ML20083D696

Proposed Tech Specs Clarifying Organizational Changes & Shift Manning to Meet NUREG-0737 Levels

ML20083D696
Person / Time
Site:	Hatch
Issue date:	12/20/1983
From:	GEORGIA POWER CO.
To:
Shared Package
ML20083D690	List: ML20083D689 ML20083D696
References
RTR-NUREG-0737, RTR-NUREG-737 TAC-49076, TAC-49077, NUDOCS 8312280215
Download: ML20083D696 (55)

Text

F ATTACIPENP 2 NRC DOCKET 50-321 OPERATIN3 LICENSE DPR-57 EIMIN I. HATOI NUCLEAR PIANT UNIT 1 PROPOSED CHAM;E 'IO TECHNICAL SPECIFICATIONS Replace the following pages of the Unit 1 Appendix "A"

Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical lirie indicating the area of change.

Remove Page Insert Page 6-1 6-1 6-la 6-2 6-2 6-3 6-3 6-4 6-4 6-6 6-6 6-7 6-7 6-8 6-8 6-9

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6-9 6-11 6-11 6-12 6-12 6-13 6-13 6-15 6-15 6-17 6-17 6-20 6-20 6-21 6-21 I

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PDR l

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7 6.0 AINI_NISTRATIVE CONTROLS 6.1 RESPOtEIBILITY 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 OIGANIZATION 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 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 room for each reactor containing-fuel, c.

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

d.

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

All CORE ALTEPATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities durire thie, 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 or any personnel required for other essential functions during a fire emergency.

HA'ICH UNIT 1 6-1

I ADUNISTRATIVE CONTRCTE 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 operating.

However, in the event that unforeseen problems require substantial arrounts 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 <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

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

shall be reviewed monthly by the General Manager-Plant Hatch or his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

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SENIOR SENIOR VICE PREStDEN T SAFETY REVIEW TECHNICAL ENGR COtJSTRUCTION VICE PRESIDENT DOARD getpPORT

& PROJECT M ANAGER POWER GENERATION l

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GENERAL MANAGER VICE PRESIDENT POWER l.-

I VtCE PFESIDENT OUALITY ASSURANCE SUPPLY ENGINEERING AND

& GENERAL MANAGER AND RADIOLOGICAL SN MSM tb NUCLEAR GENERATION HEALTH & SAFETY I

I HATCH M AN AGER (a)

OUALITY ASSURANCE Cll!EF ENGINEER (b)

NUCLEAR GENERATION PROJECT MANAGER REVIEW

& audit

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GENERAL HATCH ENVIRONMENTAL AFFAIRS PLANT REV4W f,l AN AGER (C)

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L'NES OF RESPONSIDILITY

2. CURRENTLY VACANT

- - - -- - - - LINES OF COMMUN! CATION

b. CURRENTLY FILLED BY S AME INDIVIDU AL

c. ONSITE PERSONNEL FIGURE 6.2.1-1 OFFSITE ORGANIZATION t

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MANAGER MANAGER MANAGER MANAGER ADMINISTRATION MANAGER HEALTH PHYSICS OPERATIONS ENGINEERING MAINTENANCE FINANCE AND TRAINING

& CHEMISTRY HUMAN RESOURCES iisssuos.,

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NRC LICENSE REQUIREMENTS SRO SENIORREACTOR0PERATOR

- - - - - - LINES OF COMMUNICATION RO REACTOR 0PERATOR LINES OF RESPONSIBluTY I

N - NONE REQUIRED

• ONSITE RESPONSIBILITY FOR FIRE PROTECTION FIGURE ' 6.2.2--l UNIT ORGANT ZaTION l

TABLE 6.2.2-1 MINIMG4 SHIFT CREW COtG:OSITION#

Condition of Unit 1 - Unit 2 in Reactor Power Operation, Hot Standby or Hot Shutdown Condition LICENSE APPLICABLE CATEI3ORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL **

2 2*

OL**

3 3

I Non-Licensed 3

3 Shift Technical Advisor 1

1 N

Condition of Unit 1 - Unit 2 in Cold Shutdown Condition or Refuel Mode LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL **

2 1*

OL**

3 2

NonLicensed 3

3 shift Technical Advisor 1

None Condition of Unit 1 - No Filel in Unit 2 LICENSE APPLICABLE CATEGORf OPERATIONAL CONDITIONS 1,2,3 4&5 SQL 2

1*

OL 3

2 NonLicensed 2

3 Shift Technical Advisor 1

None

• Does not include the Licensed Senior Reactor Operator or Senior Reactor l

Operator Limited to Fuel Handling, supervisoring CORE ALTERATIONS.

l

• • Assumec each individual is licensed on both units.

1. Shift crew composition, including an individual qualified in radiation protection procedures, may be less than the minimum requirements i

for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unoxnected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.21.

