ML20196G387
| ML20196G387 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/22/1999 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20196G384 | List: |
| References | |
| NUDOCS 9907010141 | |
| Download: ML20196G387 (21) | |
Text
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s ATTACHMENT TO LICENSE AMENDMENT NO.
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FACILITY OPERATING LICENSE NO. DPR-66 t
DOCKET NO. 50-334 l
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l Replace the following pages of Appendix A, Technical Specifications, l
with the enclosed pages as indicated.
The revised pages are l
identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 6-1 6-1 6-3 6-3 6-5 6-5 6-6 6-6 6-23 6-23 i
6-24 6-24 i
6-25 6-25 1
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PDR r
DPR-66*
t ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The plant manager shall be responsible for overall facility l
operation and shall-delegate in writing the succession to this
. responsibility during his absence.
6.2 ORGANIZATION.
6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for facility l
operation and corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility and communication L.411 be established and defined for. the highest management levels through intermediate levels to and including all operating organization positions.
These-relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these technical specifications shall be documented in the Unit 2 UFSAR.
The correlation between the positions described in thesa.
technical specifications and the plant-specific titles are documented in the Unit 2 UFSAR, Table 13.1-2.
b.
The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and i
maintenance.
l c.
The corporate officer with direct responsibility for the plant shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, i
maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out radiation protection and quality assurance l
functions may report.to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
BEAVER VALLEY - UNIT 1 6-1 Amendment No.
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DfR ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) c.
A ' break of at least eight hours should be allowed between work periods, including shift turnover time.
d.
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.
I i
Any deviation from the above guidelines shall be authorized by the plant manager or predesignated alternate, or higher l
levels of management.
Authorized deviations to the working hour guidelines shall be documented and available for NRC review.
g.
The operations manager shall either hold a senior reactor operator license or have held a senior reactor operator license for a pressurized water reactor.
The assistant operations manager shall hold a current senior reactor operator license.
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l BEAVER VALLEY - UNIT 1 6-3 Amendment No.
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DPR A'D M I N I"S T R A T I V E C O N T R O L S I
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~6 ~. 3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility and radiation protection staff l
shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for.the operations managar as specified in Specification 6.2.2.g, the radiation protection manager
-who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the technical advisory engineering representative who shall have a bachelor's degree or equivalent in a scientific or engineering' discipline with specific training in plant design and response analysis of the plant for transients and accidents.
f:
6.4 TRAINING 6.4.1-A retraining and replacement training program for the I
facility staff: shall be _ maintained and shall meet or exceed the l
l requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
6.5 DELETED l
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS, a.
The Commission shall be notified in accordance with 10 CFR 50.72 and/or a
report be submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and I
b.
Each REPORTABLE EVENT shall be reviewed by the OSC, and the l
l results of this review shall be submitted to the ORC.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The-following actions shall be taken in the event a Safety l
. Limit is violated:
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a.
The facility shall be placed in at least HOT STANDBY within one (1) hour.
b.
The Safety Limit violation shall be reported to the Commission within one hour and to the plant manager and to l
the ORC within 24 honrs.
l c.
A Safety" Limit Vi$lation Report shall be prepared.
The report shall be reviewed by the On-Site Safety Committee 1
(OSC).
.This report shall describe (1) applicable 4
circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures,
.and (3) corrective action taken to prevent recurrence.
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BEAVER VALLEY - UNIT 1 6-5 Amendment No.
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DPR-6 6. -
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) d.
The Safety Limit Violation Report shall be submitted to the Commission, the ORC and the plant manager within 30 days of l
the violation.
6.8 PROCEDURES l
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.
Not used.
e.
Not used.
f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
4 6.8.2 Deleted 6.8.3 Deleted 6.8.4 A Post-Accident monitoring program shall be established, implemented, and maintained:
A program which will provide the capability to obtain and analyze reactor
- coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples following an accident.
The program shall include the following:
(i)
Training of personnel, (ii)
Procedures for sampling and analysis, and (iii)
Provisions for maintenance of sampling and analysis equipment.
