Text

Amends 109 & 47 to Licenses DPR-57 & NPF-5,respectively, Revising Tech Specs to Reflect Corporate & Plant Reorganization to Change Composition of Plant Review Board & to Delete Senior Reactor Operator License Requirement
	ML20128L194
Person / Time
Site:	Hatch
Issue date:	06/27/1985
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA
Shared Package
ML20128L200	List: ML20128L194; ML20128L220;
References
	TAC 49076, TAC 49077, TAC 49706, DPR-57-A-109, NPF-05-A-047 NUDOCS 8507240360
	Download: ML20128L194 (46)
	v • d • e

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$2 recoq(o g

UNITED STATES NUCLEAR REGULATORY COMMISSION o

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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.109 License No. DPR-57 i

1.

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

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 Comission's rules and regulations-set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the

-provisions of the Act, and the rules and regulations of the Comission; C..There is reasonable assurance (i) that the activities a'uthorized by this amendment can be conducted without endangering the health and -

safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the 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 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:

8507240360 850627 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 COMMISSION JJ F. Sto z, Chief Uperating Reactors ranch #4

' Division of Licensing

Attachment:

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

ATTACHMENT TO LICENSE AMENDMENT NO.109 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 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 6-6 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 5-6 5-6 5-9 5-9 5-11 5-11

i a

6.0 AD4INISTRATIVE CONTRnrs 6.1 RESPCEIBILITY 6.1.1 'Itie 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 OIGANIZATION OFTSI'IE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2.1-1.

UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and:

a.

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

b.

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

c.

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

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

e.

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

f.

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

f HAICH UNIT 1 6-1 Amendment flo.109

ADUNISMATIVE COMELS g.

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

senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating 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 temporary 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 more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months r

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 ' hours in any seven day period, all excluding shift turnover time.

4 (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

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

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

designee tio assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

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AININISTRATIVE CONTpnrR 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or e::ceed the minimum qualifications of ANSI N18.1-19'/1 for comparable positions except for the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, Septenber 1975, and the Shift 'nx:hnical Advisor who shall 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 TRAINDG 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 l

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

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

6.5 REVIN AND AUDIT 6.5.1 PIANP REVIN BOARD (PRB)

Ft2CTICN 6.5.1.1 The PRB shall function to advise the General Manager-Plant Hatch on l

all matters related to nuclear safety.

CD1 POSITION 6.5.1.2 The Plant Review Board shall be composed of the:

Chairman *:

General Manager-Plant Hatch Member:

Deputy General Manager Member:

Superintendent of Operations Member:

Superintendent of Maintenance Member:

Health Physics Sup:rintendent Member:

Superintendent of Quality Control Member:

Superintendent of Plant Engineering and Services Member:

Superintendent of Regulatory Compliance Menber (non-voting):

Representative of Site Quality Assurance

General Manager-Plant Hatch to designate chairman from voting PRB membership as necessary.

ALTERNNFES 6.5.1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis; however, no more than two alternates snall participate as voting members in PRB activities at any one time.

HA'IO! - UNIT 1 6-6 Amendment No.109

AININISTRATIVE COMROLS MEETING FRBQUENCY 6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chaiman or his designated alternate.

QUWiN 6.5.1.5 The minium quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chaiman or designated Chaiman and four l

I voting members including alternates.

RESPONSIBILITIES

6. 5.1. 6 The Plant Revieu Board shall be responsible for:

a.

Review of (1) all procedures. required by Specification 6.8 and changes thereto, (2) any other proposed procedures or changes thereto as determined by the General Manager-Plant Hatch to affect l

nuclear safety.

4 b.

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

c.

Review of c11 proposed changes to Appendix "A"

Technical Specifications.

d.

Review of all proposed changes or modifications to unit systems or

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equipment that affect nuclear safety.

e.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations 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 requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notification to the Comiission.

g.

Review of unit operations to detect potential nuclear safety hazards.

h.

Perfomance of special reviews, investigations or analyses and -

reports thereon as requested by the General Manager-Plant Hatch or l

the SRB.

HATCH-UNIT 1 6-7 Amendment No.109 v.

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

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

AUIHORITY

6. 5.1. 7 The PRB shall:

i a.

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

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

b.

Render determinations in writing with regard to whether or not 1

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

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 l

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.

i RECORDS

6. 5.1. 8 The Plant Review Board shall maintain written minutes of each PRB meeting that, at a minimum, document the results of all PRB activities performed under the responsibility and authority provisions of these Technical Specifications.

Copies shall be provided to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations and the Safety Review Board.

6.5.2 SAFEIY REVIEW BOARD (SRB)

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

a.

Nuclear power plant operations, b.

Nuclear engineering, c.

Chemistry and radiochemistry.

HATCH - UNIT 1 6-8 Amendment flo.109

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Metallurgy, e.

Instrumentation and control, f.

Radiological safety, g.

Mechanical and electrical engineerirg, h.

Quality assurance practices.

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

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

person as he shall designate.

The composition of the SRB shall meet the, requirements of ANSI N18.7-1976.

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

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

MEETIN3 rmuutNCY 6.5.2.5 The SRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.

HATG - UNIT 1 6-9 Amendment No.109 r

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- AININISTPATIVE CONrpdrR AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the SRB. Each inspection or audiE shall be performed within the specified time interval with:

1.