PIANT HAICH UNIT 1 6-4

AIMINISTRATIVE CONTROLS 6.3 UNIT STAFF OUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except for the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the shift Technical Advisor who shall have a bachelor's degree or 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 TRAININ3 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 recomendations of Section 5.5 of. ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

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

6.5 REVIEW AND AUDIT 6.5.1 PLANP REVIEN BOARD (PRB)

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

all matters related to nuclear safety.

COMPOSITION 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 Superintendent Member:

Superintendent of Quality Control Member:

Superintendent of Plant Engineering Services Member:

Superintendent of Regulatory Compliance Member (non-voting):

Repres.entative of Site Quality Assurance

• General Manager-Plant Hatch to designate chairman from voting PRB l

membership 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.

HA'ICH - UNIT 1 6-6

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

OUORIM 6.5.1.5 The minimum quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or designated Chairman and three members l

including alternates.

RESPOEIBILITIES 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 nuclear l

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 charges or modifications to unit systems or equignent that affect nuclear safety.

e.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recomendations to prevent recurrence to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Generation and to the Safety Review Board (SRB).

f.

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

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 the SRB.

I HNICH-UNIT 1 6-7

ArNINISTRATIVE CONTROM RESIONSIBILITIES (Continued) i.

Review of the Security Plan and implementing procedures and shall subnit reconinended changes to the SRB, j.

Review of the Dnergency Plan and implementing procedures and shall submit reconinended changes to the SRB.

AUIEORITY 6.5.1.7 The PRB shall:

a.

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

b.

Render determinations in writing with regard to whether or not each item considered under

6. 5.1.6 (a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Generation 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 Specificationc. Copies shall be provided to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Generation and the Safety Review Board.

6.5.2 SAFEIY REVIBi 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 engineerirg, c.

Chemistry and radiochemistry.

HA1G - UNIT 1 6-8

NNINISTRATIVE COmROES EUNCTION (Continued) d.

Metallurgy, e.

Instrumentation and control, f.

Radiological safety, g.

Mechanical and electrical engineerirg, h.

Quality assurance practices.

COMPOSITION 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 l

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 mefrber 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.

CDNSULTANTS 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 FREQUDCY 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.

HATOI - UNIT 1 6-9

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

1.

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

2.

A total maximum combined interval time for any 3 consecutive inspection or audit intervals not to exceed 3.25 tines the specified inspection or audit interval.

These audits shall encompass:

a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b.

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

c.

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

d.

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

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

f.

The Security Plan and implementing procedures at least once per 12 l

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

l l

g.

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

or the Executive Vice President Power Supply, h.

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

l l

i.

An independent fire protection and loss prevention inspection and I

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

l j.

An inspection and audit of the fire protection and loss prevention l

program shall be performed by an outside qualified fire consultant l

at intervals no greater than 3 years.

During the year in which l

the inspection or audit occurs, the requirements of 6.5.2.8i can l

be affected concurrently.

HATCH - UNIT 1 6-11

ADMINISTRATIVE CONTROLS AUIBORITY 6.5.2.9 The SRB shall report to and advise the Executive Vice President -

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

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

6.6 REPORTABLE OCCURREICE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURREFCES.

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

to the requirements of Specification 6.9 b.

Each REPORTABLE OCCURRE?CE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Comission 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 Generation.

I 6.7 SAFETY LIMIT VIOLATION l

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

a.

The unit shall be placed in at least HOT SHUTDONN within two hours, b.

The Safety Limit violation shall be reported to the Comission, the 1

Manager Nuclear Generation or the Vice President and General l

Manager Nuclear Generation and to the SRB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l HATCH - UNIT 1 6-12 t

AEMINISTRATIVE CONTROLS SAFEIY LIMIT VIOLATION (Continued)_

c.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PRB.

This report shall describe (1) applicable circumstances preceding the violation, (2) 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 Conmission, the SRB and the Manager of Nuclear Ge eration or the Vice President and General Manager of Nuclear Genc.ation within 14 days of the violation.

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

a.

The applicable procedures reconmended in Appendix "A"

of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security Plaa implementation, e.

Emergency Plan inplementation.

f.

Fire Protection Program implementation.

i 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by I

the PRB and approved by the General Manager-Plant Hatch prior to implementation and reviewed periodically as set forth in administrative procedures.

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

i a.

The 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 License on the unit affected.

The change is documented, reviewed by the PRB and approved by the c.

General Manager-Plant Hatch within 14 days of implementation.

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HA'ICH - UNIT 1 6-13

)

4

AININISTRATIVE CONTROLS T

AINJAL REPORTS (Continued) 6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility and other personnel, including contractors, receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,2 e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

The dose assignment to. various duty functions may be estimates based-on pocket dosimeter,

TLD, or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

I l

b.

Documentation of all challenges to safety / relief valves.

i c.

Any other unit unique reports required on an annual basis.

MCNHILY OPERATItG REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall j

be subnitted on a monthly basis to the Director, Office of Management and Program Analysis, U.

S.

Nuclear Regulatory Commission, Washington, D. C.

