ML17326B092

Proposed NUREG-0737 Tech Specs,Per Generic Ltr 82-16

ML17326B092
Person / Time
Site:	Cook
Issue date:	04/08/1983
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17326B091	List: ML17326B090 ML17326B092
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-16, NUDOCS 8304150328
Download: ML17326B092 (9)

Text

6.0 ADMINISTRATIVE CONTROLS 6 .1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsi-bility during his absence.

6.2 ORGANIZATION OFFSITE 6 .2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6 .2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Operator shall be in the contx'ol room when fuel is in the reactor.

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

d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

e. ALL CORE ALTERATIONS after the initial fuel loading 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 site Fire Brigade of at least 5 members shall be maintained onsite at all times. The fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

g. The amount of overtime worked by plant staff membex's performing safety-related functions must be limited in accordance with NRC Policy Statement on working hours (Generic Letter No. 82-12).

D. C. COOK UNIT 1 6-1 Amendment No.

8304150328 830408 PDR ADOCK 05000315 P PDR

ADMINISTRATIVE CONTROLS 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months follow--

ing initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test .program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS 6 .9.1.4 Annual reports covering the activities of the unit as described below 'for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

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) receiv-ing exposure greater than 100 mrem/yr and their rem exposure according to work and ) ob junctions, reactor operations and surveillance, inservice inspection,

'.g.,

assorted man 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 received from external sources shall be assigned to specific, major work functions.

b. The complete results of steam generator, tube inservice inspec-tions performed during the report period (reference Specifica-tion 4.4.5.5.b) .

C ~ Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves 1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

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

D. C. COOK - UNIT 1 6-15 Amendment No.

ADMINISTRATIVE CONTROLS

d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% k/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5X k/k; or occurrence of any unplanned criticality.

e. Failure or malfunction of one or more components which prevents or could prevent, by. itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the SAR.

Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR.

ge 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.

F 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 specification 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.

Failure of the pressurizer PORVs or safety valves.

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, D. C. COOK - UNIT 1 6-17 Amendment No.

Attachment 3 to AEP:NRC:0744 Changes to Unit 2 Technical Specifications 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this respon-sibility during his absence.

6.2 ORGANIZATION OFFSITE 6 .2.1 The offsite organization for facility management and technical support shall be as shown in Figure 6 .2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Operator shall be in the control room when fuel is in the 'reactor.

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

d. An individual qualified in radiation protection procedures shall be on site when fuel is in the 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 site Fire Brigade of at least S members shall be maintained onsite at all times. The Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shut-down of the unit or any personnel required for other essential functions during a fire emergency.

g. The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12) .

.D. C. COOK - UNIT 2 6-1 Amendment No.

ADMINISTRATIVE CONTROLS power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year-. The initial report shall be submitted prior to March 1 of the year following initial criticality.

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 man rem exposure according to work and gob functions, associated 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.

b ~ The complete results of steam generator tube inservice inspections performed during the report period (reference Spec"fication 4.4.5.5.b).

C ~ Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

1 4 A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

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

D. C. COOK UNIT 2 6-15 Amendment No.

ADMINISTRATIVE CONTROLS

d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% 4 k/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the'technical specifica-tions; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5%4k/k; or occurence of any unplanned criticality.

e. Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the SAR.

f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR.

g. Conditions arising from natural or manmade 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 specifica-tions that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

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 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.

Failure of the pressurizer PORVs or safety valves.

THIRTY DAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of writ-ten reports to the Director of the Regional Office within thirty days of D. C. COOK UNIT 2 6-17 Amendment No.

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