A maximum allowable extension not to exceed 25% of the inspection or audit interval.

2.

A total maximum cortined interval time for any 3 consecutive j

inspection or atdit intervals not to exceed 3.25 times the specified inspection or audit interval.

@ese audits shall enecmpass:

a.

The conformance of unit operation to provisions contained within the 'Itchnical 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.

c.

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

d.

%e performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

1 e.

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

f.

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

g.

Any other area of unit operation considered appropriate by the SRB l

or the Executive Vice President Power Supply.

I h.

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

i.

An independent fire protection and loss prevention inspection and i

audit shall be performed annually utilizing either gaalified offsite licensee personnel or an outside fire protection firm.

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j.

An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant

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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.

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AININISTRATIVE CONTROLS AUINORITY 6.5.2.9 h 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.

RECORDS 6.5.2.10 Records of SRB activities shall be prepared, approved and dis M buted as indicated below:

a.

Minutes of each SRB meeting shall be prepared, approved and fowarded to the Executive Vice President-Power Supply within 14 1

days following 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 encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President-Power Supply and to the I

management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION j

6.6.1 h following actions shall be taken for REPORTABLE OCCURRENCES.

a.

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

Each REPORTABLE OCQJRRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Countission shall be reviewed by the PRB and submitted to the SRB and the Manager of Nuclear Generation or the Vice President and l

General Manager Nuclear Operations.

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

h unit shall be placed in at least HUr SHlTTDOWN within two hours.

a.

b.

h Safety Limit violation shall be reported to the Commission, the

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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 .

i HATCH - UNIT 1 6-12 Amendment flo.109

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AININISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PRB.

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

d.

'The Safety Limit Violation Report shall be submitted to the Commission, the SRB and the Manager of Nuclear Generation or the i

Vice President and General Manager Nuclear Operations within 14 i

days of the violation.

6.8 PROCEDURES i

6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

f a.

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

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

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 thereto, shall be reviewed by the PRB and approved by the appropriate member of plant management, designated by the General Manager - Plant Hatch, prior Plant Hatch will approve to implementation.

The General Manager administrative procedures, security plan implementing procedures, emergency plan implementing procedures and changes thereto.

All other procedures of this specification and chariges thereto will be approved by the department head designated by the General Manager - Plant Hatch.

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

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

a.

The intent of the original procedure is not altered.

b.

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

c.

The change is doctamented, reviewed by the PRB and approved in i

writing by the General Manager.- Plant Hatch, or his designee as l

assigned by 6.8.2, within 14 days of implementation.

HATO{ - UNIT 1 6-13 Amendment flo.109 e@

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

a.

A radiction monitoring device which continuously indicates the 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 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 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.

l 6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems 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 include the following:

1)

Provisions 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, l

(4) HPCI, and (5) RCIC.

6.14 IODINE MONITORING 1

The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

under l

accident conditions. This program shall include the following:

1)

Training of personnel, 2)

Procedures for monitoring, and l

3)

Provisions for maintenance of sampling and analysis equipment.

l

Areas requiring personnel access for establishing hot shutdnwn condition.

l HATCH - UNIT 1 6-21 Amendment No. 65, 79,109 l

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5.0 Administrativa controls his section describes administrative and management controls established to implement the HNP Environmental 'Iednical Specifications (ETS).

Measures specified in this section include assignments of responsibility, review and audit functions, procedures, and reporting requirements.

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Corporate responsibility for implementation of the ETS and for assuring that. the station is operated in such a way as to provide protection for the environment rests with the Executive Vice President - Power Supply.

I Responsibilities for canpliance with the ETS and for the envirorsnental monitoring program required by the ETS are given,below.

Independent audit shall be provided for all matters, as discussed in Section 5.3.2, by the General Manager of Quality Assurance and g -

Radiological Health and Safety.

5.1 Re!!ponsibility 5.1.1

%e General Manacer-Plant Hatch is responsible for monitoring

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plant effluents; for operating the plant within the Limiting conditions for operation (IIDs) spe'cified in Section 2r and for the collection and measurements associated with all radiological i

samples described in Section 3.2, except for clams, American shad, shoreline sediment, and the annual surveys.

%ese exceptions are the responsibility of the Manager of Environmental Affairs. We General Manager-Plant Hatch also is l

responsible for inplementing the special surveillance activities described in Sections 4.2 and 4.3.

l 5.1.2 he Manager of Environmental Affairs is responsible for the envirorsnental monitoring programs specified in Sections 3 and 4, 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 that are not assigned either (i) to the General Manager-Plant Hatch by Section 5.1.1 or (ii) to the. Manager-Nuclear j

Engineering and Chief Nuclear Engineer by Section 5.

We Manager of Environmental Affairs is responsible.for coordinating these programs with appropriate groups.

5.1.3 he Manager-Nuclear Engineering and Chief Nuclear Engineer is l

responsible for the interpretation, evaluation, and routine reporting of the results of the radiological environmental monitoring program described in Section 3.2.

5.1.4 2e General Manager of Quality Assurance and Radiological Health and Safety is responsible for conducting periodic audits of p

plant operations and the environmental nonitoring activities to ensure conformance with the ETS.