20555, with a copy to the Regional Office of Inspection and Enforcement no later than the 15th of each month following the calendar month covered by the report.

REPORTABLE OCCURREtCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specification 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC.

Supplemental reports may be required to fully describe final resolution of occurrence.

In case of corrected or supplemental reports, j

a licensee event report shall be completed and reference shall be made to the l

original report date.

i i

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orhis taoulation supplements the requirements of 20.407 of 10 CFR Part 20.

HATCH - UNIT 1 6-15

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AININISTRATIVE CONTROL PROMPT NOTIFICATION WITH WRITTEN 10ILOWUP (Continued) 9 Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by Technical Specifications.

h.

Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

i.

Performance of structures, systems, or components which requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

i j.

Failure or malfunction of any safety / relief valve.

THIRTY DAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event *,

The written report shall include, as a minimum, a completed l

copy of a licensee event report form.

Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a.

Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

l b.

Conditions leadirg to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

c.

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in recctor protection systems or engineered safety feature systems.

• All Type B and Type C Leakage Tests (i.e., Local Leak Rate Tests) that fail (i.e., test leakage is such that an LER would be required) during an outage i

shall be reported per one thirty-day written report and shall be submitted within 30 days of the end of such an outage.

HATCH - UNIT 1 6-17 i

AININISTRATIVE CO?7fROL PECORD RETENPION (Continued) c.

Records of radiation exposure for all individuals entering raJiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.

f.

Records of reactor tests and experiments.

g.

Records of trainirg aru qualification for current members of the unit staff, h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities required by the QA

Manual, j.

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

k.

Records of meetings of the PRB and SRB.

1.

Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7.4-la and 3.7.4-lb, including the date at which the service life comences and associated installation and maintenance records.

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

6.12 HIGH RADIATION ARFA l

6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph j

20.203 (c) (2) of 10 CFR 20, each high radiation area in which the intensity of l

radiation ic greater than 100 mrent/hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requirirg issuance of a Radiation Work Permit *,

Any individual or group of individuals permitted

• Health Physica personnel, or personnel eccorted by Health Physics personnel in accordance with approved emergency procedures, shall be exempt from the RVP issuarce requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

l HA'ICli UNIT 1 6-20 L

AEf4INISTPATIVE CtNTROL to enter such areas shall be provided with or acccmpanied by one or more of the followirg, 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 perform periodic radiation surveillance at the frequency specified by the facility Health j

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 mrenVhr.

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, i

l l

l l

HA'ICH UNIT 1 6-21 l

ATr7CINENT 3 tmC DOCEP 50-366 OPERATItG LICENSE NPF-5 EDVIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHAtGE 70 TECHNICAL SPECIFICATIONS Replace the following pages of the Unit 2 Appendix "A"

Technical Specifications with the enclosed pages. The revised pages are identified by amendment ntrrber and contain a vertical line indicating the area of change.

Remove Page Insert Page 6-1 6-1 6-la 6-2 6-2 6-3 6-3 6-4 6-4 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 6-14 6-14 6-16 6-16 6-18 6-18 6-19 6-19 l

l f

6.0 AEMINISTRATIVE COVPROLS 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 responsibility durirg his absence.

6.2 OICANIZATION OFFSI7E 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:

Each on duty shift shall be composed of at least the minimum shif t a.

crew composition shown in Table 6.2.2-1.

b.

At least one licensed Operator shall be in the control room for each reactor containiry 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 Fuel Handling who has no other concurrent responsibilities durity 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 or any personnel required for other essential functions during a fire emergency.

HATO! UNIT 2 6-1

A&lINISTRATIVE CCMROLS g.

A&Tdnistrative 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 operating.

However, in the ever.t 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 <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

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

(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 i

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 designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

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HNIGI UNIT 2 6-la i

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!!ATCil - UNIT 2 6-3

TABLE 6.2.2-1 I

MINIMLM SHIFT CR_EW COMPOSITION Condition of Unit 2 - Unit 1 in Reactor Power Operation, Hot Standby or Hot Shutdown Condition LIGtE APPLICABLE CATEORY OPERATIONAL CONDITIONS 1,2,3 4&5 I

SOL **

2 2*

OL**

3 3

Non-Licensed 3

3 Shift Technical Advisor 1

1

.i Condition of Unit 2 - Unit 1 in Cold Shutdown Condition or Refuel Mode LIGIG APPLICABLE CATE OIE OPERATIONAL COtOITIONS 1, 2, 3 4&5 SOL **

2 1*

OL**

3 2

l NonLicensed 3

3 Shift Technical Advisor 1

None Condition of Unit 2 - No Fuel in Unit 1 LICENSE APPLICABLE i

CATEGORY OPEPATIONAL CONDITIONS 1,2,3 4&5 SOL 2

1*

OL 3

2 NonLicensed 2

3 Shift Technical Advisor 1

None

• Does not include the Licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervisoring CORE ALTEPATIOFS.

• • Assumes each individual is licensed on both units.

