ML20153E907

Proposed Tech Spec Changes,Modifying Offsite Organization & Responsibilities of Plant Review Board,Reflecting Addition of Primary Meteorological Tower & Clarifying Retention Period for QA Documents

ML20153E907
Person / Time
Site:	Hatch
Issue date:	02/17/1986
From:	GEORGIA POWER CO.
To:
Shared Package
ML20153E905	List: ML20153E899 ML20153E907
References
TAC-60982, TAC-60983, TAC-61637, TAC-61638, NUDOCS 8602250197
Download: ML20153E907 (29)

Text

_ _ _ _ _

6.0 ADMINISTRATIVE- CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager-Plant Hatch shall be responsible for' overall unit operation, except for the Radiological Environmental Monitoring Program as described below and for delegatiori in writing of the succession of responsibility during his absence.

6.1.2 The Manager Radiological Safety shall be responsible for the Radiological Environmental Monitoring Program as described in the Specification 3/4.16 of Unit 1 and for the writing of the Annual Radiological Environmental Surveillance Report. The Manager Radiological Safety shall review the proposed changes to plant systems or equipment, provided that such changes are identified by the Plant Review Board (PRB) as having a potential radiological environmental impact.

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

6.2 ORGANIZATION 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 Operators shall be in the control room for each reactor containing fuel,

c. At least two licensed ~ 0perators 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.

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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 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 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager of Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55.

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

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)

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 PRB shall be composed of the Chairman (*) General Manager-Plant Hatch Member Deputy General Manager Member Superintendent of Operations l Member Superintendent of Instrument and Controls 3 Member Health Physics Superintendent Member Superintendent of Quality Control Member Superintendent of Plant Engineering and Services Meaber Superintendent of Regulatory Compliance Member (Non-Voting) Representative of Site Quality Assurance General Manager-Plant Hatch to designate chairman from l voting PRB 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.

HATCH - Unit 1 6-6

ADMINISTRATIVE CONTROLS-MEETING FREQUENCY 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.

QUORlN 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 four members including alternates.

RESPONSIBILITIES 6.5.1.6 The' Plant Review Board shall be responsible for:

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

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

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

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

e. Investigation of all reportable violations of the Technical l Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President and General Manager Nuclear Operations and to {

the Safety Review Board (SRB).

f. Review of events requiring written notification to the Commission per the Technical Specifications and/or reporting requirements of -

10 CFR 50.73.

g. Review of unit operations to detect potential nuclear safety hazards,

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the General Manager-Plant Hatch or- i the SRB.

HATCH - UNIT 1 6-7

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ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

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

k. Review of any unplanned onsite release of radioactive material to the environs when such release is in excess of 1 Ci, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for gaseous effluents. Also included is the preparing and forwarding to the General Manager-Plant Hatch and the SRB reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence.

1. Review of changes to the PROCESS CONTROL PROGRAM and the 0FFSITE 00SE CALCULATION MANUAL (00CM), except for the section on the Radiological Environmental Monitoring Program in the ODCM.

m. Review of proposed change (s) to plant systems and equipment to determine whether the proposed change has a potential radiological environmental impact. Such change (s) will be reported to the Manager-Radiological Safety. I AUTHORITY 6.5.1.7 The PRB shall:

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

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i RECORDS '

6.5.1.8 The Plant Review Board shall maintain written minutes of each PRB meeting that, at a minimum, document the results of all PRB activities i performed under the responsibility and authority provisions of these Technical Specifications. Copies shall be provided to the Vice President and General Manager Nuclear Operations and the Safety Review Board.  !

HATCH - UNIT 1 6-8

ADMINISTRATIVE CONTROLS

k. The Radiological Environmental Monitoring Program and the results thereof annually.

1. The ODCM, PCP, and implementing procedures biennially.

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

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

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

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

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

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

b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PRB and submitted to the SR8 and the Vice President and General Manager Nuclear Operations.