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

Changes affecting cwgy organization depicted in Figure 5.2-1 will not require NRC approval prior to

~ implementation, but such danges shall be reported to NRC within 30 days in accordance with section 5.7.2 5-1 Amendment flo.109 l

i

E 5.3 Review and Audit 5.3.1 Independent Review 5.3.1.1 The General Manager-Plant Hatch is responsible for I

routine review of plant operations to ensure that HNP is operated in compliance with the Icos specified in Section 2.

5.3.1.2 The Manager of Environmental Affairs shall review the following:

a. We conduct of the environmental monitoring programs, on a routine basis, to ensure that the specifications in Sections 3 and 4 are being inplemented.

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

potential adverse envirorrnental inpact.

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

d. Proposed changes to the ETS.

e. Proposed changes to the Environmental Programs Description Document.

5.3.1.3

%e Safety Review Board (SRB) shall review the following:

a. Proposed changes to the ETS.

b. Results _ of the environmental monitoring programs prior to their submittal in each Annual Environmental Surveillance Report.

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

l.

d. Procedures or changes hereto, which could affect the monitoring of station operation, that may be considered by the Manager of Environmental Affairs, the Manager-Nuclear Engineering and Chief Nuclear Engineer, or the Plant Review Board to be appropriate for SRB review.

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

l

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

5-2

. Amendment No. 109 I

I'

!j __

-.. -. -._._ _. -~____ ____ _ _ _.. _. -. _.,

~,---------. -._ -,-_ -.

d 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 from the site.

5.3.1.5 The Manager-Nuclear Engineering and Chief Nuclear l

~~

Emineer shall review the following:

l t

Proposed changes to plant systems or equipment, provided a.

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

b.

Proposed cha g es to Section 3.2 of the ETS.

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

Hatch, the Manager of Environmental Affairs, and the Manager-Nuclear Engineering and Chief Nuclear Ergineer related to compliance with the E13.

5.3.2.2 Audits of facility activities shall be perfomed at least once a year under the cognizance of the SRB to ensure i

conformance of. facility operation to all provisions of the ETS.

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

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

5.4.3 A separate report of each LCO violation shall be prepared by the General Manager-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 Environmental Affairs, the Manager-Nuclear Engineering and Chief Nuclear Egineer, 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 NRC in acconiance with Section 5.7.2.

5.5 State and Federal Permit Certifications Section 401 of PL 92-500, the Federal Water Pollution Control Act i

Amendments of 1972 (FWPCA), requires any applicant for a Federal license or pemit to conduct any activity that enay result in any discharge into 5-3 Amendment No.109

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i provisions of Sections 301, 302, 306, and 307 of the EWPCA.

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 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 Federal license or permit for which the certification is provided.

Accordingly, the licensee shall comply with the requirements set forth in the currently applicable 401 certification and amendments (

thereto issued to the licensee by the Georgia Environmental Protection i

Division.

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

We NPDES permit authorizes the licensee to discharge from HNP Units 1 and 2 to the Altamaha River in accordance with effluent limitations, monitoring requirements, and other conditions stipulated in the

permit, effective August 1,

1983,~ through Decenber 5,1987 Subsequent revisions to the. certifications will be a e- --_-hted in acx:ordance with the provisions of Section 5.7.3.

5.6 Procedures Detailed written procedures, including applicable check lists and instructions, shall be prepared and followed for all activities involved in implementing the ETS. Procedures shall apply to sampling, data 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 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 areas pertaining to maintenance and calibration of instrumentation and in other such areas of interface with the above procedures.

i All procedures shall be maintained in a manner convenient for review and l

inspection.

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

the GPC General Office.

5.6.1 Envirorsnental Programs Description Document i

Based on these procedures, the licensee shall prepare and follow l

an environmer.tal program description document (EPDD) describing I

the monitoring programs that are required by Sections 3.1 and 4.1.

Wis document shall include descriptions of sanpling equipnent locations, frequencies anr: number of replications, 4

sample analyses, data recording and storage, and instrument calibrations where appropriate.

i 5-4 Amendment No.109

These program ~ descriptions shall be approved by the NRC, and 1

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

5.6.2 Quality Assurance of Program Results Procedures shall be esthblished to assure the quality of FIS program results, including analytical measurements.

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

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

5.6.3 Coupliance with Procedures In addition to the procedures specified in Section 5.6, the station operating procedures shall include provisions to ensure that each Unit and all its systems and components are operated in compliance with the conditions established in the ETS.

5.6.4 Changes in Procedures, EPDD, and Station Design or Operation Changes in the procedures, EPDD, and station design or operation may be made in accordance with Section 5.3 and suject to the conditions described below:

a.

The licensee may (i) make changes in the stations design and operation; (ii) make changes in the EPDD developed in accordance with section 5.6.1; and (iii) conduct tests and experiments not

. described in the EPDD without. prior NBC approval, unless the proposed change, test, or experiment involves either a change in the objectives of the ETS, an unreviewed environmental question of substantive inpact, 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 (i) a matter

(

which may result in a significant increase in any adverse envirornental inpact previously evaluated in the final environmental statement, as modified by staff's testimony at the hearing, supplements thereto, environmental inpact appraisals, or in initial or final adjudicatory decisions; or (ii) a significant change in effluents or power level; or (iii) a matter not previously reviewed and evaluated in the doctanents specified in (i) of this paragraph which may have a significant adverse l

environmental impact.

l 5-5 Amendment No. 109 l-I

V.

i

c. %e -licensee shall maintain records of changes to EPDD and to facility design or operation made pursuant to this section.

