D ese audits shall enccmpass:

a.

Se conformance of unit operation to provisions contained within the hchnical specifications and applicable license conditions at least once per 12 months, b.

The performarce, trainino and qualifications of the entire unit l

staff at least once per 12 months.

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

unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d.

We performance of activities requirc.d by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 Q150, at least once per 24 months.

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

12 months shall be perfossied by individuals who have no direct responsibility for implementation of this plan.

f.

We security Plan and implementing procedures at least once per 12 months shan 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 sPs l

or the Executive Vice President Power Supply.

I h.

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

1.

An independent fire protection and loss prevention inspection and audit shan be performed annually utilizing either gaalified offsite licensee personnel or an outside fire protection firm.

j.

An inspection and audit of the fire protection and less prevention program shan 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 6.5.2.81 can be affected concurrently.

EArot - tNIT 1 Nll l

Mendnent No p, pf, pp.109 s

AININISTRATIVE CONTROLS Mmiolt1TY 6.5.2.9 The SRB shall report to and advise the Execut'ive Vice President -

Power Supply on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

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

a.

Minutes of each SRB seeting shall be prepared, approved and fowarded to the Executive Vice President-Power Sgply within 14 I

days following each useting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be

preparud, approved and forwarded to the Executive Vice l

President-Power Supply within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President-Power Sgply and to the i

annagement positions susponsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCC2HUtENCE ACTION 6.6.1 The in11owing actions shall be taken for REPORTABLE OCCUlUtENCES.

a.

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

b.

Each REPORIABLE OCCINLRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission shall be reviewed by the PitB and submitted to the SRB 4

and the Manager of Nuclear Generation or the Vice President and l

.l General Manager Nuclear Operations.

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

a.

The smit shall be placed in at least HOT SRTTDolW within two hours.

b.

The safety Limit violation shall be reported to the Commission, the Manager Nuclear Generation or the Vice President and General Manager Nuclear Operations and to the SRB within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

HATOf - UNIT 1 6-12 Anendment No. #5,109

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AININISTRATIVE CONTRMA SAFETY 1.1MIT VIG.ATION (Continued) c.

A Safety Limit Violation Report shall be prepared.

The report I

shall be reviewed by the PRB.

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

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the violation won facility components, systems or structures, and j

(3) corrective action taken to pavent recurrence.

i d.

h Safety Limit Violation Report shall be submitted to the Commission, the SRB and the Manager of Nuclear Generation or the a

Vice President and General Manager Nuclear Operations within 14 3

days of the violation.

6.8 PROGIMtES 6.4.1 Written pmcodures shall be established, implemented and maintained coverig the activities referenced below:

1' 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 mlated equipment.

c.

I d.

Security Plan implementation.

i h ersency Plan implementation.

e.

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Fire Protection Program implementation.

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6.8.2 Each. procedure of 6.8.1, and other procedures drich the General J

Manager - Plant Hatch has determined to affect nuclear safety, and chanses j

thereto, shall be reviewed by the FRB and approved by the appropriate member of plant management, designated by the General Manager - Plant Match, prior to implementation.

The General Manager Plant Hatch will approve administrative procedures, security plan implementing procedures, emergency 1

plan implementing procedures and changes thereto. All other procedures of this specification and chages thereto will be approved by the department head designated by the General Manager - Plant Match.

i h procedures of i

this specification shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above any be made provided-a.

h intent of the original procedure is not altered.

I b.

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

License on the unit affected.

c.

The change is doctamented, mytowed by the PRE and approved in writing by the General Manager - Plant Match, or his designee as l

t assigned by 6.8.2, within 14 days of implementation.

HATO( - UNIT 1 6-13 Amenhent No. 5),109 l

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to enter such areas shall be provided with or accompanied by one er more of I

the following.

A radiation monitoring device which continuously indicates the a.

radiation dose rate in the area.

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.

c.

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over.

the activities within the area and shall perfom periodic radiation 4

surveillance at the frequency specified by the facility Health l

Physics supervision in the Radiation Work Permit.

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6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 aren/hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Laboratory Foreman on duty.

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6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT 4

i The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain hiohly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:

t 1)

Provisions establishing preventive maintenance and periodic visual inspection requirements, and j

2) system leakage test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequency not to exceed refueling cycle intervals. The systems subject to this testing are (1) Residual Heat Removal (2) Core Spray, (3) Reactor Water Cleanup, (4)HpC1,and(5)RCIC.

j 6.14 100!NE MONITORING The licensee shall implement a program which will ensure the capability to 1

i accurately detemine the airborne iodine concentration in vital areas

under i

accident conditions. This program shall include the following:

1 Training of personnel, i

2 Procedures for monitoring, and l

3 Provisions for maintenance of sampling and analysis equipment.

j

Areas requiring personnel access for establishing hot shutdown condition.

HATCH-dMIT1 6-21 Amendment No. 85,79,100 l

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f 5.0 Administrative Controls i

This section describes administrative and management controls established to implement the las' Environmental Technical specifications (ETS).

1 Measures specified in this section include assigrunents of responsibility, l

review and audit functions, procedures, and reporting requirements.

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j Corporate responsibility for implementation of the EIS and for assuring l

that the station is operated in auch a way as to provide protection for i

the environment rests with the Executive Vice President - Power supply.

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Mesponsibilities for ocupliance with the Ers and for the environmental

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nonitorirg program required by the E25 are given,below.

Independent audit shall be provided for all matters, as diarmead in i

section 5.3.2, by the General Manager of Quality Assurance and Radiological Bealth and safety.

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5.1 mesponsibility 5.1.1 The General Manager. Plant Batch is responsible for monitoring

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plant affluents; for operating the plant within the Limiting 4

Conditions for operation (140s) specified in section 2r and for the co11= +9= and measurements associated with all radiological i

aseples described in section 3.2, except for class, American shed, shoreline sediment, and the annual _ surveys.

These j

exceptions are the responsibility of the Manager of i

Environmental Affairs. The General Manager-Plant Match also is l

t responsible for implementing the special surveillance activities described in sections 4.2 and 4.3.

5.1.2 The Manager of Environmental Affairs is responsible for the i

i environmental monitoring programs specified in sections 3 and 4, t

i except as noted in sections 5.1.1 and 5.1.3 He also is responsible for section 4.1 and for those aspects of section 3.2 j

that are not assigned either (i) to the General Manager-Plant Estch by section 5.1.1 or (ii) to the Manager-maclear Engineering and Chief p elear Engineer by section 5.

The Manager of Envirormental Affairs is responsible for coordinating these programs with appropriate groups.

i 5.1.3 The Manager-pelaar Engineering and Chief Melaar Engineer is l

t responsible for the interpretation, evaluation, and routine i

reporting of the results of the radiological environmental I

t monitoring program described in section 3.2.

1 5.1.4 the General senager of Quality Assurance and undiological Health j

and safety is responsible for conducting periodic audits of p

plant operations and the envirormental sonitoring activities to i

ensure conformance with the Ers.

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5.2 organization f

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A chart showing coupeny organization relative to environmental matters is, presented in Figure 5.2-1.

