Text

Tech Spec Pages for Amendments 176 and 138 Relocate Administrative Control Requirements
	ML052080138
Person / Time
Site:	Limerick
Issue date:	07/25/2005
From:	; NRC/NRR/DLPM
To:	;
References
	TAC MC2739, TAC MC2740
	Download: ML052080138 (26)
	v • d • e

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY

............................ 6-1 6.2 ORGANIZATION..................................................... 6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATION............

................... 6-1 Figure 6.2.1-1 Deleted........................... 6-3 6.2.2 UNIT STAFF...................................................... 6-2 Figure 6.2.2-1 Deleted........................... 6-4 Table 6.2.2-1 Minimum Shift Crew Composition....................... 6-5 6.2.3 DELETED; Refer to note on page............

.................... 6-6 6.2.4 SHIFT TECHNICAL ADVISOR..................

....................... 6-6 6.3 UNIT STAFF QUALIFICATIONS........................................ 6-6 6.4 D LETED

.......................................................... 6-7 6.5 DELEIE 6.5.1 Deleted I

Deleted...................................................

6-7 6-7 6-7 6-7 6-7 6-8 6-9 I

I I

LIMERICK - UNIT 1 xxv i Amendment No. An, 31, 96, 4-60,176

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 Deleted Deleted.................................................... 6-9 Deleted.................................................... 6-9 Deleted.................................................... 6-10 Deleted.................................................... 6-10 Deleted.................................................... 6-10 Deleted.................................................... 6-10 Deleted.................................................... 6-10 Deleted.................................................... 6-12 6.5.3 Deleted.6-12 6.6 REPORTABLE EVENT ACTION

........ 6-12a 6.7 SAFETY LIMIT VIOLATION........................

6-12a 6.8 PROCEDURES AND PROGRAMS.....

............ 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS............

6-15 Startup Report............

6-15 Annual Reports.

6-15 Monthly Operating Reports.................................. 6-16 Annual Radiological Environmental Operating Report.........

6-16 Semiannual Radioactive Effluent Release Report............. 6-17 CORE OPERATING LIMITS REPORTS.............................. 6-18a 6.9.2 SPECIAL REPORTS............................................ 6-18a 6.10 DELETE........................

6-19 6.11 RADIATION PROTECTION PROGRAM.............................. 6-20 6.12 HIGH RADIATION AREA.......

.......... 6-20 LIMERICK - UNIT 1 XXvi i Amendment No. 4R, 4R, 96, 176

ADMINISTRATIVE CONTROLS 6.5 DELETED THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 1 6-7 Amendment No. 40, 3X, i-5,

.6, 4-9, 4-0, 46, 176 Correction Ltr. dAd 0/17-/95

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 1 6-8 Amendment No. 4, 47, 404, 434, 1-54,176

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 1 6 -9 Amendment No. 40, 3-s, 96, 434, 176

ADMINISTRATIVE COQIROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 1 6-10 Amendment No. 46, 176

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 1 6-12 Amendment No. -0, 4Z, 4-7, 9i6, 4-54,176

ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b.

Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the NRB, Plant Manager and the Vice President, Limerick Generating Station.

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

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The Vice President, Limerick Generating Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the NRB.

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

c.

The Safety Limit Violation Report shall be submitted to the Commission, the NRB, Plant Manager, and the Vice President, Limerick Generating Station, within the 14 days of the violation.

LIMERICK - UNIT I 6-12a Amendment No. 4X, 9F,, 4-64,176

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 cover Written procedures shall be established, implemented, and maintained ing the activities referenced below:

a.

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

b.

The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737.

c.

Refueling operations.

d.

Surveillance and test activities of safety-related equipment.

e.

Security Plan implementation.

f.

Emergency Plan implementation.

g.

Fire Protection Program implementation.

h.

PROCESS CONTROL PROGRAM implementation.

i.

OFFSITE DOSE CALCULATION MANUAL implementation.

j.

Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15, February 1979.

The information from Section 6.8.2 has been relocated to QATR.

The information from Section 6.8.3 has been relocated to QATR.

6.8.2 6.8.3 I

I LIMERICK - UNIT 1 6-13 Amendment No. 40, 4X, 996, 439, 176

ADMINISTRATIVE CONTROLS 6.10 DELETED THE INFORMATION FROM SECTION 6.10 HAS BEEN RELOCATED TO THE QATR.

LIMERICK - UNIT 1 6-19 Amendment No. 47-,176

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

6.12.1 High Radiation Areas with dose rates (deep dose equivalent) greater than 0.1 rem/hr and not exceeding 1.0 rem/hour (at 30 centimeters from the radiation sources or from any surface penetrated by the radiation):

a. Each accessible entryway to such an area shall be barricaded and conspicuously posted as a High Radiation Area.

Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

LIMERICK - UNIT 1 6-20 Amendment No. 48, 435, 176

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) a)

A health physics qualified individual (i.e.,

qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for controlling personnel radiation exposure within the area, OR b)

Be under the surveillance, as specified in the RWP or equivalent, by means of closed circuit television, of a health physics qualified individual (i.e., qualified in radiation protection procedures),

responsible for controlling personnel radiation exposure in the area, and with the means to communicate with the individuals in the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:

a.

Shall be documented with the following information:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and LIMERICK - UNIT 1 6-21a Amendment No. 413-5, 176

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

2.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective upon review and acceptance by the PORC and approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCM:

a.

Shall be documented with the following information:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2.

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective upon review and acceptance by the PORC and the approval of the Plant Manager.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE 00CM.