@e licensee also shan 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 ETS, or does not affect the requirements of Section 5.6.5.

We licensee shall furnish to the NRC, annually or at such shorter intervals as may be specified in the

licerise, a

report,containing descriptions, analyses, interpretations, and evaluations of-such changes, tests, and experiments,

d. Changes in the EPDD which affect sanpling frequency, location, gear, or replication shall be reported to the NRC within 30 days after their implementation, unless otherwise reported in accordance with Section 5.7.3.

Changes which affect sangling technique or data recording and storage shall be reported to the NRC at the end of the year. These reports shall provide a description of the changes made, the reasons for making the changes, and an evaluation of the environmental inpact of these changes.

e. Proposed changes or modifications to plant systems or equipment shan be reviewed in accordance with Section 5.3.

f. Proposed changes to procedures for inplementing the responsibilities specified in Section 5.1.1 shall be - reviewed and approved by the PRB. Tenporary 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 shall be documented and subsequently reviewed by the PRB and approved by the General Manager-Plant Hatch on a timely basis.>

l

g. Proposed changes to procedures for implementing the i

responsibilities specified in Section 5.1.2 shan be reviewed by the staff of Environnental Affairs. Such proposed changes shall subsequently be reviewed and approved by the Manager of i

Environmental Affairs.

Proposed changes to procedures for i

implementing the responsibilities specified in Section 5.1.3

(

shall ba reviewed by the staff of the Manager-Nuclear l-Engineering and Chief Nuclear Engineer.

Such proposed changes l

shan snh==quantly be reviewed and approved by the Manager-Nuclear Engineering and Chief Nuclear Engineer. When L

deemed appropriate by the Manager of Envirorynental Affairs or l

the Manager-Nuclear Engineering and Chief Nuclear Engineer, such proposed changes also shall be reviewed by the SRB prior to implemenation.

5-6 Amendment No. 109 1

I

~----~-w-- ~a

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~

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

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

a.

Prompt Report - Those events requiring pronpt reports shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone, telegraph, or facsimile transmission, and followed within 10 days by a written report.

b.

Thirty Day Report - Nonroutine events not requiring a prompt report, as described in Section 5.7.2a, shall be reported to NRC either (i)' within 30 days of their 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 correspording certification or permit issued pursuant to Section 401 or 402 of PL 92-500.

The-report submitted to NRC in accordance with (iii) of this paragraph will consist of a copy of the report made to the Georgia Department of Natural Resources, Environmental Protection Division.

Written., reports and, to the extent possible, -preliminary telephone, telegraph or facsimilie reports shall (i) describe, analyze, and evaluate the occurrence, including the extent and magnitude of the impact; (ii) describe the cause of the occurrence; and (iii) indicate corrective action (including any significant danges made in procedures) taken to preclude recurrence and to prevent similar occurrences involving similar components or systems.

5.7.3 Charr es in Environmental Technical Specifications and Permits 5.7.3.1 Changes in Environmental Tecnnical Specifications Request for changes in ETS shall be submitted to the NRC for review and authorization in accordance with 10 CFR 50.90.

The request shall irclude an evaluation of the environmental impact of the proposed change and a supporting justification.

Implementation of such requested changes in ETS shall not conmence prior to incorporation by the NRC of the new specifications in the ).icense.

Proposed changes to the ETS shall be reviewed and approved by the Manager of Environmental Affairs, the PRB and the SRB.

Proposed changes to Section 3.2 also will be-reviewed and approved by the Manager-Nuclear Engineering ard Chief Nuclear Engineer.

Prict to approval, the possible impact of the proposed clanges will be evaluated.

70 avoid conflicts and to maintain consist'ency between the safety and environmental a:pects i

of plant operation, proposed changes to Section i will i

be reviewed in the same manner as proposed chances to the Safety Technical Specifications.

{

5-9 Amendment flo.109

EXEClTTIVE VICE PRESIDENT POWIR SUPPLY GENIRAL MANAbt:K QUALITY ASSURANCE SAFlitT REVIEW i

AND RADIOLOGICAL llEAL'Ill 4 SAFEIY BOARD (SRB)

VICE PRESIDD T ENGINhtRING SENIO81 VIC3 PRESIDINT AND CONSTRUCTION SERVICES NUCL2AR POWIR VICE PRESIDENT AND VICE PRESIDINT AND 01IEF I

GENIRAL MANAGIR ENGINEER POWER SUPPLY NUCLEAR OPERATIONS ENGINEERING AND SERVICES MANAGIR NUCLEAR MANAGBt NUCLEAR ENGINEIRING AND CIIEF CIIINISTRY AND a MANAGER OF NUCLEAR ENGINEER IIEAL'Ill IHYSICS NUCLEAR GENERATION 1I GENERAL MANAGER MANAGER OF PIANT llATOf ENVIRONENTAL AFFAIRS s.n b

PLANI REVIEW BOARD (PRB) iY k

a CURREKILY VACANT ORGANIZATION STRUCI1JRE RELATED g

TO ENVIROM ENTAL ACTIVITIES a

FIGJRE 5.2-1 5

a e

e

ff UNITED STATES l

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g NUCLEAR REGULATORY COMMISSION 5

4j WASHINGTON, D. C. 20555

/

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

The Nucle 0r Regulatory Comission (the Comission) has found that:

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

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'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 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. NPF-5 is hereby amended to read as follows:

~__

2-Technical Specifications The_ Technical Specifications contained in Appendices 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 4

Technical Specifications.