Changes affecting company organization depicted in Figure 5.2-1 will not require 1st approval prior to j

' implementation, but such changes shall be reported tn Isc within 30 days in accordance with section 5.7.2 i

bl hnendment No. 109 l

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5.3 noview and Audit

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5.3.1 Independent Moview l

I 5.3.1.1 The General Manager-Plant Match is responsible for i

routine review of plant operations to ensure that NW is operated in compliawe with the ICOs specified in Section 2.

5.3.1.2 The Manager of Envirorumental Affairs shall review the following:

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a. The conduct of the envirorumental sonitoring programs, j

on a routine basis, to ensure that the specifications in sections 3 and 4 are being implemented.

b. Proposed changes to plant systems or equipment, provided such changes are identified by the Plant moview Board as having a

potential adverse envirorumental aspect.

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c. Procedures for implementing the reopensibilities i

specified in section 5.1.2, and proposed changes 4

thereto.

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d. LW changec to the 225.

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e. Proposed changes to the Environmental Programs Description Document.

j 5.3.1.3 The safety moview Board (SRS) ahall review the following:

a. Proposed & anges to the ET5.

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b. Results of the envirerseental monitoring programs prior to their sutuaittal in each Annual Envirornental surveillance Report.

c. Violations of Ers to determine whether adequate j

corrective action is being taken to prevent j

recurrence.

d. Procedures or changes hereto,' which could affect the monitoring of station operation, that maf be i

i considered by the Manager oi Environmental Affairsi the Managerh Engineering and Chief Muclear l

1 Engineer, or the Plant Review Board to be appropriate l

for SRB review.

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- 5.3.1.4 The Plant Review Board (PR3) shall review the following:

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a. Proposed changes to ple'nt systems or equipment.

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b.

Procedures for implementing the responsibilities specified in Section 5.1.1, and proposed changes _thereto.

c.

Proposed changes to the ETS.

d.

Unplanned releases of a radioactive, material [ rom the site.

5.3.1.5 The knager-Nuclear Engineering and Oti,ef Nuclear l

Ergineer shall review the following:

Proposed changes to plant systems or equipment, provided a.

that such changes are identified by the PRB as having a potential radiological environmental impact.

b.

Proposed charges to Section 3.2 of the ET5.

5.3.2 Audit Responsibility 5.3.2.1 The General Manager of Quality Assurance and Radiological Health and Safety is responsible for an audit, conducted at least once a year, of the activities of the General i

Manager-Plant

Etch, the Manager of Envirormental

.i Affairs, and the Manager-Nuclear Ergineering and Chief Nuclear Ergineer related to camp 11ance with the ET3.

fl 5.3.2.2 Audits of facility activities shall be perfomed at least

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once a year under the cognizance of the SRB to ensure conformance of facility operation to all ' provisions of the ETS.

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5.4 Action to be taken if a Limitina Condition for Operation is Exceeded 5.4.1 3

Remedial action, as permitted by the ET5, shall be taken until the LC0 can be achieved.

J 5.4.2 Violations of an 140 will be reported immediately to the General knager-Plant Etch.

5.4.3 A separate report of each 140 violation shall be prepared by the General knager-Plant Hatch. Copies of such reports will be submitted to the Vice President and General Manager Nuclear Operations, the Manager Nuclear Generation, the Manager of Invirormental Affairs, the Manager-Nuclear Ergineering and i

Qilef Nuclear Ercineer, and the Chairman of the SRB for review and approval of corrective actions, as specified in Section 5.3.1.3c.

5.4.4 The General Manager-Plant Hatch shall report such violations l

to the letC in accordarme with Section 5.7.2.

t 5.5 State and Federal Permit Certifications 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 5-3 Amendment ?;o.109

. _ _ ~. _

t 4

provisions of Sections 301, 302, 306, and 307 of the FWPCh. Section 401 of PL 92-500 further requires that any certification provided under this section shall set forth any effluent limitations and other limitations and 4

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

Accordingly, the licensee shall-ccuply with the requirements j

set forth in the currently applicable 401 certification and amendments l I

thereto issued to the licensee by the Georgia Environmental Protection -

Division.

In accordance with the provisions of the Georgia Water Quality Control act, the BWCh and the rules and regulations peceulgated pursuant to each of these acts, the Georgia Enviromental Protection Division, j

under authority delegated by the U. S. IPA, issued IWDIs Pennit No. GA 0004120 to the licensee.

De IWDEs posit authorises the licensee to i

discharge frcui Ine Units 1 and 2 to the Altamaha River in accordance with effluent limitations, monitoring recpirements, and other conditions i

stipulated in the

peceit, effective August 1,

1983,~ through j

December 5, 1987 sutsequent revisions to the. certifications will be = = - ~hted in j

accordance wit.h the provisions of section 5.7.3.

1 5.6 Procedures Detailed written procedures, including applicable check lists and instructions, shall be prepared and followed for all activities involved i

in implementing the ETS. Procedures shall apply to sampling, data 4

recording and storage instrument calibration, measurement and data

(

recording and storage, instrument calibration, measurement and analysis.

and actions to be taken when limits are approached or exceeded. Testing j

frecuency of any alarm shall be included. These frequencies shall be determined from experience with similar instruments in similar environments and from manufacturers' technical manuals.

Plant operating procedures may be referenced in the above procedures in

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areas pertaining to maintenance and calibration of instrumentation end in other such areas of interface with the above procedures.

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f All procedures shall N maintained in a menner convenient for review and

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inspection.

Procedures dich are the responsibility of the General l

i Manager-Plant MatcS shall be kept at the plant. Procedures dich are the I

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responsibility of the Manager of Envirormental Affairs and the

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Manager-leaclear Engineering and Chief indaar Engineer shall be kept at l

l the GPC General office.

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j 5.6.1 Enviromental Programs Description naa-nt 1

Bened on these procedures, the licensee shall prepare and follow i

an enviromental progra description deciment (EPDD) describing i

the monitoring programs that are required by sections 3.1 and t

4.1.

Ris docuent shall include descriptions of sampling 1

equipment lacetions, frequencies and rumber of replications, l

aseple analyses, data recording and storage, and instrument 2

calibrations where appropriate, t

5-4 Amendment No. 109 i

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These program descriptions shall be approved by the isC, and subsequent ardifications to these progenes shall be made by the i

licensee in accordance with sections 5.6.4 and 5.6.5._

s f.6.2

-Quality Assurance of Program Results t

Procedures shall be eseblished to assure the quality of ETS program 4

results, including analytical measurements.

These pere =^wes shall doctament the program in policy directives, desip ate responsible organizations or individuals, describe purchased services (e.g.,

l contractural laboratory or other contract services), and provide for i

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audits of results and procedures by licensee personnel. In addition, l

these quality assurance procedures shall provide for systees to identify and correct deficiencies in technical monitoring programs or 3

related shinistrative activities, to investigate ancmalous or suspect results, and to review and evaluate program results.

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5.6.3 Compliance with Procedures f

In addition to the procedures specified in section 5.6, the station

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operating procedures shall include provisions to ensure that and Unit and all its systems and components are operated in compliance with the i

conditions established in the ETE.

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3 5.6.4 Changes in Procedures, EPDD, and Station Desis or W ation i

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Changes in the procedures, IPDD, and station design or operation any l

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be made in accordance with Section 5.3 and suject to the conditions i

described below:

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l a.