1. Shift crew composition, including an individual qualified in radiation protection procedures, may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided inmediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.21.

PIANT HA'IG UNIT 2 6-4 I

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed 'the minimum qualifications of ANSI N18.1-1971 for comparable positions except for the Health Physics Superintendent who shall meet or exceed the qualifications of l

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 sIxx:ific 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 recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

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

6.5 REVIEN AND AUDIT 6.5.1 PLANP REVIN BOARD (PRB)

FUNCTION l

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

all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Review Board shall be composed of the:

Chairman *:

General Manager-Plant Hatch Member:

Deputy General Manager Membar:

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 l

Member (non-voting):

Representative of Site Quality Assurance

• General Manager-Plant Hatch to designate chairman from voting PRB l

membership as necessary.

ALTERNATES 6.5.1.3 All alternate members shall be appointed ir writing by the PRB Chairman to serve on a temporary basis; however, to more than two alternates shall participate as voting members in PRB activities at any one time.

HA'ICH - UNIT 2 6-5

b ADMINISTI%TIVE CONTR(LS MEEfDG FRB]tEtCY 6.5.1.4 The PRB shall meet. at least once per calendar month and as convened by the PRB Chairman or his designated alternate.

QUORIM 6.5.1.5 The minimum quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or designated Chairman and three members l

including alternates.

RESPOf6IBILITIES 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 proceduren or changes thereto as determined by the General Manager-Plant Hatch to affect nuclear l

safety.

b.

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

c.

Review of all proysed changes to Appendix "A"

Technical Specifications.

d.

Review of all proposed changes or modifications to unit systems or equignent 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 Nuclear Generation and to the Safety Review Board (SRB).

f.

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

l IWIG-UNIT 2 6-6 l

I,

ADMINISTRATIVE COhrrROI.S RESPONSIBILITIES (Continued) i.

Review of the Security Plan and implementing pre cedures and shall sutmit recomended changes to the SRB, j.

Review of the Emergency Plan and implementirg procedures and shall submit recomended changes to the SRB.

AUTHORITY 6.5.1.7 The PRB shall:

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 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Generation 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 Generation and the safety Review Board.

6.5.2 SAFETY REVIEN BCARD (SRB)

FUNCPION 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 2 6-7

)

AININISTRATIVE COtTPROLS MJtCTION (Continued) d.

Metallurgy, e.

Instrumentation and control, f.

Radiological safety, g.

Mechanical and electrical engineerirg, b.

Out.lity assurance practices.

CCNPOSITION 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 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 voting privileges.

00tEULTA17PS 6.5.2.4 Consultants shall be utilized as determined by the SRB Chairman or Vice-Chairman to provide expert advice to the SRB.

MEETItG FREQUEtCY 6.5.2.5 The SFB 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.

HNICII - UNIT 2 6-8

l I

AENINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the SRB. Each inspection or audit shall be performed within the specified time interval with:

1.

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

2.

A total maximum combined interval time for any 3 consecutive inspection or audit intervals not to exceed 3.25 times the specifid inspection or audit interval.

These audits shall encompass:

a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months, b.

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

c.

The results of actions taken to correct deficiencies occurring in 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 implementing procedures at least once per 12 months shall be performed by individuals who have no direct responsibility for implementation of this plan, f.

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

g.

Any other area of unit operation considered appropriate by the SRB or the Executive Vice President Power Supply.

I h.

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

i.

An independent fire protection and loss prevention inspection and aciit shall be performed annually utilizing either qualified oftsite 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 6.5.2.8i can be affected concurrently.

4 HA'ICH - UNIT 2 6-10

AININISTRATIVE CONPPOLS i

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

l 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 I

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 I

forwarded to the Executive Vice President-Power Supply and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REFORTABLE OCCUFREICE ICTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURPEICES.

a.

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

Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Comnission 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 Generation.

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

a.

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

b.

The Safety Limit violation shall be reported to the Commission, the l

Manager Nuclear Generation or the Vice President and General Manager Nuclear Generation and to the SRB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

HA'ICH - UNIT 2 6-11 j

i ADMINISTRATIVE CON 1'ROLS SAFETY LIMIT VIOIATION (Continued) c.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PRB.

This report shall describe (1) applicable circumstances preceding the violation, (2) 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 Comission, the SRB and the Manager of Nuclear Generation or the Vice President and General Manager of Nuclear Generation within 14 days of the violation.

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

a.

The applicable procedures recommended in Appendix "A"

of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Eecurity Plan implementation, e.

Emergency Plan implementation, f.

Fire Protection Program implementation.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PRB and approved by the General Manager-Plant Hatch prior to implementation I

and reviewed periodically as set forth in administrative procedures.

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

1 a.

The intent of the original procedure is not altered.

l 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 documented, reviewed by the PRB and approved by the General Manager-Plant Hatch within 14 days of implementation.

I HA1CH - UNIT 2 6-12

_.__-~.

_AENINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) 6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility and other personnel, including contractors, receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,2 e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter,

TLD, or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions, I

b.

Documentation of all challenges to safety / relief valves.

c.

Any other unit unique reports required on an annual basis.

MOU1HLY OPERATIIG REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.

S.

Nuclear Regulatory Commission, Washington, D. C.

20555, with a copy to the Regional Office of Inspection and Enforcement no later than the 15th of each month following the calendar month covered by the report.

REPORTABLE CCCURREtCES 6.9.1.7 The REPORTABLE OCCURREFCES of Specification 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NPC.

Supplemental reports may be required to fully describe final resolution of occurrence.

In case of corrected or supplanental reports, a licensee event report shall be completed and reference shall be made to the original report date.

2 nis tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

T HA'ICH UNIT 2 6-14 l

1

ADMINISTRATIVE COm'ROL PROMPP NorIFICATION WI7H WRITTEN FOLINUP (Continued) g.

Conditions arising from natural or man-made events that, as a direct result of the event, require unit shutdown, operation of safety systems, or other protective measures required by technical specifications.

h.

Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation.in a manner less conservative than assumed in the analyses, i.

Performance of structures, systens, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

j.

Failure or malfunction of any safety / relief valve THIRTY DAY WRI7 TEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event *.

The written report shall include, as a minimum, a completed I

copy of a licensee event report form.

Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a.

Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

b.

Conditions leadirg to operation in a degraded mode permitted by a limitirg condition for operation or plant shutdown required by a limiting condition for operation.

c.

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

• All Type B ano Type C Leakage Tests (i.e., Local Leak Rate Tests) that fail (i.e., test leakage is such that an LER would be required) during an outage shall be reported per one thirty-day written report and shall be submitted within 30 days of the end of such an outage.

HA7CH UNIT 2 6-16

= _ _ - _ _ _

AININISTRATIVE CONIROL RE00PD RETENPION (Continued) 4 c.

Records of radiation exposure for all individuals entering radic. tion control areas.

d.

Records of gaseous and liquid radioactive material released to the

environs, e.

Records of transient or. operational cycles for those unit components identified in Table 5.7.1-1.

c f.

Records of reactor tests and experiments, g.

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

~

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities required by the QA Manual.

j.

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

k.

Records of meetings of the PRB and SRB.

Q l.

Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7.4-la and 3.7.4-lb, including the date at which the service life commences and associated installation and 1

maintenance records.

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

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrenVhr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted i

• Health Physics personnel, or personnel escorted by Health Physics personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection l

procedures for entry into high radiation areas, j

HA1G UNIT 2 6-18 l

l l

NEINISTRATIVE COM'ROL to enter such areas shall be provided with or accompanied by one or more of the followirg.

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 perform periodic radiation surveillance at the frequency specified by the facility Health Physics supervision in the Padiation Work. Permit.

l 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 mrenVhr.

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.

HATCH UI:IT 2 6-19

ATTACHMENT 4 NBC DOCKETS 50-321, 50-366 OPERATIFG LICENSES DPR-57, NPF-5 EDWIN I.' HATCH NUCLEAR PLANT UNITS 1 AND 2 PROPOSED CIIAFGE 10 ENVIROtNENTAL TECHNICAL SPECIFICATIONS Replace the follwing 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 Page Insert Page 5-1 5-1 5-2 5-2 5-3 5-3 s'

5-4 5-4 5-5 5-5 5-6 5-6 5-9 5-9 5-11 5-11 i

l l

l l

l l

5.0 Administrative 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 INS 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 ccepliance with the ETS and for the environmental monitorirg program required by the ITS 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 l

Radiological Health and Safety.

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

plant effluents; for operating the plant within the Limiting Con:litions for Operation (LCOs) 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 Environmental 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 Engineerirg and Chief Nuclear Engineer by Section 5.

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

5.1.3 The Manager-Nuclear Engineering and Chief Nuclear Engineer is I

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

5.1.4 The General Manager of Quality Assurance and Radiological Health I

and Safety is responsible for conductirg periodic audits of plant operations and the environmental monitoring activities to ensure conformance with the ETS.

5.2 Organization A chart showire company organization relative tc environmental matters is presented in Figure 5.2-1.

Changes affecting company organization depicted in Figure 5.2-1 will.not require NFC approval prior to implementation, but such changes shall be reported to NRC within 30 days in accordance with Section 5.7.2 5-1 p-c -ee e e ve& -- -..

.~#

. se

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 HIP is operated in compliance with the Iros specified in Section 2.

5.3.1.2 The Manager of Environmental Affairs shall review the following:

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

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

potential adverse environmental impact.

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

a. Proposed changes to the Ers.

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

c. Violations of EIS 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 Ecard to be appropriate for SRB review.

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

a. Proposed changes to plant systems or equipnent.

5-2

i

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

Engineer shall review the following:

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

4

b. Proposed changes to Section 3.2 of the ETS.