3.

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

FOR THE NUCLEAR R GULATORY COMMISSION Jo F. Stofz, Chigf 0 rating Reactors ( ranch #4

< Division of Licensing

Attachment:

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

ATTACHMENT TO LICENSE N4ENDMENT NO. 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 5-5 5-5 5-6 5-6 5-9 5-9 5-11 5-11

- 6.0 AEMINISTRATIVE CON 1WYR 6.1 RESPONSIBILITY 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 j

responsibility during his absence.

6.2 OR3ANIZATION

~

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

UNIT STAFF t

6.2.2 The. unit organi2.ation shall be asj shown on Figure 6.2.2-1 and:

Each on duty shift shall be ccznposed of at least the minimum shift a.

crew composition shown in Table 6.2.2-1.

b.

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

each reactor containing fuel.

l c.

At least two licensed Operators shall be present in the control l

roan for each reactor in the process of start-up, scheduled reactor shutdown and during recovery from reactor trips.

d.

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

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

f.

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

t 6-1 Amendment No. 47 IMOI UNIT 2

/

t

(

1 ADIINISTRATIVE COB 7TROLS g.

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

senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operatirg.

Howver, 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 temporary 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 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, all excluding shift turnover time.

(3) A break of at leact 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 antire 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

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

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

designee to assure thry excessive hours have not been assiged.

Routine deviation from the above guidelines is not authorized.

HA'IQi UNIT 2 6-la Amendment No. 47 1

J

PRESIDENT

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VICE PRESIDENT Q

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HATCH UNIT 2 6-3 Amendment flo. 47 wa-,, -,

-, - - ~.

ADMINISTFATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATICNS i

6.3.1 Each mernber of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except for th'e Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor. who shall have a bachelor's degree or 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 TPAINItG 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 I -

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

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

6.5 REVIDi AND AUDIT 6.5.1 PIANT REVIH4 BOARD (PRB)

FLNCTICN 6.5.1.1 The PRB shall function to advise the General Manager-Plant Hatch on l

all matters related to nuclear safety.

COMPOSITICN 6.5.1.2 'The Plant Review Board shall be conposed of the:

Chairman *:

General Manager-Plant Hatch Member:

Deputy General Manager i

Member:

Superintendent of Operations Member:

Superintendent of Maintenance Member:

Health Physics Superintendent Member:

Superintendent of Quality Control Member:

Superintendent of Plant Engineering Services Member:

Superintendent of Regulatory Compliance Member (non-voting):

Representative of Site Quality Assurance

General Manager-Plant Hatch to designate chairman from voting PRB I

merrbership as necessary.

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

HNIG - UNIT 2 6-5 Amendment No. 47 g

l

' AININIS1RATIVE CONTROLS

-MEETING FREQUENCY

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

QUCRIN

6. 5.1. 5 The miniatui quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or designated Chairman and four l

voting members including alternates.

RESPONSIBILITIES

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

a.

Review of (1) all procedures required by Specification 6.8 and changes thereto, (2) any other proposed procedures or changes thereto as determined by the General Manager-Plant Hatch to affect I

nuclear safety.

b.

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

c.

Review of all proposed changes to Appendix "A"

Technical Specifications.

d.

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

e.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recomaendations 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 requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notification to the Consission.

g.

Review of unit operations to detect potential nuclear safety hazards.

h.

Performance of special review investigations or analyses and reports thereon as requested by the General Manager-Plant Hatch or i

the SRB.

i i

l HATCH-UNIT 2 6-6 Amendment No. 47 l

AININI51'RATIVE CONTROLS RESPONSIBILITIES (Continued) 1.

Review of the Security Plan and implementing procedures and shall submit reconsnended changes to the SRB, J.

Review of the Emergency Plan and implementing procedures and shall submit reconsnended changes to 'the SRB.

AIJIMORITY 6.5.1.7 The PRB shall:

Reconsnend in writing to the General Manager-Plant Hatch approval I

a.

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

b.

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

c.

Provide written. notification 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 6.5.1.8 The Plant Review Board shall maintain written minutes of each PRB meeting that, at a minimum, document the results of all PRB activities performed under the responsibility and authority provisions of these Technical Specifications.

Copies shall be provided to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations and the Safety Review Board.

6.5.2 SAFEIT REVIEW BOARD (SRB)

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

a.

Nuclear power plant operations, b.

Nuclear engineering, c.

Chemistry and radicchemistry.

HATOi - UNIT 2 6-7 Amendment No. 47

AIMINISTRATIVE CONTROLS MRCTICE (Continued) d.

Metallurgy, e.

Instrumentation and control, f.

Radiological safety, g.

Mechanical and electrical engineering, h.

Quality assurance practices.

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

The Chairman and Vice Chairman and other members shall be Power Supply or such other l

. appointed by the Executive Vice President person as he shall designate.

The composition of the SRB shall meet the requirements of ANSI N18.7-1976.

ALTERNATES 6.5.2.3 All alternate representatives shall be appointed in writing by the absent member to serve on a temporary basis; however, no more than two alternates shall participate in SRB activities at any one time and alternate representatives shall not have votirg privileges.