The licensee may (i) make changes in the stations design and

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operations (ii) make changes in the EPDD developed in accordance j

j with section 5.6.1r and (iii) conduct tests and experiments not 1

described in the EPDD without prior IOC w..d,

t.r. lass the

j proposed change, test, or experiment involves either a change in the objectives of the ETE, an unreviewed environmental question of j

substantive ispect, or affects the requirements of section 5.6.5.

b.

A proposed change, test, or experiment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter I

j which may result in a sipificant increase in any adverse l

envirotunantal impact previously evaluated in the final enviraramental statement, as modified by staff's testimony at the j

hearing, supplements thereto, envirorunental ispect appraisals, or in initial or final adjudia=*~y decisions or (ii) a significant i

l change in effluents or power levels or (iii) a matter not previously reviewed and evaluated in the documents specified in 1

(i) of this paragraph whid may have a significent adverse f

environmental impact.

1 i

1 5-5 Amendnent No. 109 l

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c. The licensee shall maintain records of changes to EPDD and to

- t facility design or operation made pursuant _to this section.

The 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 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 ris, or does not l

affect the requirements of Section 5.6.5.

1he licensee shall furnish to the lec, annually or at such shorter intervals as may be specified in the license, a report.containing descriptions, analyses, interpretations, and evaluations of j

such changes, tests, and experiments.

d. Changes in the EPDD which affect sampling fregNncy, location, 14 gear, or rT

-fe=t shall be reported to the IEC within 30 days after their implementation, unless otherwise reported in l

i accordance 'rith Section 5.7.3.

Changes which affect sempling technique or data recording and storage shall be reported to the ist at the end of the year. These reports stall provide a i

description of the changes made, the reasons for making the changes, and an evaluation of the enviremental ispect of these changes,

e. Proposed changes or modifications to plant systems or

, equipment shall be reviewed in accordance with section 5.3.

l

f. Proposed changes to procedures for implementing the responsibilities specified in Section 5.1.1 shall be reviewed and approved by the PRS. Tagorary changes to the procedures j

that do not change the intent of the original pere = Awe may be made with the concurrence of two individuals holding - senior i

reactor operator licenses. Such changes shall be daa==nted and subsequently reviewed by the pas and approved by the General Manager-Plant Match en a timely basis..

I

g. Proposed changes to procedures for implementing the responsibilities specified in Section 5.1.2 shall be reviewed i

by the staff of Envirorumental Affairs. Such proposed changes j

shall =*==y="itly be reviewed and approved by the Manager of i

Enviroeveental Affairs.

Proposed changes to procedures for 47-- -.i.ing the responsibilities specified in Section 5.1.3 1

shall be reviewed by the staff of the Manager-Nuclear l

Engineering and Chief teaclear Engineer. Such proposed changes shall

= *==y =gtly be-reviewed and approved b

the Manager-laaclear Engineering and Chief Itaclear Engineer.y When deemed appropriate by the Manager of Enviremental Affairs or the Manager 4aaclear Engineering and chief Isuelear Engineer, sudt proposed changes also shall be reviewed by the SRB prior to irl--

etion.

5-6 Amendment No.109 l

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i (iii) an unusual or important event occurs, as specified in 1

Section 4.2.

Reports shall be submitted under _ane of the report schedules described below:

i a.

Prompt Report - those events requiring prompt reports j

shall os reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by i

telephone, telegraph, or facsimile transmission, and

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followed within 10 days by a written report.

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b.

Shirty Day Report - pontoutine events not requiring a i

pecept report, as described in section 5.7.2a, shall be i

i reported to lac either -(i)' within 30 days of their l

occurrencer or (ii) within the time limit designated in i

the appropriate specification; or (iii) within the time limit specified by the reporting requirement of the corresponding certification or permit issued pursuant to l

Section 401 or 402 of PL 92-500. The report submitted to IWC in accordance with (iii) of this paragraph will i

i consist of a copy of the report made to the Georgia Department of untural Resources, Envirorsnental j

Protection Division.

1 Written., reports and, to the extent possible, preliminary telephone, telegraph or facsimilie reports shall (i) describe, analyse, and evaluate the occurrence, including the extent and magnitude of the is (ii) describe the cause of the coeurrencer and (iii) pectsindicate corrective action (including any siytificant changes made in procedures) -taken to preclude recurrence and to prevent s'=Har occurrences involving similar i

components or systems, t

5.7.3 Changes in Envirorumental suchnical specifications and Permits i

5.7.3.1 Cha.,.e in mvirorsmental Mchnical Specifications 1

ascpaast for changes in EIS shall be submitted to the 1st i

for review and authorisation in accordance with 10 CFR 50.90. The request shall include an evaluation of the envirorsmental impact of the proposed change and a j

supporting justification.

Implementation of such 1

requested changes in EIS shall not commence prior to d

i.-y ation by the IEC of the new specifications in the license.

Proposed changes to the ETS shall be reviewed and approved by the Manager of Environmental Affairs, the pas and the sie. Proposed changes to Section 3.2 also l

will be reviewed _ and approved by the Manager-Itaclear Engineering and Chief Itaclear Engineer.

Prior to oval, the possible impact of the proposed changes b9 evaluated. 10 avoid conflicts and to maintain consistency between the safety and environmental aspects of plant operation, proposed changes to section 2 will he reviewed in the same menner as proposed changes to i

the safety suchnical Specifinstions.

1 i

F9 Amendnent No.109 i

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VICE PRESIDBfr IOWBt StPPLY

-.sJtL B5HWlutst quALIII AssuRAnt.a 5Artly REVIEW Alm RAD 10tEGICAL HEALTH 4 SAFETY BOMtD (SRB)

VIG rurhiper I asminttRING MN AM CONSTRUCTION SERVICES NUCLEAR 70WBt I '

VIG rur >sutNI AND VIG FRP3tpsRI AND WIEr GWBtAL MkN4GBt ENGINEBt POWBt SUPPLY

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NUCLEAR OPERATIONS ENGINEStING AND SERVICES BWUmuta nuumut psusts.esi muu.FJUL ENGilEilRING Als GIIF OEMISIRY AND a DENAGBt OF NUCtJiAR BIGIIE!IR INi4L1H FHYSICS NUCLEAft GBfBtATION E

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R a 05tRWTLY M OllGANIZATION STRICItNtE REIATED j

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NUCLEAR REGULATORY COMMISSION m ane=oron,o.c. mess i

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GEORGIA POWER COMPANY 1

OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-366 EDWIN !. NATCH NUCLEAR PLANT UNIT N0. 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 47 License No. NPF-5 1.

The Nuclear Regulatory Consiission (the Cosmiission) has found that:

A.

The applications for amendment by Georgia Power Company, et al.,

(the licensee) dated July 9, 1962, October 24 and December 20, 1983, and April 24, 1984, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Cosetission's rules and regulations set forth in 10 CFR Chapter I; 3.

The facility will operate in conformity with the appitcation, the provisions of the Act, and the rules and regulations of the Connission;-

C.

There is reasonable assurance (1) that the activities authorised by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Cosatission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. 4PF-5 is hereby amended to read as follows:

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l 2-L Technical Specifications

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The Technical Specifications contained in Appendices l

A and B, as revised through Amendment No. 47, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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3.