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

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

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

HATCH - UNIT 1 6-12

ADMINISTRATIVE CONTROLS SAFETY LIMIT' VIOLATION (Continued)

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRB. This report shall describe (1) applicable 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 Vice President and General Manger l Nuclear Operations 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. Security Plan implementation,

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation

h. OFFSITE DOSE CALCULATION MANUAL implementation 6.8.2 Each procedure of 6.8.1 and other procedures which the General Manager - Plant Hatch has determined to affect nuclear safety, and changes thereto, shall be reviewed by the PRB and approved by the appropriate member of plant management, designated by the General Manager - Plant Hatch, prior to implementation. The General Manager -

Plant Hatch will approve administrative procedures, security plan implementing procedures, emergency plan implementing procedures and changes thereto. All other procedures of this specification and changes thereto will be approved by the department head designed by the General Manger - Plant Hatch. The procedures of this specification shall be reviewed periodically as set forth in administrative procedures.

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

a. The intent of the original procedure is not altered.

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

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

writing by the General Manager - Plant Hatch, or his: designee as3 assigned by 6.8.2, within 14 days of-implementation.

l 6.8.4 Proposed - changes to procedures for implementing - the ' responsibilities' specified in section 6.1.2 shall be reviewed and approved by the Manager

. Radiological Safety or his designee. . When deemed appropriate by the Manager Radiological Safety, such proposed changes shall also be reviewed by the Safety Review Board prior to implementation.

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5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 3.11-1.

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

l 5.2 CONTAIPNENT C0tFIGURATION 5.2.1 The primary containment is a steel structure composed of a series of vertical right cylinders and truncated cones which form a drywell. This drywell is attached to a suppression chamber through a series of vents. The suppression chamber is a steel pressure vessel in the shape of a torus. The primary containment has a total minimum free air volume of 255,978 cubic feet.

DESIGN TEMPERATURE Af0 PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:

a. Maximum design internal pressure 56 psig.

b. Maximum allowable internal pressure 62 psig.

c. Maximum internal temperature 3400F.

d. Maximum external pressure 2 psig.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The initial core shall contain 560 fuel assemblies with each fuel assembly containing 62 fuel rods and 2 water rods clad with Zircaloy -2.

Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of 3341 grams uranium. The initial core loading shall have a maximum average enrichment of 1.87 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum average enrichment of 2.90 weight percent U-235. 7X7 fuel containing 49 fuel rods and no water rods may also be inserted.

HATCH - UNIT 2 5-1 h

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DESIGN FEATURES CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 137 control rod assemblies each consisting of a cruciform array of stainless steel tubes containing 143 inches of Baron Carbide, B4C, powder surrounded by a cruciform shaped stainless steel sheath.

5.4' REACTOR COOLANT SYSTEM DESIGN PRESSURE AW TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

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

b. For a pressure of 1250 psig, and

c. For a temperature of 575 0F.

VOLLNE 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 17,050 cubic feet at a nominal Tave of 5400F.

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

5.6 FUEL STORAGE CRITICALITY 5.6.1 The new and spent fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assemblies placed with the storage racks to ensure a kerr ecuivalent to 0.95 when flooded with unborated water. The ke rr of 0.95 includes conservative allowances for uncertainties.

HATCH - UNIT 2 5-3 L j

2 6.0 ADMINISTRATIVE CONTROLS-6.1 RESPONSIBILITY' 6.1.l' The General Manager-Plant Hatch shall be responsible for overall unit operation, except for the Radiological . Environmental Monitoring Program as l described below and for delegation in writing of the succession of a responsibility during his absence.

6.1.2 The Manager Radiological > Safety shall be responsible for the Radiological Environmental Monitoring Program as described in .the Specification 3/4.16 of Unit 1 and for the writing of the Annual Radiological Environmental Surveillance Report. The Manager Radiological Safety shall review the proposed changes to plant systems or equipment, provided that such changes are identified by the Plant Review Board (PRB) as having a potential' radiological environmental impact.

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

6.2- ORGANIZATION 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 Operators shall be in the control room for each reactor containing fuel.

c. At least two licensed Operators shall- be present in the control room for each reactor in the process of . start-up, ..aeduled 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.

HATCH UNIT 2 6-1

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6.3 -UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall neet 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 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager of Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55.