CotEULTAtTIS 6.5.2.4 Censultants shall be utilized as determined by the SRB Chairman or Vice-Chairman to provide expert advice to the SRB.

' MEETI1G FmuuDCY 6.5.2.5 The SRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.

HAICH - UNIT 2 6-8 Amendment No. 47 m

..__,.m__

.-..c...

L I

l ADtINISTPATIVE CO!NJ AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the SRB. Each inspection or audiE shall be performed within the specified time interval with:

1.

A maximum allowable extension not to exceed 25% of the inspection or audit interval.

2.

A total maximum combined interval time for any 3 consecutive inspection or audit intervals not to exceed 3.25 times i:he specified inspection or audit interval.

These audits shall enccupass:

a.

The conformance of unit operation to provisions contained within the 7echnical 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.

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

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

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months, e.

The Emergency Plan and irplementing procedurer at least once per 12 months shall 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 shall be performed by individuals who have no direct responsit'lity for implementation of this plan.

9 Any other area of unit operation considered apprcpriate by the Spa l

or the Executive Vice President Power Supply.

I h.

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

i.

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

During the year in which the inspection or audit occurs, the requirements of 6.5.2.81 can be affected concurrently.

HATCH - UNIT 2 6-10 Amendment No. 47 1

AD4INISTRATIVE CONTROLS AITINORITY 6.5.2.9 The SRB shall report to and advise the Executive Vice President -

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

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

a.

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

days following 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 zwports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President-Power Supply and to the I

management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REP 0krABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES.

The Commission shall be notified and/or a report submitted pursuant a.

to the requirements of Specification 6.9 b.

Each. REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Consiission shall be reviewed by the PRB and submitted to the SRB and the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations.

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

The unit shall be placed in at least HOT SHlTTDOWN within two hours.

a.

b.

The Safety Limit violation shall be reported to the Cosmiission, 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 .

j i

i I

HATO! - UNIT 2 6-11 Amendment No. 47

AININISTRATIVE CONTROLS SAFE 1Y LIMIT VIOLATION (Continued) c.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PRB.

This report shall describe (1) applicable circunstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and

- - ~

(3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commission, 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 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

The applicable procedures recommended in Appendix "A" of Regulatory a.

Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Energency Plan implementation.

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 thereto, shall be reviewed by the PRB and approved by the appropriate member of plant management, designated by the General Manager - Plant Hatch, prior Plant Hatch will approve to implementation.

The General Manager administrative procedures, security plan implementing procedures, emergency plan implementing procedures and changes thereto.

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

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

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

a.

The intent of the original procedure is not altered.

b.

De change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c.

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

HATOi - UNIT 2 6-12 Amendment flo. 47

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

a.

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

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 surveillance at the frequency specified by the facility Health l

Physics supervision in the Radiation Work Pemit.

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 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.

l 6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems 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 include the following:

1)

Provisions 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.

HATCH - UNIT 2 6-19 Amendment No. 47

,~

1 l

~5.0 Administrativa controls This section describes administrative and management controls established to implement the HNP Environmental 'Itchnical Specifications (ETS).

Measures specified in this section include assignments of responsibility, review and audit functions, procedures, and reporting requirements.

Corporate responsibility for implementation of the ETS and for assuring that the station is operated in such a way as to provide protection for,

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

I Responsibilities for cepliance with the ETS and for the enviromental monitorirg program required by the ETS are given. below.

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

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

Radiological Health and Safety.

5.1 Resoonsibility 5.1.1 The General Manager-Plant Hatch is responsible for monitoring

(

r plant effluents; for operating the plant within the Limiting

. Conditions for operation (T.00s) specified in Section 2; and for the collection and measurements associated with all radiological samples described in Section 3.2, except for clams, American

shad, shoreline sediment, and the annual surveys.

These exceptions are the responsibility of the Manager of Enviromental Affairs.

The General Manager-Plant Hatch also is l

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 environmental monitoring programs specified in Sections 3 and 4, 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 that are not assigned either (i) to the General Manager-Plant Hatch by Section 5.1.1 or (ii) to the Manager-Nuclear Engineering and Chief Nuclear Engineer by Section 5.

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

The Manager-Nuclear Engineering and Chief Nuclear Engineer is l

5.1.3 responsible for the interpretation, evaluation, and routine reporting of the results of the radiological environmental monitoring program described in Section 3.2.

5.1.4

'the General Manager of Quality Assurance and Radiological Health and Safety is responsible for conducting periodic audits of plant operations and the environmental monitoring activities to ensure conformance with the ETS.

5.2 Oraanization

_ A chart showirg capany organization relative to environmental matters is l

presented in Figure 5.2-1.

Changes affecting company organization i

depic ted in Figure 5.2-1 will not require NRC approval prior to l

implementation, but such changes shall be reported to NRC within 30 days l

in acx:ordance with Section 5.7.2 l

5-1 Amendment No. 47 p.

.,,.,,.. _.,,. _,,. _... ~. - - -. _.. _..

5.3 Review and Audit 5.3.1 Indeoende.at Review 5.3.1.1 The General Manager-Plant Hatch is responsible for i

routine r.eview of plant operations to ensure that HNP is operated in compliance with the ICOs specified in Section 2.

5.3.1.2 The Manager of Environmental Affairs shall review the following:

a. te conduct of the environmental monitoring programs, on a routine basis, to ensure that the specifications in Sections 3 and 4 are being implement 6d.