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

FOR THE NUCLEAR R GULATORY COPetISSION f

Jo n F. Stofz, Chi rating Reactors anch #4 Jivision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 27,1985 I

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ATTACHMENT TO LICENSE AMENDMENT HO. 47 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

Remove Insert 6-1 6-1 6-la 6-la 6-2 6-2 6-3 6-3 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-10 6-10 6-11 6-11 6-12 6-12 6-19 6-19 Replace the following pages of the Appendix "B" Environmental Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

Remove Insert 5-1 5-1 5-2 5-2 5-3 5-3 5-4 5-4 5-5 5-5 5-6 5-6 l

5-9 5-9 5-11 5-11

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6.0 AININIS"mA"'IVE CCNNIS 6.1 RESPONSIBILITY 6.1.1 2e General Manager-Plant, Hatch shall be responsible for overall unit l

operation and shall-delegate in writing the succession to this responsibility during his absence.

6.2 OR:ANI*ATION GTSTIE 6.2.1 Se offsite organization for unit management and technical support shall be as shown on Figure 6.2.1-1.

UNIT STAFF 6.2.2 @ e. unit organization shall be as shown on Figure 6.2.2-1 and a.

Each on duty shift shall be caposed of at least the minimum shift crew ccuposition shown in Table 6.2.2-1.

b.

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

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

d.

An individual qualified to implement radiation protection procedures shall be on site den fuel is in either reactor, e.

All CDRE AL"DATIOt6 shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Bandling who has no other concurrent responsibilities during this operation.

f.

A Fire Team of at least five marrbers shall be maintained onsite at all times. Se Fire 'mam shall not include the mininzn shift crew l

necessary for safe shutdown of Units 1 and 2 or any personnel required for other essential functions during a fire emergency.

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19201 UNIT 2 6-1 Amendment No. 47 I

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g.

Administrative procedures shan be developed and implimiented to 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 shan be maintained without routine heavy use 4

of overtime. 'me objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while.the plant is operating.

Howver, in the event that unforeseen problems require substantial amounts of overtime to be used or during extended periods of shutdown for refueling, major maintenarce, or major plant modifications, the fonowing guidelines shall be fonowed on a tegorary basis (1) An individual should not be permitted to work note 'than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, ="-1 Ming shift turnover time.

(2) An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period, an excluding shift turnover time.

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

(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 General Manager-Plant Hatch,or his deputy of higher levels of l

managenent, in accordance with established procedures and with doctanentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime shan be reviewed monthly by the General Manager-Plant Hatch or his l

desiytee to assure that excessive hours have not been assigned.

Routine deviation frcun the above guidelines is not authorized.

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AIMMIS'IPAmT CtWNWA 6.3 INIT SIAIT CUALIFICATICNS -

6.3.1 Each member of the unit staff shall meet or e N the minimum qualifications of ANSI N18.1-1971 for conparable positions except for the Health Ehysics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, Septseber 1975, and the Shift 'Mchnical Advisor who shan have a bachelor's degree or equivalent 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 TRAINDC 6.4.1 A retraining and replacement training program for the unit staff shan be maintained under the direction of the Manager of Training and sha n meet or l.

exceed the requirements and reer====ndations 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 NEPA Code-1975, except for fire protection training sessions which shall be held at least once per 92 days.

6.5 REmW AND AtEIT 6.5.1 FINC REVIIW BOARD (PPE FUCTICN 6.5.1.1 The PRB shan function to advise the General Manager-Plant Hatch on all matters related to nuclear safety.

CINFOSITICN 6.5.1.2 The Plant Review Board shall be 2----:=-1 of the:

Chairnan*:

General Manager-Plant Hatch Menber:

Deputy General Manager Mar.t>er:

Superintendent of Operations Manber Superintendent of Maintenance Marber:

Nealth Physics Superintendent i

Menber:

Superintendent of Quality Control Member:

Superintendent of Plant Engineering Services Member Superintendent of Regulatory Conpliance Manoer (non-voting):

Representative of site Quality Assurance Meneral Manager-Plant Hatch to designate chairman from voting PRB l

menbership as necessary.

ALTERNRr!S 6.5.1.3 An alternate

===*=rs shall be appointed in writing by the PRB C2sairman to serve on a tenporary basist however, no more than two alternates sha n participate as voting members in PRB activities at any one time.

j EMOI - 11 NIT 2 6-5 Amendment No. 4, 47

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6. 5.1. 4 The PR3 shall meet at least once per calendar month and as convened by the PRB Chaiman or his designated altemate.

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6. 5.1. 5 The minimun quorum of the PRB necessary for the performance of the i

PRB responsibility and authority provisions of these Technical Specifications shall consist of the Qiairman or designated Chairman and four l

voting members including alternater.

RESPONSIBILITIES

~ 6. 5.1. 6 The Plant Review Board shall be responsible for:

Review of (1) all p)rocedures required by Specification 6.8 and s.

i charges thereto, (2 any other proposed procedures or changes thereto as determined by the General Manager-Plant Hatch to affect 1

4 I

nuclear safety.

b.

Review ot' all proposed tests and experiments that affect nuclear safety.

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c.

Review of all proposed charges to Appendix "A"

Technical j

Specifications.

d.

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

J Inve'stigation of all violations of the Technical Specifications e.

including the preparation and forwarding of reports covering evaluation and recouaiendations to prevent recurrence to the Manager of Nuclear Generation or the Vice President and General Manager l

Nuclear Operations and to the Safety Review Board (SRB).

I f.

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

3 Review of unit operations to detect potential nuclear safety hazards.

f h.

Perforu mce of special review investigations or analyses and reports thereon as repested by the General Manager-Plant Hatch or i

the SRB.

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HATO(-UNIT 2 6-6 Amendment No. 47 i

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AININISmATIVE COUR0Ui i

RESPONSIBILITIES (Continued) i 1.

Review of the Security Plan and implementing procedures and shall submit recomended cheeses to the SRB, I

j.

Review of the Baergency Plan and implementi'ng procedures and shall submit recomended charges to the SRB.

AlmRNLITY

6. 5.1. 7 The PRB shall:

Recommend in writire to the General Manager-Plant Hatch approval l

4 a.

l or disap' roval of items considered under 6.5.1.6(a) through (d) p abw.

i b.

Render determinations in writing with regard to whether or not each ites considered under 6.5 1.6(a) through (e) above constitutes an ureviewed safaty question.

1 c.

Provide written notification with 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Manager of Nuclear Generation or the Vice President and General Manager i

Nuclear Operations and the Safety Review Board of disagreement between the PRB and the General Manager-Plant Hatch; however, the General Manager-Plant Hatch shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

e j

RBCDRDS i

L

6. 5.1. 3 The Plant Review Board shall maintain written minutes of each PRB l

l meeting that, at a minis m, docuent the results of all PRB activities performed under the responsibility and authority provisions of these Technical Specifications. Copies shall be provided to the Manager of Nuclear Generation j

or the Vice President and General Manager Nuclear Operations and the Safety Review Board.

a 6.5.2 SAPETY REVIBf 30MtD (stb) 4 PUNCTION 6.5.2.1 The SRB shall function to designated activities in the areas of: provide independent ruview and audit of l

j a.

Nuclear power plant operations, b.

Nuclear engineerire, c.

Quesistry and radiochemistry.

IRTQi - IMIT 2 6-7 Amendment No. 47 i

l xtsmsmmr mnwu fincTION tcontinued) d.

Metallurgy, e.

Instruentation and control, f.

Radiological safety, g.