BEAVER VALLEY - UNIT 1 6-6 Amendment No.
DfR ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601 of 10 CFR 20, each high radiation area in which
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the intensity of radiation is greater than 100 mrem /hr but less than i
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 Radiological Work PermitW Any individual or group l
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 J
the radiation dose rate in the area and alarms when a j
preset integrated dose is received.
Entry into such areas j
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 j
' positive control over the activities within the area and 1
shall perfort periodic radiation surveillance at the frequency specified by a facility radiation protection supervisor in the Radiological Work Permit.
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6.12.2 The requirements of 6.12.1, above, also apply to each high radiation area in which the intensity of radiation is greater than j
1000 mrem /hr.
In addition, locked doors shall be provided to prevent j
unauthorized entry into such areas and the keys shall be maintained under the administrative control of the shift supervisor on duty and/or a facility radiation pr e ction supervisor.
1 (1)
Radiation protection personnel, or personnel escorted by radiation protection personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their radiation protection duties, provided they comply with approved radiation protection l
procedures for entry into high radiation areas, BEAVER VALLEY - UNIT 1 6-23 Amendment No.
L DMR-66,f ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP:
a.
Shall be documented and records of reviews performed shall be retained in accordance with the applicable record retention provision of the quality assurance program description referenced in the Updated Final Safety Analysis Report.
This documentation shall contain:
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 overall conformance of the solidified waste product to existing requirements of
- Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the OSC and the approval of the plant manager, predesignated alternate or a predesignated manager to whom the plant manager has assigned in writing the responsibility for review and approval of specific subjects.
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained in accordance with the applicable record retention provision of the quality assurance program description referenced in the Updated Final Safety Analysis Report.
This documentation shall contain:
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 20.1302, 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.
'D.
Shall become effective after review and acceptance by the OSC and the approval of the plant manager, predesignated alternate or a predesignated manager to whom the plant manager has assigned in writing the responsibility for review and approval of specific subjects.
BEAVER VALLEY - UNIT 1 6-24 Amendment No.
1 DPR-66 ADMINI'STRATIVE CONTROLS t
I OFFSITE DOSE CALCULATION MANUAL (ODCM) (Continued) l l
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.
6.16 Moved to the PROCESS CONTROL PROGRAM.
6.17 Containment Leakaae Rate Testina Procram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J,
Option B,
as modified by approved exemptions (1)
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163,
" Performance-Based Containment Leak-Test Program," dated September 1995.
J The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 40.0 psig.
The maximum allowable containment leakage rate, La, at Pa, shall be 0.10% of containment air weight per day.
Leakage Rate acceptance criteria are:
a.
Containment leakage rate acceptance criterion is < 1.0 La for the overall Type A leakage test and < 0.60 La for the Type B and Type C tests on a minimum pathway leakage rate (MNPLR) basis.
During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La on a maximum pathway leakage rate (MXPLR) (2 ) basis for Type B and Type C tests and < 0.75 La for Type A tests.
(1) Exemptions to Appendix J of 10 CFR 50 dated November 19,
- 1984, December 5, 1984, and July 26, 1995.
(2) For penetrations which are isolated by use of a closed valve (s),
blind flange (s), or de-activated automatic valve (s), the MXPLR of the isolated penetration is assumed to be the measured leakage through the isolation device /s).
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BEAVER VALLEY - UNIT 1 6-25 Amendment No.
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ATTACHMENT 131 l
Unit No. 2 Technical specification Paces l
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ATTACHMENT TO LICENSE AMENDMENT NO.
EACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert XIV XIV 6-1 6-1 6-2 6-2 6-3 6-6 6-6 6-7 6-7 6-22 6-22 6-24 6-24 6-25 6-25 i
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7.-
NfF-73,-
I INDEX
. ADMINISTRATIVE CONTROLS SECTION PAGE 6.2.2 UNIT STAFF..............................
6-2 l
6.3 FACILITY STAFF OUALIFICATIONS....................
6-6 6.4 TRAINING.........................................
6-6 6.5 DELETED s
6.6 REPORTABLE EVENT ACTION..........................
6-6 6.7 SAFETY LIMIT VIOLATION...........................