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

potential adverse envirorsnental impact.

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

d. Proposed changes to the EIS.

e. Proposed changes to the Environmental Programs Description Document.

5.3.1.3 The Safety Review Board.(SRB) shall review the following:

a. Proposed changes to the ETS..

b. Results of the environmental monitoring programs prior to their submittal in each Annual Environmental Surveillance Report.

c. Violations of ETS to determine whether adequate 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 Manager-Nuclear Engineering and Chief Nuclear Engineer, or the Plant Review Board to be appropriate for SRB review.

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

a. Proposed changes to pla'nt systers or equipment.

5-2

-Amendment !!o. 47

... ~.-

b.

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

Proposed cilanges to the ETS.

c.

d.

Unplanned releases of a radioactive, material from the site.

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

Engineer 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 changes to Secticn 3.2 of the ETS.

C.3.2 Audit Responsibility 5.3.2.1 The General knager of Quality Assurance and Radiological Health and Saf e,ty is responsible for an audit, conducted at least once a year, of the activities of the General Manager-Plant

Hatch, the Manager of Environmental Affairs, and 7.he Manager-Nuclear Engineering and Chief Nuclear Engineer re _ated to compliance with the ETS.

5.3.2.2 Audits of facility activities shall be performed at least once a year under the cognizance of the SRB to ensure conformance of facility operation to all provisions of the ETS.

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

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

5.4.3 A separate report of each LCO violation shall be prepared by the General Manager-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 Environmental Affairs, the Manager-Nuclear Er ' - ' ring and Chief Nuclear Engineer, and the Chairman of the ror review and approval of corrective actions, as specified in Section 5.3.1.3c.

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

to the NRC in accordance with Section 5.7.2.

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 No. 47 N

provisions of Sections 301, 302, 306, and 307 of the FWPCA. Section 401 of PL 92-500 further requires that any certification provided under this section shall set forth any effluent limitat. ions and other limitations and monitoring requirements necessary to assure that any applicant for a Federal license or permit will comply with the applicable limitations.

Certifications provided in accordance with Section 401 set forth conditions on the Federal license or permit for which the certification is provided.

Accordingly, the licensee shall comply with the requirements set forth in the currently applicable 401 certification and amendments 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 FWPCA and the rules and regulations promulgated pursuant to each of these acts, the Georgia Environmental Protection Division, under authority delegated by the U. S. EPA, issued NPDES Permit No. GA 0004120 to the licensee.

Tne NPDES permit authorizes the licensee to discharge from HNP Units 1 and 2 to the Altamaha River in accordance with effluent limitations, monitoring requirements, and other conditions stipulated in the

permit, effective August 1,

1983, through December 5, 1987

. Subsequent revisions to the certifications will be ac.wmdated in accordance with the provisions of Section 5.7.3.

5.6 _ Procedures Detailed written procedures, including applicable check lists and instructions, shall be prepared and followed for all activities involved in implementing the ETS.

Procedures shall apply to sampling, data 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 frecuency of any alarm shall be included. These frecuencies shall 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 end in other such areas of interface with the above proceoures.

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

Procedures which are the responsibility of the General l

Manager-Plant Hatch shall be kept at the plant. Procedures which are the I

responsibility of the Manager of Environmental Affairs and the Manager-Nuclear Engineering and Chief Nuclear Engineer shall be kept at l

the GPC General Office.

5.6.1 Environmental Procrams Description Document Based on these procedures, the licensee shall prepare and follow l

an environmental program description document (EPDD) describing the monitoring programs that are required by Sections 3.1 and 4.1.

' Itis document shall include descriptions of sampling equipnent locations, frequencies and number of replications, sample analyses, data recording and storage, and instrument calibrations where appropriate.

5-4 Amendment No. 47

s These program ' descriptions shall be approved by the NRC, and subsequent modifications to these programs shall be made by the licensee in accordance with Sections 5.6.4 and 5.6.5.

5.6.2 Quality Assurance of Procram Results Procedures shall be established to assure the quality of ETS program results, including analytical measurements.

These procedures shall document the program in policy directives, designate responsible-organizations or individuals, describe purchased services (e.g.,

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

5.6.3 Conoliance with Procedures In addition to the procedures soecified in Section 5.6, the station operating procedures shall include provisions to ensure that each Unit and all its systems and components are operated in compliance with the

~ conditions established in the ETS.

.5.6.4 Chances in Procedures, EPDD, and Station Desian cr Ooeration Changes in the procedures, EPDD, and station design or operation may be made in accordance with Section 5.3 and suject to the conditions described below:

a.

The licensee may (i) make changes in the stations design and operation; (ii) make changes in the EPDD developed in accordance with Section 5.6.1; and (iii) conduct tests and experiments not described in the EPDD without prior NBC approval, unless the proposed change, test, or experiment involves either a change in the objectives of the ETS, an unreviewed environmental question of substantive inpact, or affects the requirements of Section 5.6.5.

b.

A proposed charge, test, or experiment shall be deemed to involve an unreviewed environmental question if it concerns (i) a matter which may result in a significant increase in any adverse envirornental inpact previously evaluated in the final environmental statement, as modified by staff's testimony at the hearing, supplements thereto, environmental impact appraisals, or in initial or final adjudicatory decisions; or (ii) a significant 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 environmental impact.