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

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)

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 PRB shall be composed of the Ch airman (*) General Manager-Plant Hatch Member Deputy General Manager Member Superintendent of Operations Member Superintendent of Instrument and Controls l Member Health Physics Superintendent Member Superintendent of Quality Control Member Superintendent cf Plant Engineering and Services Member Superintendent of Regulatory Compliance Member (Non-Voting) Representative of Site Quality Assurance General Manager-Plant Hatch to designate chairman from voting PRB 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.

HATCH - Unit 2 6-5 .

ADMINISTRATIVE CONTROLS MEETING-FREQUENCY 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.

QUORUM 6.5.1.5 The minimum quorum of the PRB necessary for the performance.of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or designated chairman and four members including alternates.

RESPONSIBILITIES ,

6.5.1.6 The Plant Review Board shall be responsible for:

a. Review of al'1 procedures required b'y SpecificatNon 6.8 and changes thereto, except those for the Radiological Environmental Monitoring Program, any other proposed procedures or changes thereto as determined by the General Manager --P1 ant Hatch to affect nuclear safety.

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

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

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

e. Investigation of all reportable violations of the Technical l Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President and General Manager Nuclear Operations and to the Safety Review Board (SRB). l

f. Review of events requiring written notification to the Commission per the Technical Specifications and/or reporting requirements of 10 CFR 50.73.

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

h. Performance of special reviews,- investigations or analyses _ and reports thereon as requested by the General Manager-Plant Hatch or-the SRB.

HATCH - UNIT 2 6-6

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

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

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

k. Review of any unplanned onsite release of radioactive material to the environs when such release is in excess of 1 Ci, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 Ci of noble gases or 0.02 Ci of radiciodines for gaseous effluents. Also included is the preparing and forwarding to the General Manager-Plant Hatch and the SRB reports covering evaluation, recomendations and disposition of the corrective action to prevent recurrence.

1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL (00CM), except for the section on the Radiological Environmental Monitoring Program in the ODCM.

m. Review of proposed change (s) to plant systems and equipment to determine whether the proposed change has a potential radiological environmental impact. Such change (s) will be reported to the g Manager-Radiological Safety, i AUTHORITY 6.5.1.7 The PRB shall:

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

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President and General Manager Nuclear Operations and the Safety Review Board of disagreement between the PRB and the General Manager-Plant Hatch; l 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 Vice President and General Manager Nuclear Operations and the Safety Review Board.

HATCH - UNIT 2 6-7 I

ADMINISTRATIVE CONTROLS

k. The Radiological Environmental Monitoring Program and the results thereof annually.

1. The ODCM, PCP, and implementing procedures biennially.

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

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

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

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

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following acticas shall be taken for REPORTABLE OCCURRENCES.

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

b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission snall be reviewed by the PRB and submitted to the SRB and the Vice President and General Manager Nuclear Operations.

l 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 SHUTDOWN within two hours.

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

HATCH - UNIT 2 6-11

ADMINISTRATIVE CONTROLS SAFETY-LIMIT-VIOLATION (Continued)

c. A Safety Limit Violation Report shall be prepared. The report

. shall be reviewed by the PRB. This report shall describe (1) applicable 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 Commission, the SRB and the Vice President and General Manger l Nuclear Operations within 14 days of the violation. I 6.8 -PROCEDURES 6.8.-l 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. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation

h. OFFSITE DOSE CALCULATION MANUAL implementation 6.8.2 Each procedure of 6.8.1 and other procedures which the General

, Manager - Plant Hatch has determined to affect nuclear safety, and changes thereto, shall be reviewed by the PRB and approved by the appropriate member of plant management, designated by the General ~ Manager - Plant Hatch, prior to implementation. The General Manager -

Plant Hatch will ' approve administrative procedures, security plan implementing procedures, emergency plan implementing procedures and changes thereto. All other procedures of this specification and changes thereto will be approved by the department head designed by the General Manger - Plant Hatch. The procedures of this specification shall be reviewed periodically as set forth in administrative procedures.

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

a. The intent of the original procedure is not altered.