Mechanical and electrical engineering, h.

Quality assurance practices.

CINPOSITION 6.5.2.2 De SRB shall be conposed of a minisun of seven persons who as a grow provide the expertise to review and audit the operation of a nuclear power plant.

We Chairman and Vice Chairman and other members shall be appointed by the Executive Vice President - Power Supply or such other l

person as he shall designate. The conposition of the SRB shall meet the requirements of ANSI N18.7-1976.

AINNAITS 6.5.2.3 All alternate representatives shall be appointed in writing by the absent member to serve on a tenporary basis; however, no more than two alternates shall participate in SRB attivities at any one time and alternate representatives shall not have voting privileys.

CDEUI3NTS 6.5.2.4 Consultants shall be utilized as determined by the SRB Chairman or Vice-Oainnan to provide expert advice to the SRB.

MTI'DG P1ECENCY 6.5.2.5 Se SRB shall meet at least once per calendar efuarter during the initial year of unit operation following fuel loading a t at least once per six months thereafter.

I MPact - UNIT 2 6-8 Amendment No. 47 i

1

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i Amens'Am? cces ALTr:S

~ 6.5.2.8 Audits of unit activities shall be performed under the' cognizance of the SRB. Each inspection or audit shan be performed within the specified time interval with:

1.

A max 2 mum allowable extension not to exceed 25% of the in.pection or atx!it interval.

2.

A total maximian contined interval time for any 3 consecutive inspection or audit intervals not to exceed 3.25 times the specified inspection or audit interval.

m ese audits sha n encanpass:

The conformance of unit operation to provisions contained within a.

the Technical specifications and applicable license conditions at least once per 12 months.

b.

The performance, training and qualifications of the entire unit l

staff at least once per 12 months.

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

unit equipnent, structures, systems or method of operatien that i

affect nuclear safety at least once per 6 months.

d.

De performance of activities required by the operational Quality Assurance Program to meet the criteria of Appendix *B",10 CTR 50, at least once per 24 months, Tne Emergency Plan and inplementing procedures at least once per e.

12 senths shan be performed by individuals who have no direct responsibility for inplementation of this plan, f.

The Security Plan and implementing procedures at least once per 12 months sha n be perfor: red by individuals who have no direct

+

responsibility for inglementazion of this plan.

g.

Any other area of unit operation considered appropriate by the SP3 or the Executive Vice President Power Supply, l

i h.

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

i.

An irdependent fire protectio;. ard loss prevention inspection and audit shan be performed annuan y utilizing either gaalified offsite licensee personnel or an outside fire protection firm.

j.

An inspection and audit of tha fire protection and loss prevention program shan be performed ty 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 6.5.2.81 can be affected concurrently.

HATCH - UNIT 2 6-10 Amendment No. 22, Q, 47 1

a __._._

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l l

l-ADENISTRATIVE CONTROLS ALTmDRITY 6.5.2.9 The SRB shall report to and advise the Executive Vice President -

Power Swply on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

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

s.

Minutes of each SRB meeting shall be prepand, approved and fowarded to the Executive. Vice President-Power Supply within 14 l

days followirg each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be

prepared, approved and forwarded to the Executive Vice l

President-Power Supply within 14 days following completion of the review.

c.

Audit reports encespassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President-Power Supply and to the l

management positiera responsible for the areas audited within 30 days after ccumpletion of the audit.

6.6 REP 0kTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCQJRRENCES.

a.

The Commission shall be notifled and/or a report submitted pursuant to the requirements of Specification 6.9 i

b.

Each REPORTABLE OCQRRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Consission shall be reviewed by the PRB and submitted to the SRB l

and the Manager of Nuclear Generation or the Vice President and l

General Manager Nucler.r Operations.

)

6.7 SAFETY LDGT VIG.ATION l

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

s.

The unit shall be placed in at least HCTr SRTTDOIN within two hours.

b.

The Safety Limit violation shall be reported to the Comission, the Manager Nuclear Generation or the Vice President and General Manager Nuclear Operations and to the SRB within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

HATOi - INIT 2 6-11 Amendment No. 47

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4 AININISTRATIVE Carmt0LS SAFETY LDtIT VIMATION (Continued)

~*

c.

A Safety Limit Violation Report shall be prepared.

The report I

shall be reviewed by the PRB.

This report shall describe (1) applicable ciremstances preceding the violation, (2) effects of the violation gon facility components, systems or structures, and (3) corrective action taken to prevent acurrence.

l d.

h Safety Limit Violation Report shall be submitted to the Consission, the SRB and the Manager of Nuclear Generation or the l

Vice President and General Manager Nuclear Operations within 14 I

days of the violation.

6.8 Mto G DURES 6.8.1 Written procedures shall be established, implemented and maintained coverirg the activities referenced below:

j a.

The applicable procedures acommended in Appendix "A" of Regulatory i

Guide 133, Revision 2, February 1978.

J 6

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

1 j

d.

Security Plan implementation.

e.

Baergency Plan implementation.

4 f.

Fire Protection Program implementation.

6.8.2 Each procedure of 6.8.1, and other procedures which the General Manager - Plant Hatch has determined to affect nuclear safety, and changes j

thereto, shall be reviewed by the PRB and approved by the appropriate assber l

of plant management, designated by the General Manager - Plant Hatch, prior J}

to implementation.

The General Manager Plant Hatch will approve t

administrative procedures, security plan implementing _l other procedures o procedures, emergency plan implementing procedures and changes thereto. Al this specification and changes thereto will be approved by the departnesit i

head designated by the General Manager - Plant Hatch. The procedures of this specification shall be nyiewed periodically as set forth in d

akinistrative procedures.

i 1

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

j a.

h intent of the original procedure is not altered.

b.

The change is approved by two sembers of the plant annagement staff, at least one of whom holds a Senior Reactor Operator's License on the mit affected.

c.

h change is docuented, reviewed by the PRB and approved in i

writing by the General Manager - Plant Hatch, or his designee as assigned by 6.8.2, within 14 days of implementation.

HATO! - IMIT 2 6-12 Anendment No. 47 j

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ADMINISTRATIVE CONTR01.

to enter such areas shall be provided with or accompanied by one or more of the following.

A radiation monitoring device which continuously indicates the a.

i radiation dose rate in the area.

b.

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

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, An individual qualified in radiation protection procedures who is c.

equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health l

Physics supervision in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.

In additien, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative centrol of the Shift Supervisor on duty and/or the Laboratory Foreman on outy.

l l

6.13 INTEGRITY OF SYSTEMS OtJTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from syster.s outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall incluc'e the following:

1)

Provisio'ns establishing preventive maintenance and periodic visual inspection requirements, and 2)

System leakage test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequency not to exceed refueling cycle intervals. The systems subject to this testing are (1) Residual Heat Removal, (2) Core Spray, (3) Reactor Water Cleanup.

(4)HPCI,and(5)RCIC.

i l

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i NATCH - UNIT 2 6-19 Amendment No, M e 47 I

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- - a.s 5.0 Administrative Controls J

nis section describes administrative and management controls established l

to lapiment the HNP Errriromental Mchnical specifiqations (ETS).

i Measures specified 'in this section include assignments of responsibility, i

j review and audit functions, procedures, and reporting requirements.

l l

Corporate responsibility for implementation of the m and for assuring j

that the station is operated in sue a way as to provide protection for the erwironment rests with the Docutive Vice President - Poner Supply.

l l

1 J

nesponsibilities for ccupliance with the ETS and for the envirorunental monitorirg program required by the m are given. below, i

Independent audit shall be provided for all matters, as discussed in 3

section 5.3.2, by the General Manager of Quality Assurance and g

j Radiological Health and safety.