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 Manager-Plant Hatch, the Manager of Environmental

Affairs, and the Manager-Nuclear Engineering al.3 Chief Nuclear Engineer related 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 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 ETS, shall be taken until the ICO can be achieved.

l 5.4.2 Violations of an ICO will be reported immediately to the General l

Manager-Plant Hatch.

5.4.3 A separate report of each ICO 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 Generation, the Manager of Environmental

Affairs, the Manager-Nuclear Engineering and Chief Nuclear Engineer, 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 to I

the NBC 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

provisions of Sections 301, 302, 306, and 307 of the IWPCA.

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 l 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.

The 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 acconmodated 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, datr_

recording and storage, instrument calibration, measurement and data recording and storage, instrument calibraton, measurement and analysis, and actions to be taken when limits are approached or exceeded.

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.

All procedures shall be maintained in a manner convenient for review and 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 Environmental Programs Description Document Based on these procedures, the licensee shall prepare and follow an environmental program description document (EPDD) describing the monitoring programs that are required by Sections 3.1 and 4.1.

This 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

-_-_-_-___-________-___Y

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 Program 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 Conpliance 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 E7S.

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

which may result in a significant increase in any adverse environmental impact previously evaluated in the final l

environmental statement, as modified by staff's testimony at the i

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 l

(i) of this paragraph which may have a signific' int adverse environmental impact.

l 5-5 i

i

... ~.

_.c.

y x _

I

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

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 rot affect the requirements of Section S.6.5.

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

license, a

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

.F

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 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 impact of these changes.

i

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

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

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 I

by the staff of Environmental Affairs.

Such proposed changes L

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

Proposed changes to procedures for implementing the responsibilitien specified in Section 5.1.3 shall be reviewed by the staff of the Manager-Nuclear l

Engineering and Chief Nuclear Engineer.

Such proposed changes shall subsequently be reviewed and approved by the Manager-Nuclear Engineering and Chief Nuclear Engineer.

When deemed appropriate by the Manager of Environmental Affairs or l

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

l l

5-6 1

(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 prompt reports shall be reported within 24 nours by telephone, telegraph, or facsimile transmission, and followed within 10 days by a written report.

b.

'Ihirty 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 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, Environmental Protection Division.

Written Reports

and, to the extent

possible, preliminary telephone, telegraph or facimilie reports shall (i) describe, analyze, and evaluate the occurrence, including the extent and magnitude of the impact; (if) describe the cause of the oo:urrence; and (iii) indicate corrective action (including any significant chames made in procedures) taken to proclude recurrence and to prevent similar occurrences involving similar camponents or systems.

5.7.3 Charges in Environmental Technical Specifications and Permits 5.7.3.1 Chames in Environmental Technical Specifications Request. for changes in ETS shall be submitted to the NRC fro review and authorization in accordance with 10 CFR 50.90.

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

Implementation of such requested charges in ETS shall not commence prior to incorporation by the NRC of the new specifications in the license.

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

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

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

'Ib avoid conflicts and to maintain consistency 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

.w m

(T EXECUTIVE VICE PRESIDENT POWER SUPPLY SAFETY REVIEW GENERAL MANAGER OUALITY

. ASSURANCE AND RADIOLOGICAL BOARD (SRB)

HEALTH & SAFETY SENIOR SENIOR VICE PRESIDENT m

VICE PRESIDENT ENGR CONSTRUCTION POWER GEllERATION

& PROJECT MANAGER 1

VICE PRESIDENT VICE PRESIDENT POWER l

& GErJERAL MAf1AGER SUPPLY ENGINEERING NUCLEAR GENERATION AND SERVICES (b)

M AN AGER - NUCLE AR ENGINEERING AND I

CHIEF NUCLE AR ENGINEER MANAGER NUCLEAR GENERATION (a)

CHIEF ENGINEER (b)

GENERAL MANAGER MANAGER PLANT HATCH ENVIRONMENTAL AFFAIRS mennn

1. ~

^^

I PLANT REVIEW

b. CURRENTLY FILLED BY SAME INDIVIDUAL BOARD (PRB) j FIGURE 5.2-1 t

ORGANIZATIONAL STRUCTURE RELATED TO ENVIRONMENTAL ACTIVITIES I

i 4

A'ITACENENP 5 NFC DOCKETS 50-321, 50-366 OPERATI1G LICENSES DPR-57, l@F-5 EIMIN I. HA'ICH NUCLEAR PLANP UNITS 1 AND 2 PRTOSED CHA!GE 'IO RADIOII)GICAL EFFLUENP TECHNICAL SPECIFICATIONS (RETS)

Replace the following pages of the Unit 1 and 2 Section 6 Appendix "A"

Radiological Effluent 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 Page Insert Page HNP-RETS-2 HNP-RETS-2 HNP-RETS-5 HNP-RETS-5 HNP-RETS-6 HNP-RETS-6 HNP-RETS-8 HNP-RETS-8 HNP-RETS-13 HNP-RETS-13 HNP-RETS-14 HNP-8ETS-14 HNP-RETS-18 HNP-RETS-18 HNP-RETS-24 HNP-RETS-24 HNP-RETS-27 HNP-RETS-27 HNP-RETS-28 HNP-RETS-28 Replace the following pages of the Unit 1 and 2 Section 5 Appendix "B"

Radiological Effluent Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.