6-6 6.8 PROCEDURES.......................................
6-7 6.9 REPORTING REQUIREMENTS 6.9.1 Occupational Radiation Exposure Report..
6-16 6.9.2 Annual Radiological Environmental Operating Report........................
6-16 6.9.3 Annual Radioactive Effluent Release Report..................................
6-17 6.9.4 Monthly Operating Report................
6-18 6.9.5 Core Operating Limits Report............
6-19 6.10 DELETED 6.11 RADIATION PROTECTION PROGRAM....................
6-19 l
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BEAVER VALLEY - UNIT 2 XIV Amendment No.
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'NPF-73*
6.O A'DMINISTRATIVE' CONTROLS 6.1 RESPONSIBILITY 6.1.1 The plant manager shall be responsible for overall facility l
operation and shall delegate in writing the succession to this responsibility during his. absence.
6.2 ' ORGANIZATION
.6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite - organizations shall be established for facility operation and corporate management, respectively.
The onsite and offsite organizations shall. include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility and communication shall be established and defined for the highest management levels. through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the
. form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent i
forms of documentation.
These requirements, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these technical specifications shall be documented in the Unit 2 UFSAR.
The correlation between the positions described in these technical specifications and the plant-specific titles are documented in the Unit 2 UFSAR, Table 13.1-2.
b.
The -plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance.
c.
The corporate officer with direct responsibility for the l
plant shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out radiation protection and quality assurance l
functions may report to the appropriate onsite' manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
BEAVER VALLEY - UNIT 2 6-1 Amendment No.
x
NfF-73*
ADMINISTRATIVE CONTROLS 6.2.2 UNIT STAFF
.The unit organization shall be subject to the following:
a.
Each 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 l
when fuel is in the reactor.
c.
At least two licensed operators shall be in the control l
room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips, d.
An individual qualified in radiation protection procedures shall be onsite 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.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; senior reactor operators, reactor operators, radiation control technicians, auxiliary operators, meter and control repairman, and all personnel actually performing work on safety related equipment.
The objective shall be to have operating personnel work a normal 8-hour
- day, 40-heur week while the plant is operating.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
a.
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, b.
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.
c.
A break of. at least eight hours should be allowed
'between work periods, including shift turnover time.
BEAVER VALLEY - UNIT 2 6-2 Amendment No.
I
NfF ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) d.
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 plant manager or predesignated alternate, or higher l
levels of management.
Authorized deviations at the working hour guidelines shall be documented and available for NRC review.
g.
The operations manager shall either hold a senior re. actor operator license or have held a senior reactor operator license for a pressurized water reactor.
The assistant operations manager shall hold a current senior reactor operator license.
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i BEAVER VALLEY - UNIT 2 6-3 Amendment No.
l (Next page is 6-5)
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N,1 F-7 3 -
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS I
6.3.1 Each member of the facility and radiation protection staff l
shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the operations manager as specified in Specification 6.2.2.g, the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the technical advisory engineering representative who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the j
facility staff shall be maintained and shall meet or exceed the l
requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
6.5 DELETED 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified in accordance with 10 CFR 50.72 and/or a
report be submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the OSC, and the results of this review shall be submitted to the ORC.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least HOT STANDBY within one (1) hour.
b.
The Safety Limit violation shall be reported to the Commission within one hour.
The Safety Limit violation shall be reported to the plant manager and to the ORC l
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the On-Site Safety Committee (OSC).
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.
BEAVER VALLEY - UNIT 2 6-6 Amendment No.
7 l
NPF-73,-
' ADMINISTRATIVE CONTROLS i
l SAFETY LIMIT VIOLATION (Continued) i d.
The Safety Limit Violation Report shall be submitted to the Commission, the ORC and the plant manager within 30 days of l
the violation.
{
6.8 PROCEDURES
'6.8.1 Written procedures shall be established, implemented, and 1
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.
Not used.
e.