5.1 neaponsibility l

5.1.1 Se General Manager-Plant Bats is responsible for monitoring l

1 plant effluents: for operating the plant within the 1.imiting

)

Conditions for operation (tIDs) specified in section 23 and for l

the collection and measurements associated with all radiological samples des ribed in section 3.2, except for clans, American i

shad, shoreline sediment, and the annual surveys.

These l

emoptions are tne responsibility of the Manager of i

mvironmental Affairs. De General Manager-Plant Hatch also is l

]

responsible for amplementing the special surveillance activities-j described in sections 4.2 and 4.3.

i 1

J 5.1.2 me Manager of Enviromental Affairs is responsible for the enviromental monitoring programs specified in sections 3 and 4, emept as noted in sections 5.1.1 and 5.1.3 Me also is responsible for section 4.1 and for those aspects of Section 3.2 1

that are not assigned either (1) to the General Manager-Plant Match by section 5.1.1 - or (ii) to tne Manager-Nuclear i

mgineering and Chief Muclear Engineer by section 5.

The j

Manager of Enviremental Affairs is responsible for coordinating j

these programs with appropriate groups.

)

j 5.1.3 The Manager-Nuclear Engineering and Chief Nuclear agineer is l

i responsible for the interpretation, evaluation, and routine

}

reporting of the resulta of the radiological environmental l

monitoring progran described in section 3.2.

j i

5.1.4 Se General Manager of Quality Assurance and Radiological Health and safety is responsible for conducting periodic. audits of e

plant operations and the enviromental sanitoring activities to s

J ensure conformance with the E25.

i 5.2 Creanisation j

1 A dart showieg eenyony organisation relative to enviromental mstters is

[

l presented in Figure 5.2-1.

Changes affecting ocupany organisation depicted in Figure 5.2-1 will not require let approval prior to 1

i Auplementation, but mad danges shall be reported to set within 30 days in accordarme with section 5.7.2 t

t F1 Amendnent No. 47 I

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e 5.3 Review and Audit 5.3.1 Indeoendent Review

=

5.3.1.1 Se General Manager-Plant Nats is responsible for I

routine review of plant operations to ensure that BNP is operated in coupliance with the Icos specified in s

Section 2.

5.3.1.2 he Manager of Envirorsnental Affairs shall review the a

following:

a. Se conduct of the envirorsnental monitoring programs, on a routine basis, to ensure that the specifications in sections 3 and 4 are being implemented.

b. Proposed changes to plant systesE or equipnent, 1

provided sud changes are identified by the Plant moview Board as having a

potential adverse environmental ispect.

c. Procedures for implementing the responsibilities specified in section 5.1.2, and proposed changes thereto.

d. Proposed d anges to the EIS.

e. Proposed danges to the Envirorsnental Programs 4

Description Document.

.j 5.3.1.3 We Safety moview Board (SRB) shall review the following:

1

a. Proposed danges to the ETS.

b. Results of the envirorsnental monitoring programs prior to their sutsnittal in each Annual Environmental surveillance moport.

c. Violations of ETS to determine 4 ether adegaate corrective action is being taken to prevent recurrence.

d. Procedures or changes hereto, which could affect the monitoring of station operation, that may be considered by the Manager of Environmental Affairs, the Mana Engineer,ger-Nuclear Engineering and Chief Raclear i

or the Plant neview Board to be appropriate I

for SRB review.

5.3.1.4 The Plant Deview Board (PRB) shall review the following:

I

a. Proposed danges to pla'nt systems or equipnent.

5-2

. Amendment ?:o. 47

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I b.

Procedures for implementing the responsibilities specified in Section 5.1.1, and proposed changes thereto.

c.

Proposed changes to the ETS.

radioactive, material from the d.

Unplanned releases of a site.

l 5.3.1.5 The Manager-Nuclear Ingineering and Chi,ef Nuclear l

~~

Ergineer shall review the following:

a.

Proposed changes to plant systems or equipment, provided that such charges are identified by the PRB as having a potential radiological environmental impact.

b.

Proposed charges to Section 3.2 of the EIS.

5.3.2 Audit Responsibility

~

5.3.2.1 The General Manager of Quality Assurance and Radiological Health and Safety is responsible for an audit, conducted 4

at least once a year, of the activities of the General Manager-Plant

Hatch, the Manager of Invironmental Affairs, and the Manager-Nuclear Erigineering and Chief Nuclear Ergineer related to compliance with the EIS.

l 5.3.2.2 Audits of facility activities shall be performed at least j

once a year under the cognizance of the SRB to ensure i

conformance of facility operation to all provisions of the D*

v 5.4 Action to be taken if a Limitire Condition for Operation is Exceeded 5.4.1 Remedial action, as permitted by the ITS, shall be taken until the LCO can be achieved.

)

l 5.4.2 Violations of an LC0 will be reported immediately to the General Manager-Plant Hatch.

)

1 5.4.3 A separate report of each LC0 violation shall be prepared by the General Manager-Plant Hatch. Copies of such reports will i

be sutuiitted to the Vice President and General Manager Nuclear i

Operations, the Manager l'aclear Generation, the Manager of l

Invirorurental Affairs, the Manager-Nuclear Erigineering and l

Otief Nucloar Ergineer, and the Chairman of the SRB for review and approval of corrective actions, as specified in Section 5.3.1.3c.

5.4.4 The General Manager-Plant Hatch shall report such violations l

to the PetC in accordance with Section 5.7.2.

5.5 State and Federal Permit Certifications Section 401 of PL 92-500, the Pederal Water Pollution Control Act Amendments of 1972 (FWPCA), requires any applicant for a Federal license

. or permit to conduct any activity that,mee result in any discharge into 5-3 Amendment No. 47 i.

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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 shan set forth any effluent limitations and other limitations and acnitoring requirements necessary to assure that any e c=nt for a i

Federal license or permit win ecuply with the applicable limitations.

Certifications provided in accordance with Section 401 set forth conditions on the Federal license or per: nit for which the certification is provided. Accordingly, the licensee shan comply with the regairements set forth in the currently applicable 401 certification and amendments i thereto issued - to the licensee by the Georgia Environmental Protection Division.

In accordance with_ the provisions of the Georgia Water Quality control act,. the PHPCA and the rules ard regulations pecaulgated pursuant to each of these acts, the Georgia Envirorsnental Protection Division, j

under authority delegated by the U. S. EPA, issued NPDE5 Permit No. GA 0004120 to the licensee.

De WDES permit authorizes the licensee to discharge frcan Hw Units 1 and 2 to the Altamaha River in accordance with effluent limitations, monitoring requirements, and other conditions l_

stipulated in the

permit, effective August 1,

1983, through

~

i Decenter 5, 1937

*==rment revisions to the certifications win be accimacdated in accordance with the provisions of Section 5.7.3.