Renove Page Insert Page HNP-PETS-10 HNP-RETS-10

MLI,STRATIVE CONTROLS 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 Fuel 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 Team 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.

g.

Administrative procedures shall be dcveloped 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 operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used or during extended periods of autdown 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 <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

(2)

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all 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 rot 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 management, in accordance with establiched 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 designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorizc<1.

HNP-RETS-2

TABLE 6.2.2-1 (SHEEP 1 OF 3)

MINIMUM SHIPP CREW COMPOSITION 0 Condition of Unit 1 - Unit 2 in Reactor Power Operation, Hot Standoy or Hot Shutdown Condition LIGNSE APPLICABLE CATEORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL **

2 2*

OL**

3 3

I

\\

Non-Licensed 3

3 Shift Technical Advisor 1

1 Condition of Unit 1 - Unit 2 in Cold shutdown Condition or Refuel Mode LIGNSE APPLICABLE CATEORY OPERATIONAL CONDITIOtG 1,2,3 4&5 SOL *

• 2 1*

OL**

3 2

I NonLicensed 3

3 Shift Technical Advisor 1

None HNP-RETS-5

TABLE 6.2.2-1 (SHEET 2 OF 3)

MINIMIM SHIFT CREW CO(POSITION Condition of Unit 1 - No Fuel in Unit 2 LICENSE APPLICABLE CATEGORY OPERATIONAL COtOITIONS 1,2,3 4&5 SOL 2

1*

OL 3

2 NonLicensed 2

3 Shift Technical Advisor 1

None

• Does not include the Licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervisoring CORE ALTERATIONS.

• Assumes each individual is licensed on both units.

1. Shift crew composition, including an individual qualified in radiation protection procedures, may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to acconnodate unexpected absence of on duty shift crew ma, ers provided innediate action is taken to restore the shif t crew cm,sition to within the s

minimum requirements of Table 6.2.2-1.

HNP-RETS-6 m

i i

AEt!INISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for canparable positions except for the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering diecipline with specific training in plant design, and response and analysis of.the plant for transients and accidents.

6.4 TRAININ3 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager of Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 6.4.2 A training program for fire protection shall be maintained under the direction of the Senior Regulatory Specialist and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except for fire protection training sessions which shall be held quarterly.

6.5 REVI N AND AUDIT 6.5.1 PLANP REVIN BOARD (PRB)

FUNCTION 6.5.1.1 The PRB shall function to advise the General Manager-Plant Hatch on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Review Board shall be composed of the:

Chairman *:

General Manager-Plant Hatch Member:

Deputy General Manager l

Member:

Superintendent of Operations l

Member:

Superintendent of Maintenance Member:

Health Physics Superintendent Member:

Superintendent of Quality Control

• General Manager-Plant Hatch to designate chairman from voting PRB l

menbership as necessary.

HNP-RETS-8 i

AI:MINISTRATIVE CCNTROLS e.

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

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

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

h.

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

i.

Reports and meetings minutes of the Plant Review Board.

AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the SRB.

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

1.

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

2.

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

These audits shall enecmpass:

a.

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

annually, b.

The performance, training and qualifications of the unit staff annually.

l c.

The results of actions taken to correct deficiencies occurring in unit equipnent, structures, systems or method of operation that l

affect nuclear safety semi-annually.

i d.

The performance of activities required by the Operational Quality l

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

10 CFR 50, biennially.

I 1

HNP-RETS-13 i

l I

L

AEMINISTRATIVE CONTROLS e.

The Emergency Plan and implementing procedures annually shall be performed by individuals who have no direct responsibility for implementation of this plan, f.

The Security Plan and implementing procedures annually shall be performed by individuals who have no direct responsibility for l

inplementation of this plan, g.

Any other area of unit operation considered appropriate by the SRB or the Executive Vice President Power Supply, h.

The Fire Protection Program and implementing procedures biennially.

i.

An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified 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 6.5.2.8i can be affected concurrently.

k.

The Radiological Environmental Monitoring Program and the results thereof annually.

ALGORITY 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.

M RuS 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 days following each meeting.

b.

Reports of reviews enempassed by Section 6.5.2.7 above, shall be

prepared, approved and forwarded to the Executive Vice 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 management positions responsible for the areas audited within 30 days after completion of the audit.

HNP-RETS-14

AEMINISTRATIVE CONN'OLS routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling.

The dose assignment to various duty functions may be estimates baced on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20%

of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions, b.

Documentation of all challenges to safety / relief valves.

c.

Any other unit unique reports required on an annual basis.