6-12 l

1

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

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

HATCH - UNIT 2 6-12a I

TABLE OF CONTENTS

-Section Page 1.0 Definitions 1-1 2.0 (Section Deleted) 3.0 Bivironmental Monitoring - Deleted 3-1 4.0 Special Surveillance and Study Activities 4-1 4.1 Erosion Control Inspection 4-1 4.2 ' Unusual or Important Events Requirements 4-1 4.3 Exceeding Limits of Other Relevant Permits 4-1 5.0 Administrative Controls 5-1 5.1 Responsibility 5 5.1.1 General Manager 5-1 5.1.2 General Manager - Quality Assurance 5-1 1 5.2 Organization 5-1 5.3 Review and Audit 5-2 5.3.1 Independent Review 5-2 5.3.2 Audit Responsibility 5-3 5.4 State and Federal Permits and Certificates 5-3 5.5 Procedures 5-3 5.5.1 Quality Assurance of Progran Results 5-4 5.5.2 Compliance with Procedures 5-4 5.5.3 Gianges in Procedures and Station Design or Operation ~ 5-4 5.5.4 NRC Authority to Require Revisions 5-6 i

m.____ _ _ _ _ __ _ _ . _ _____ _ _ _ _ _ . _ _ . _ _ _ _ . _ . . _ _ __ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ _ _ . . _ . _ _ _ _ _ _ . . _ . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . . _ _ _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _

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

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

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

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

5.1 Responsibility 5.1.1 The General Manager-Plant Hatch is responsible for the environmental monitoring programs. The General Manager-Plant Hatch is also responsible for implementing the special surveillance activities described in section 4.

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

5.2 Organization A chart showing company organization relative to environmental matters is presented in figure 5.2-1. Changes affecting company organization depicted in figure 5.2-1 will not require NRC approval prior to implementation, but such changes shall be reported to NRC.

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

a. Proposed changes to plant systems or equipment, provided I such changes are identified by the Plant Review Board (PRB) as having a potential adverse environmental impact.

b. Proposed changes to the Environmental Technical l Specifications (ETS).

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

a. Proposed changes to the EIS.

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

c. Procedures or changes hereto, which could affect the monitoring of station operation, that may be considered by the Manager of Environmental Affairs or the PRB to be appropriate for SRB review.

5.3.1.4 The FRB shall review the following:

a. Procedures for implementing the responsibilities specified in section 5.1.1 and proposed changes thereto.

b. Proposed changes to the ETS.

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

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

5.4 State and Federal Permit and Certificates Section 401 of PL 92-500, the Federal Water Pb11ution Control Act Amendments of 1972 (FWPCA), requires any applicant for a Federal license or permit to conduct any activity that may result in any discharge into provisions of Sections 301, 302, 306, and 307 of the BfPCA. Section 401 of PL 92-500 further requires that any certification provided under this section shall set any effluent limitations and other limitations and monitoring requirements necessary to assure that any applicant for a Federal license or permit will comply with the applicable limitations. Certification provided in accordance with Section 401 set forth conditions on the Federal license or permit for which the certification is provided. Accordingly, the licensee shall comply with the requirements set forth in the currently applicable 401 certification and amendments thereto issued to the licensee by the Georgia Favironmental Protection Division.

In accordance with the provisions of the Georgia Water Quality Control Act, the RfPCA and the rules and regulations promulgated pursuant to each of these acts, the Georgia Environmental Protection Division, under authority delegated by the U.S. EPA, issued NPDES permit No. GA 0004120 to the licensee. We NPDES pemit authorizes the licensee to discharge from IINP 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 accommodated in accordance with the provisions of section 5.6.3.

5.5 Procedures Detailed written procedures, including applicable checklist and instructions, shall be prepared and followed for all activities involved in implementing the ETS. All procedures shall be maintained in a manner convenient for review and inspection.

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

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5.5.1 Quality Assurance of Program Results l 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, 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.

I 5.5.2 Compliance with Procedures In addition to the procedures specified in Section 5.5, the station operating procedures shall include provisions to ensure that each Unit and all its systems and commnents are operated in compliance with the conditions establisled in the Ehvironmental Technical Specifications (E15).