5.6 Procedures 3

Detailed written procedures, including applicable check lists and 1

instructions. shall be prepared and followed for all activities involved in implementing the ETS. Procedures shall apply to sampling, data j

recording ad storage, instrument calibration, sieasurement and data 4

recording and storace. instrument calibration, measurement and analysis, i

.and actions to be taken when limits are approached or exceeded. Testing frecuency of any alarm shall be included. These frecuencies shall i

be detennined from experience with similar instruments in similar environments and from manufacturers' technical manuals.

Plant operating procedures may be referenced in the' above procedures in areas pertaining to maintenance and calibration of instrumentation and in j

other such areas of interface with the above procedures.

J All procedures shan be maintained in a manner convenient for review and inspection.

Procedures which are the responsibility of the General j

i Manager-Plant Hatch shall be kept at the plant. Procedures which are the responsibility of the Manager of Environmental Affairs and the Manager-Itaclear Engineering and Chief laaclear Engineer shall be kept at l

the GPC General Office.

5.6.1 Envirorumental Programs Description Document ansed on these procedures, the licensee shan prepare and follow an environmental programa description document (EPDD) describing the acnitoring programs that are required by Sections 3.1 and 4.1.

Ris d= = ant shau include descriptions of sangling equipment locations, frequercies and rasuber of replications, sample analyses, data recording and storage, and instrument j

calibrations where appropriate.

I M

Amendment No. 47

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These program descriptions shall be approved by the NIC, and i

subsequent modifications to these programs shall be made by the licensee in acx:ordance with Sections 5.6.4 and 5.6.5.

4 5.6.2 Quality Assurance of Procram Results Procedures shall be esta' blished to assure the quality of E S program

-results, including analytical====wenents.

These. procedures shall i

h==nt the program in policy directives, designate responsible organizations or individuals, describe. purchased services (e.g.,

ccritractural leboratory or other contract services), and provide for audits of results and procedures by licensee personnel. In addition, l

these quality assurance procedures shall provide for systems to identify and correct deficiencies in technical monitoring programs or i

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

3 5.6.3 Concliance with Procedures l

In addition to the procedures specified in Section 5.6, the station j

operating procedures shall include prov!sions to ensure that each Unit and all its systems and + ats are operated in certpliance with the 1

conditions established in the EIS.

5.6.4 Chances in Procedures, DDD, and Station Desien or Operation i

i charxies in the peccedures, 500, and station design or operation may 4

be made in accordance with Section 5.3 and suject to the conditions described below:

)

l j

a.

The licensee may (i) make changes in the stations design and i

operation: (ii) make changes in the DDD developed in accordance l

3 with Gection 5.6.1 and (iii) conduct tests and experiments not i

described. in - the DDD without prior NIC approval, unless the proposed change, - test, or experiment involves either a change in the objectives of the ETS, an unreviewed envirorinental question of substantive impact, or affects the requirements of Section 5.6.5.

j b.

A proposed change, test, or experiment shall be deemed to involve an unreviewed envirorsnental question if it concerns (i) a matter Wiich may result in a significant increase in any adverse envirornental ingeet previously evaluated in the final environmental statement, as modified by staff's testimony at tne hearing, supplements thereto, envirorsmental ispect appraisals, or j

in initial or final adjudicatory decisionst or (ii) a significant r

change -in effluents or power level: - or (iii) a matter not previously reviewed and evaluated in the documents specified in (i) of this paragraph which may have a significant adverse 4

envirorsnental impact.

i 5-5 Amendment No. 47 1

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4 J

c. De licensee shan maintain records of changes to DDD and to facility design or operation made pursuant to this section.

De licensee also shall maintain recordy of tests and experiments carried out pursuant to. paragraph (a) of this i

section.

Sese records shall include a written evaluation which provides ~the bases for the determination that the change, test, or experiment does not involve an unreviewed envirorsnental question of substantive impact, or does not constitute a change in the objectives of the Ers, or does not affect the requirements of section 5.6.5.

De licensee shall furnish to the NRC, annually or at such shorter intervals as any be specified in the license, a report,containing 4

descriptions, analyses, interpretations, and evaluations of

-such changes, tests, and experiments.

d. Changes in the 3D0 which affect sanpling frM, location, gear, oc replication shall be reported to the NRC within 30 days after their inplementation, unless otherwise reported in l

accordance with section 5.7.3.

Changes which affect sampling technique or data recording and storage shall be reported to the NRC at the end of the year. Sese reports shan provide a 4

l description of the changes made, the reasons for making the i

changes, and an evaluation of the envirorsnental impact of these changes.

e. Proposed changes or modifications to plant systems or i

equipnent shall be reviewed in accordance with Section 5.3.

i f.

M changes. to procedures for implementing the responsibilities specified in Section 5.1.1 shan be reviewed 2

and approved by the PRB. Temporary changes to the procedures that do not change the intent of the original procedure may be made with the concurrence 'of two individuals holding senior reactor operator licenses. such changes shan be doctznented and subsequently reviewed by the Pf3 and approved by the General Manager-Plant Hatch on a timely basis.*

i i

i

g. Proposed changes-to gw ", ares for implementing the responsibilities specified in section 5.1.2 shan be reviewed by the staff of Envirorsne'ntal Affairs. Such proposed changes l

chan subsequently be reviewed and approved by the Nanager of Envitorsnental Affairs. - Proposed enanges to procedures for implementing the responsibilities specified in Section 5.1.3 shan be reviewed by the staff of the Manager-Nuclear l

Engineering and Chief Nuclear Engineer. Such proposed changes shan subsequently be reviewed and approved by the Manager-Nuclear Engineering and Chief Nuclear Engineer. When deemed appropriate by the Manager of Envirorynental Affairs or the Manager-Nuclear Engineerirng and Chief Nuclear -Engineer, 1

such proposed changes also shan be reviewed by the SPS prior to implemanation.

5-6 hmendment No. 47 i

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o (iii) an unusual or inportant event occurs, as specified in Section 4.2.

Reports shall be sutznitted under one of the report schedules described below:

~

a.

Proept Report - Dose events requiring prenpt reports 4

snall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telepnone, telegraph, or facsimile transmission, and followed within 10 days by a written report.

b.

'Ittirty Day Report - Nonroutine events not requiring a prompt report, as described in Section $.7.2a, shall be reported to NRC either (i)' within 30 days of their i

occurrence; or (ii) within the time limit designated in the appropriate specification; or (iii) within the time limit specified by the reporting requirement of the corresponding certification or permit issued pursuant to i

Section 401 or 402 of PL 92-500. The report sutsnitted to lec in accordance with (iii) of this paragraph will consist of a copy of the report made to the Georgia 1

Department of Natural Resources, Envirorsnental Protection Division.

Written

. reports and, to the extent possible, preliminary telephone, telegraph or facsimilie reports shall (i) describe, analyze, and evaluate the occurrence, includity the extent and magnitude of the inpact; (ii) describe the cause of the occurrence; and (iii) indicate corrective action (in=1udirq arrf siytificant cfurges made. in procedures) taken to preclude j

recurrence and to prevent similar occurrences involving similar cenponents or systems.

5.7.3 Chances in Envirefinental Tecnnical Specifications and Permits 5.7.3.1

_Cnan.c_es in mvironmental 1tennical Soecifications 1

l' Request for cfianges in EIS shall be sutznitted to the NRC for review and authorization in accordance with 10 CFR 50.90.