ANNUAL RADIOIOGICAL ENVIROtNENTAL SURVEILLANCE REPORT 6.9.1.6 Routine radiological environmental surveillance reports covering the radiological environmental surveillance activities related to the plant during the previous calendar year shall be submitted prior to May 1 of each year.

A single report may fulfill this requirement for both units.

6.9.1.7 The Annual Radiological Environmental Surveillance Report shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the reporting period, including (as appropriate) a comparison with preoperational studies, operational controls, previous environmental surveillanc reports, and an assessment of ant observed impacts of the plant operation on the environment.

The reports shall also include the results of the land use surveys required by Specification 3.16.2 and the interlaboratory conparison program required by Specification 3.16.3.

The Annual Radiological Environmental Surveillarce Report shall include summarized and tabulateu results in the format of table 6.9.1.7-1 of all radiological environmental samples taken during the report period, with the exception of naturally occurring radionuclides which need not be reported.

In the event that some results are not available for inclusion with the report, the report shall be submitted, noting and explaining the reasons for the missirg results. The missing data shall be subnitted as soon as practicable in a supplementary report.

The reports shall also include the following:

a.

Summary description of the radiological environmental monitoring program b.

Map of all sampling locations as keyed to a table indicating distances and directions from the main stack.

HNP-RETS-18

)

AIMINISTRATIVE CCNTROL

)

i.

Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifimtions bases; or discovery during unit life of conditions act specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition, j.

Failure or malfunction of any safety / relief valve THIRPY DAY WRITTEN REPORPS 1

6.9.1.13 The types of events listud below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event *. The written report shall include, as a minimum, a i

completed copy of a licensee event report form.

Information provided on the 4

licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a.

Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfilknent of the functional requirements of affected

systems, i

b.

Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

]

c.

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

d.

Abnormal degradation of systems, other than those specified in 6.9.1.13 (c), designed to contain radioactive material resulting from the fission process.

6.9.2 Special reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement with in the time period specified for each report.

t B

• All Type B and Type C Leakage Tests (i.e., Local Leak Rate Tests) that fail (i.e., test leakage is such that an LER would be required) during an outage shall be reported per one thirty-day written report and shall be submitted within 30 days of the end of such an outage.

l HNP-RETS-24 1

4

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+c w.

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3 ALMINISTRATIVE CONTROL f.

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

g.

Records of in-service inspections performed pursuant to these Technical Specifications.

h.

Records of Quality Assurance activities required by the QA Manual.

i.

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

j.

Records of meetings of the PRB and SRB.

k.

Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7.4-la and 3.7.4-lb, including the date at which the service life comences and associated installation and maintenance records.

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

6.12 HIGH RADIATION ARFA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrent hr but less than 1000

/

mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *, Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following.

a.

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

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 i

monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

• Health Physics personnel, or personnel escorted by Health Physics personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

HNP-RETS-27 i

ArNINISTRATIVE CONTROL c.

An irrlividual 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 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 l

I Foreman on duty.

6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAIIMENP I

Plant Hatch shall implement a progran to reduce leakage from systems outside containment that muld or could contain highly radioactive fluids during a serious transient or accident to as low as practicable levels.

This program shall include the following:

a.

Provisions establishing preventive maintenance and periodic visual inspection requirements b.

System leak test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequercy not to exceed refueling cycle intervals. The systems subject to this testing are residual heat removal, core spray, reactor water cleanup, HICI, and PCIC.

6.14 IODINE MONI'IORItG Plant Hatch shall implement a program which will ensure the capability (a) to airborne iodine concentration in vital areas acrurately determine the under accident conditions. This program shall include the following:

a.

Training of personnel b.

Procedures for monitoring c.

Provisions for maintenanace of sampling and analysis equipment.

(a) Areas requiring personnel access for establishing HOP SHUTDOWN condition.

HNP-RETS-28

5.6.1 Environmental Programs Description Document Based on these procedures, the licensee shall prepare and follow an environmental program description document (EPDD) describing the monitoring programs that are required by Sections 3.1 and 4.1.

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

These program descriptions shall be approved by the IK, and subsequent modifications to these programs shall be made by the licensee in accordance with Sections 5.5.4 and 5.5.5.

5.6.2 Quality Assurance of Program 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 irdividuals, describe purchased services (e.g.,

contractural laboratory or other contract services), and provide for audits of results and procedures by I

licensee personnel.

In addition, these quality assurance procedures shall provide for systems to identify and correct deficiencies in technical monitoring programs or related administrative activities, to investigate anomalous or suspect results, and to review and evaluate program results.

5.6.3 Canpliance with Procedures In addition to the procedures specified in Section 5.5, 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 make changes in the stations design and operation; make charges in the EPDD developed in accordance with Section 5.5.1; and conduct tests and experiments not described in the EPDD without prior NRC approval, unless the proposed change, test or experiment involves either a charge in the objectives of the ETS, an unreviewed environmental question of substantive

impact, or affects the requirements of Section 5.5.5.

HNP-RETS-10

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