LIMERICK - UNIT 1 6-22 Amendment No. 45, 48, L3,176

INDEX A6OlINTSTRATIvE CONTROLS SECTION LAUE 6.1 RESPONSIBILITY.................................................. 6-1 6.2 ORGANIZATION.................................................. 6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATION

................... 6-1 Figure 6.2.1-1 DELETED........................... 6-3 6.2.2 UNIT STAFF.................................................. 6-2 Figure 6.2.2-1 DELETED........................... 6-4 Table 6.2.2-1 Minimum Shift Crew Composition....................... 6-5 6.2.3 DELETED; Refer to note on page

................... 6-6 6.2.4 SHIFT TECHNICAL ADVISOR......................................... 6-6 6.3 UNIT STAFF QUALIFICATIONS................

........................ 6-6 6.4 DELETED.

.................................................. 6-7 6.5 DELETED 6.5.1 Deleted I

I Deleted...................................................

Deleted...................................................

Deleted..................................................

Deleted...................................................

6-7 6-7 6-7 6 -7 6-7 6-8 6-9 I

I I

LIMERICK - UNIT 2 xxvi Amendment No. X, 4O, 1992, 138

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 Deleted Deleted................................................... 6-9.

Deleted................................................... 6^9 Deleted................................................... 6-10 Deleted................................................... 6-10 Deleted................................................... 6-10 Deleted................................................... 6-10 Deleted................................................... 6-10 Deleted................................................... 6-12 6.5.3 Deleted............

6-12 6.6 REPORTABLE EVENT ACTION..

6-12a 6.7 SAFETY LIMIT VIOLATION..

6-12a 6.8 PRbCEDURES AND PROGRAMS..

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6-15 Startup Report............

6-15 Annual Reports............

6-15 Monthly Operating Reports................................. 6-16 Annual Radiological Environmental Operating Report........ 6-16 Semiannual Radioactive Effluent Release Report............ 6-17 CORE OPERATING LIMITS REPORTS............................. 6-18a 6.9.2 SPECIAL REPORTS........................................... 6-18a 6.10 DELETED.

6-19 6.11 RADIATION PROTECTION PROGRAM.

6-20 6.12 HIGH RADIATION AREA.

6-20 LIMERICK - UNIT 2 xxvii Amendment No. 4, 6g,138

ADMINISTRATIVE CONTROLS 6.4 DELETED 6.5 DELETED THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6 -7 Amendment No. 2a, 0, 4-02, 4i222, 424, 138

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6-8 Amendment No. 4-, 68, 49, 44-1, 138

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6 -9 Amendment No.

2.,

,., 138

ADMINISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6-10 Amendment No. 69,138

ADQMItISTRATIVE CONTROLS THE INFORMATION FROM SECTION 6.5 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6-12 Amendment No. X, 4As, 4O, 448, 138

ADMINISTRATIVE CONTROLS 9Z r, ODCDTAPI r FPI FNT ACT TnN u -

l.LL.L LIL-.

I l

Ir 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b.

Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the NRB, Plant Manager and the Vice President, Limerick Generating Station.

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

a.

The NRC Operations Center shall and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Station, Plant Manager, and the be notified by telephone as soon as possible The Vice President, Limerick Generating NRB shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the NRB.

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

c.

The Safety Limit Violation Report shall be submitted NRB, Plant Manager, and the Vice President, Limerick within the 14 days of the violation.

to the Commission, the Generating Station, LIMERICK - UNIT 2 6-12a Amendment No..1-, 60, 148,138

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 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.

The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737.

c.

Refueling operations.

d.

Surveillance and test activities of safety-related equipment.

e.

Security Plan implementation.

f.

Emergency Plan implementation.

9.

Fire Protection Program implementation.

h.

PROCESS CONTROL PROGRAM implementation.

i.

OFFSITE DOSE CALCULATION MANUAL implementation.

j.

Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15, February 1979.

6.8.2 The information from Section 6.8.2 has been relocated to the QATR.

6.8.3 The information from Section 6.8.3 has been relocated to the QATR.

LIMERICK - UNIT 2 6-13 Amendment No.

4-0, &A, 4-02,138

ADMINISTRATIVE CONTROLS 6.10 DELETED THE INFORMATION FROM SECTION 6.10 HAS BEEN RELOCATED TO THE QATR LIMERICK - UNIT 2 6-19 Amendment No. 40, 138

AnMTNTSTPATITVF CONTROLS 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

6.12.1 High Radiation Areas with dose rates (deep dose equivalent) greater than 0.1 rem/hr and not exceeding 1.0 rem/hour (at 30 centimeters from the radiation sources or from any surface penetrated by the radiation):

a.

Each accessible entryway to such an area shall be barricaded and conspicuously posted as a High Radiation Area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

LIMERICK - UNIT 2 6-20 Amendment No. 44, 40.), 138

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) a)

A health physics qualified individual (i.e.,

qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for controlling personnel radiation exposure within the area, OR b)

Be under the surveillance, as specified in the RWP or equivalent, by means of closed circuit television, of a health physics qualified individual (i.e., qualified in radiation protection procedures),

responsible for controlling personnel radiation exposure in the area, and with the means to communicate with the individuals in the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:

a.

Shall be documented with the following information:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and LIMERICK - UNIT 2 6-21a Amendment No. 440, 138

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

2.

A determination that the change did not reduce the overall

.conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective upon review and acceptance by the PORC and approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 Changes to the ODCM:

a.

Shall be documented with the following information:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2.

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective upon review and acceptance by the PORC and the approval of the Plant Manager.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE O0CM.

LIMERICK - UNIT 2 6-22 Amendment No. X, 44,.3,138

v t e Letter Sequence Other
TAC:MC2739, (Approved, Closed) TAC:MC2740, (Approved, Closed)
Initiation Acceptance... Administration Questions Answers Results Approval Other: ML052080138
MONTHYEAR2005-07-25 [Table View]

ML052080138

Text

Navigation menu

Search