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5.5.3 manges in Procedures and Station Design or Operation  !

manges in the procedures and station design or operation may be l made in accordance with Section 5.3 and subject to the conditions described below: )

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

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

1. A matter which may result in a significant increase in any adverse environmental impact previously evaluated in the final environmental statement, as modified by staff's testimony at the hearing, c.upplements thereto, environmental impact

. appraisals, or in initial or final adjudicatory decisions.

2. A significant change in effluents or power level.

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

c. He licensee shall maintain records of changes to facility l

design or operation made pursuant to this section. He licensee also shall maintain records of tests and experiments carried out pursuant to paragraph (a) of this section. Rese records shall include a written evaluation which provides the bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question of substantive impact, or does not constitute a change in the objectives of the EIS. ne licensee shall l furnish to the NRC, annually or at such shorter intervals as may be specified in the license, a report containing descriptions, analyses, interpretations, and evaluations of such changes, tests, and experiments.

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

e. Proposed changes to procedures for implementing the l responsibilities specified in Section 5.1.1 shall be reviewed and approved by the Plant Review Board (PRB).

Temporary changes to the procedures that do not change the intent of the original procedure may be made with the concurrence of two members of the plant management staff, at least one of whom holds a Senior Reactor Operators license on the unit affected. Such changes shall be documented and subsequently reviewed by the PRB and approved by the General Manager-Plant Ihtch within 14 days of implementation. l 5-5

5.5.4 NRC Authority to Require Revisions l B e NRC may require modification or revision of changes made by the licensee l in accordance with section 5.5.3, as a result of NRC reviews of the results of these programs, if such modifications or revisions are judged necessary to maintain consistency with the initially approved program descriptions or with the intent of the EIS. We NRC also may require modifications or revisions because of changes in plant operation or changes in environmental l conditions or concerns associated with plant operation.

5.6 Plant Reporting Requirements 5.6.1 Routine Reports Annual Environmental Surveillance Report A report on the environmental surveillance program for the previous calendar year shall be submitted to the NRC within 90 days after January 1 of each year. H e report shall include 5-6

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

W e Annual Ehvironmental Surveillance Report also will include the following:

a. Comparison with preoperational studies, with operational controls (as appropriate), and with previous environmental monitoring reports.

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

c. A summary of:

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

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

3. Ganges in station design or operation that could I involve an environmental impact or change in the findings of the final environmental statement.

4. Ganges in the EIS. l S. Copies of all reports regarding station discharges l made in accordance with NPDES permit No GA 0004120 (and subsequent revisions); these shall include reports made in accordance with Parts IB and III of the NPDES permit.

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

Results of analysis of all nonradiological environmental data collected shall be summarized and tabulated on an annual basis. j In the event that some results are not available within 90 days after January 1, the report shall be submitted, noting and explaining the missing results. % e missing data shall be submitted as soon thereafter as possible in a supplementary report.

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e-Proposed changes to the ETS shall be reviewed and approved by the Manager-Fnvironmental Affairs, the Plant Review Board, and the Safety Review Board. Prior to approval, the possible impact of the proposed changes will be evaluated.

5.6.3.2 Changes in Permits and Certificates 01anges or additions to required Federal, State, local, and regional authority permits and certificates for the protection of the environment that pertain to the requirements of the ETS shall be reported to the NRC within 30 days. In the event that the licensee initiates or becomes aware of a request for changes to any water quality requirements, limits, or values stipulated in any certificate or permit issued pursuant to Section 401 or 402 of PL 92-500, which are also the subject of an ETS reporting requirement, the NRC shall be notified concurrently with the authorizing agency. The notification to the NRC shall include an evaluation of the environmental impact of the revised requirement, limit, or value being sought.

If, during the NRC's review of the proposed change, it is detennined that a potentially severe environmental impact could result from the change, the NRC will consult with the authorizing agency to determine the appropriate action to be taken.

5.7 Records Retention 5.7.1 Records and logs relative to the following areas shall be made and retained for the life of the plant in a manner convenient for review and inspection. These logs shall be made available to the NRC on request.

a. Records and drawings detailing plant design changes and modifications made to systems and equipment as described in section 5.5.3.

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

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

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

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