We request shall include an evaluation of the i

envirornental impact of the proposed -cfiange and a styporting justification.

Inplementation of suen l

requested enanges in ETs shall not ecumence prior to t

ircorporation by the lec of the new specifications in the 4 cense.

1 e

Proposed changes to the ETS shall be reviewed and j.

approved by the Manager of Dvironmental Affairs, the PRB and the SRB. Proposed changes to Section 3.2 also 4

will be reviewed and approved by the Marager-Nuclear pgineering and Osief Nuclear pgineer.

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

'It avoid conflicts and to maintain i

consistency between the safety and envircuinental aspects i

of plant operation, proposed cfianges to Section 2 will

]

be reviewed in the same menner as gW changes to the Safety Technical specifications.

1 5-9 Amendment No. 47 l

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I-f U EttfrI C VICE PRESIDfWT IDWIR SUPPLY t '

UINIRAL mmtetst QUAW FY ASSURAl E '

SAItiI RtvILW AND RADIOLOGICAL IIEAL1114 SAFI Y BOMtD (SRB)

T VICE PRESIDEP T ENGIRttRING SEN10fv1C5 PRESiliUT AND CDNSilt0CTION SERVICES NUCLEAR IONIR VICE PRE.3IDENT AND VICE PRESIDtWT AND 0I17 GENIRAL >MNAGIR ENGINEIR POWIR SUPPLY NUCLEAR OPERATIONS ENGINEERING AND SERVICES

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'.HAmGE t NUCLEAR ENGINEIRING AND OIIEF OllNISTRY AND a SMNAGER OF

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NUCIEAR ENGIPEiER llEAL111 filYSICS NUCI. EAR GENERATION I

GENERAI. &MNAGIR 6MMAGBt OF PtAITT llATOI ENVIROf4RWTAL AFFAIRS y

p b l REVIIM BQMtD (PRB) y a OR LY VACANT ORGANIZATION STRUCTURE RELATED TO INVIR041 ENTAL ACTIVITIES I

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FIQlRE 5.2-1

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMEN 0MENTS NOS.109 AND 47 TO J

FACILITY OPERATING LICENSES NOS. OPR-57 AND NPF-5 GEORGIA POWER COMPANY OGLETRRPFlWTTDF0lfATION MUNICIPAL ELECTRIC AUTHORITY OF SEORGIA CITY OF DALTON. GEORGIA t

EDWIN I. HATCH NUCLEAR PLANT, UNITS N05. 1 AND 2 4

DOCKETS NOS. 50-321 AND 50-366

1.0 INTRODUCTION

The licensee has requested by letters dated July 9, 1982, October 24 and December 20, 1983, and April-24, 1984, changes to the Technical Specifications for the Edwin I. Hatch Nuclear Plant Units 1 and 2.

We have reviewed those changes to Section 6 for Units 1 and 2.

A brief description 3

.of the changes and our evaluation follows:

2.0 EVALUATION 1.

Corporate Reorganization - The licensee has established under the,

Executive Vice President-Power Supply, a Senior Vice President-Nuclear Power who will be responsible for all Georgia Power Company (GPC) nuclear generating plants. Reporting to the Senior Vice President-Nuclear Power will be a Vice President and General Manager-Nuclear Operations who i

has reporting to him a Manager-Nuclear Chemistry and Health Physics, a Manager-Nuclear Training, a Manager-Nuclear Generation, and a Manager-j Nuclear Engineering and Chief Nuclear Engineer.

1 Reporting to the Executive Vice President-Power Supply is a General Manager-Quality Assurance and Radiological Health and Safety who establishes GPC policy and programs in these areas. The Vice President-Engineering and Construction Services, who also repor..ts to the Executive Vice President-Power Supply, provides engineering supportm r

plant additions or modifications. The Safety Review Board also report the Executive Vice President-Power Supply. Technical support for the Hatch Station is still supplied by the Southern Company Service in engineering disciplines and for the nuclear fuel.

This organization structure is shown in a revised Figure 6.2.1-1.

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! 4 We have reviewed these changes and find that they do not dele.te technical support for the operation of the Hatch Station and should provide for increased upper level management involvement in support of the Hatch Station. These changes also meet the acceptance criteria of Section 13.1.1 of the SRP (NUREG-0800). Therefore, we find these changes acceptable.

l 2.

Plant staff reorganization - The positions of Plant Manager and Assistant Plant Manager have been retitled to General Manager and Deputy General Manager respectively. Reporting to the Deputy General Manager is a new level of _ Managers: a Manager-Engineering; Manager-Maintenance; Manager-0perations; Manager-Administrative, Finance, and Human Resources; c

Manager-Health Physics and Chemistry; and a Manager-Training, with.their 1

respective staffs.. This is shown in revised Figure 6.2.2-1.

The revised plant staff has deleted the requirement that the General Manager (formerly Plant Manager) or the Deputy General Manager (formerly Assistant Plant Manager) have a Senior Operators License.

We have reviewed these changes and find that they do not delete technical support for the operation of_the Hatch Station and meet the j

acceptance criteria of Section 13.1.2 of the SRP (NUREG-0800).

Therefore, we find these changes acceptable.

3.

. Plant Review Board - The licensee has revised the composition of the Plant Review Board to increase its membership from seven to nine members and to reflect new organizatienal,ositions of the revised plant organization.

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A quorum of the Plant Review Board shall consist of the chairman or designated j

chairman and four voting members, including alternates.

1 We find this change acceptable as it meets the acceptance criteria of 4

j Section 13.4 of the SRP (NUREG-0800).

4.

Audits - The licensee has changed the audit frequency relative to the Emergency and Security plans and their implementing procedures from once per 24 months to once per 12 months to bring the audit frequency into conformance with 10 CFR 50 and 10 CFR 73 requirements.

i We find this change acceptable as the audit frequency conforms to 10 CFR 50 i

and 10 CFR 73 requirements.

5.

Procedural Approval - The licensee has changed the provision for b

procedure approval to allow predesignated department managers to have approval authority for specified procedures in their areas of expertise.

We find this change acceptable as it meets the acceptance criteria of Section 13.5 of the SRP (NUREG-0800).

6.

Miscellaneous - There have been numerous changes made to the text

_ throughout Section 6 to reflect the revised organizational structure to l

the corporate and the plant staff level. These changes are acceptable since they merely conform the text of Section 6 to the revised 3

organizational titles.

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3.0 ENVIRONMENTAL CONSIDERATION

S This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

4.0 CONCLUSION

S We have concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

F. Allenspach Dated:

June 27,1985 h

.

v t e Letter Sequence Other
TAC:08043, (Open) TAC:08095, (Open) TAC:8043, (Open) TAC:8095, (Open)
Initiation Request, Request, Request, Request, Request Acceptance... Administration Meeting, Meeting, Meeting, Meeting, Meeting, Meeting Questions Answers Results Approval, Approval, Approval Other: ML19254E990, ML19261B262, ML19261B350, ML20023B885, ML20024F311, ML20062G268, ML20093C407, ML20101Q731, ML20127C328, ML20129J045, ML20134A118, ML20134A133, ML20134A144
MONTHYEAR1983-10-06 [Table View]

ML20134A118

Text

Attachment:

Attachment:

=.:

1.0 INTRODUCTION

3.0 ENVIRONMENTAL CONSIDERATION

4.0 CONCLUSION

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