5-5 Amendment tio. 47

1

c. The licensee shall maintain records of changes to EPDD and to facility design or operation made pursuant to this section.

The licensee also shan 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 ETS, or does not affect the requirements of Section 5.6.5.

The licensee shall furnish to the NBC, annuany or at such shorter intervals as may be specified in the licen'se, a

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

d. Changes in the EPDD which affect sampling frequency, location, gear, or replication shall be reported to the NRC within 30 days after their implementation, unless otherwise reported in accordance with Section 5.7.3.

Changes which affect sampling technique or data recording and storage shan be reported to the NBC at the end of the year. These reports shan provide a description of the changes made, the reasons for making the changes, and an evaluation of the environmental inpact of these changes.

e. Proposed changes or modifications to plant systems or

_equipnent shall be reviewed in accordance with Section 5.3.

f.Prchosed changes to procedures for implementing the responsibilities specified in Section 5.1.1 shan be reviewed 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 documented and subsequently reviewed by the PRB and approved by the.

N General Manager-Plant Hatch on a timely basis.

g. Proposed changes to procedures for implementing the responsibilities specified in Section 5.1.2 shall be reviewed by the staff of Environmental Affairs.

Such proposed changes shall subsequently be reviewed and approved by the Manager of Environmental Affairs.

Proposed changes 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.

T@en deemed appropriate by the Manager of Environmental Affairs or the Manager-Nuclear Engineering and Chief Nuclear Engineer, such proposed changes also shall be reviewed by the SPB prior to implemenation.

5-6 Amendnent flo. 47 4+,

=me.

e

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

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

a.

Prompt Reoort - Those events requirirg prompt reports shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone, telegraph, or facsimile transmission, and followed within 10 days by a written report.

b.

Thirty Day Report - Nonroutine events not requiring a prompt report, as described in Section 5.7.2a, shall be reported to NRC either (i)' within 30 days of their occurrence; or (ii) within the time limit designated in the appropriate specification; or (iii) within the time limit specified by the reporting regairement of the corresponding certification or permit issued pursuant to Section 401 or 402 of PL 92-500.

The report submitted to NRC in accordance with (iii) of this paragraph will consist of a copy of the report made to the Georgia Department of Natural Resources, Envirorsnental Protection Division.

Written

. reports and, to the extent possible, preliminary l

telephone, telegraph or facsimilie reports shall (i) describe, analyze, and evaluate the occurrence, including the extent and magnitude of the impact; (ii) describe the cause of the occurrence; and (iii) indicate corrective action (includirg arry significant charges made in ' procedures) taken to preclude recurrence and to prevent similar occurrences involving similar components or systems.

l l

5.7.3 Charnes in Environmental Technical Specifications and Permits 5.7.3.1 cnarnes in Environmental 'Iwennical soecifications t

Request for changes in EIS shall be subnitted to the NRC t

for review and authorization in accordance with 10 CFR l

50.90.

The request shall include an evaluation of the

~

environmental impact of the proposed change and a l

supporting justification.

Implementation of such requested enarges in EIS shall not connence prior to incorporation by the NRC of the new specifications in the).icense.

Proposed charges to the EIS shall be reviewed and approved by the Manager of Environmental Affairs, the PRB and the SRB.

Proposed charges to Section 3.2 also r

l will be reviewed and approved by the Manager-Nuclear l

Ergineering and Chief Nuclear Ergineer.

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

'It avoid conflicts and to maintain consist'ency between the safety and environmental aspects of plant operation, proposed changes to section 2 will be reviewed in the same manner as proposed changes to the Safety Technical Specifications.

5-9 Amendment No. 47

EXEClITI C VICE PRESIDFNr F0WIR SUPPLY GENIRAL >RN%btH QUALITY ASSURANCE SAltlY REVIEW AND RADIOLOGICAL IIEAL1116 SAFETY BOARD (SRB) 7FCE PRESIDEb TTNGINEBilNT SENIOR VIC3 PRESIDENT AND CONSTRUCTION SERVICES NUCLEAR F0WER VICE PRESIDENT AND VICE PRESII)lNT AND CIIIEF~

GENIRAL FMNAGDI ENGINEER POWER SUPPLY NUCLEAR OPERATIONS ENGINEERING AND SERVICES MANAGIR NUCLEAR MANAGIR NUCLEAR 8

ENGINElRING AND CIIEF OIINISTRY AND a BRNAGER OF NUCLEAR ENGINEER llEAL111 111YSICS NUCl.FAR GENERATION I

GENERAL 6MNAGIR bnNAGER OF PIANT IIATOI ENVIRONhfENTAL AFFAIRS u.

DI REVIEW

~

BOARD (PRB)

]

g a CURPRrrLY VACANT ORGANIZATION STRUCI11RE RELATED g

TO ENVIR0telENTAL ACTIVI;. RIES B-g FIQJRE 5.2-1 n

E c

se,

v t e Letter Sequence Other
TAC:49076, (Open) TAC:49077, (Open) TAC:49706, (Open)
Initiation Request, Request, Request, Request, Request, Request Acceptance... Administration Questions Answers Results Approval Other: ML20055A326, ML20083D696, ML20084F583, ML20084F601, ML20128L194
MONTHYEAR1983-12-20 [Table View]

ML20128L194

Text

Attachment:

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