Not used.
f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
6.8.2 Deleted 6.8.3 Deleted 6.8.4 A Post-Accident monitoring program shall be established, implemented, and maintained.
The program will provide the capability to obtain and analyze reactor
- coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere l
samples following an accident.
The program shall include the following:
l (1)
Training of personnel, (ii)
Procedures for sampling and analysis, and (iii)
Provisions for maintenance of sampling and analysis equipment.
l BEAVER VALLEY - UNIT 2 6-7 Amendment No.
l (Next page is 6-14)
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KPF-7]*
ADMINISTRATIVE CONTROLS HIGH' RADIATION AREA (Continued) issuance of a Radiological Work Permit (1)
Any individual or group l
.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.
l b.
A radiation monitoring device'which continuously integrates 1
the radiation dose rate in the area and alarms when a L
preset integrated dose'is received.
Entry into such areas l
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 I
shall perform periodic radiation surveillance at the frequency specified by a facility radiation protection supervisor in the Radiological Work Permit.
6.12.2 The requirements of 6.12.1, above, 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 a facility radiation protection supervisor.
(1). Radiation protection personnel, or personnel escorted by radiation protection personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
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BEAVER VALLEY - UNIT 2 6-22 Amendment No.
1 (Next page is 6-24)
NPF-73*
ADMINISTRATIVE CONTROLS j.13 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP:
a.
Shall be documented and records of reviews performed shall be retained in accordance with the applicable record retention provision of the quality assurance program description included in the Updated Final Safety Analysis Report.
This documentation shall contain:
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 overall conformance of the solidified waste product to existing requirements of Federal,
- State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the OSC and the approval of the plant manager, predesignated alternate or a predesignated manager to whom the plant manager has assigned in writing the responsibility for review and approval of specific subjects.
l BEAVER VALLEY - UNIT 2 6-24 Amendment No.
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1(PF ADMINISTRATIVE CONTROLS ll l l ll l l
ll ll 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 4 Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained in accordance with the applicable record
. retention provision of the quality assurance program j
' description included in the Updated Final Safety Analysis Report.
This documentation shall contain:
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 20.1302, 40.CFR Part.190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy i
or reliability of
- effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by the OSC and the approval of the plant manager, predesignated alternate or a predesignated manager to whom the plant manager has assigned in writing the responsibility for review and approval of specific subjects.
i 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.
6.16 Moved to the PROCESS CONTROL PROGRAM.-
6.17 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54 (o) and l CFR 50, exemptions (g)
This Appendix J, Option B,
as modified by approved program. shall be in accordance with the guidelines contained in Regulatory Guide 1.163,
" Performance-Based Containment Leak-Test Program," dated-September 1995.
j (1)
Exemptions to Appendix J of 10 CFR 50, as stated in the operating license.
BEAVER VALLEY UNIT 2' 6-25 Amendment No.
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ATTACHMENT B-1 Channe Summary, Unit 1 l
1 Tvoed Panes Editorial Channes 6-1 In paragraph 6.2.1 "Offsite" has been replaced by "offsite" to be consistent with Unit 2 wording. In paragraph 6.2.1.a
" Technical Specifications" has been replaced with
)
" technical specifications" to be consistent with current convention.
6-3 No additional changes are included.
i 6-5 In paragraph 6.3.1 " Radiation Protection" has been replaced with " radiation protection" to be consistent with this term used elsewhere. In paragraph 6.6.1.b "the" was added after "and" to be consistent with the Unit 2 wording.
6-6 No additional changes are included.
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i 6-23 In paragraph 6.12.2 " Shift Supervisor" has been replaced with " shift supervisor" to be consistent with titles used
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elsewhere.
6-24 In paragraphs 6.13.b and 6.14.b " predesignated Manager" has been replaced with " predesignated manager" to be consistent with titles used elsewhere.
6-25 No additional changes are included.
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ATTACHMENT B-2 Chance Summary. Unit 2 l
Tvoed Panes Editorial Channes XIV This page was added to show the page number change when l
Section 6.2.2 was shifted to page 6-2.
6 In paragraph 6.2.1.a " Technical Specifications" has been replaced with " technical specifications" to be consistent with current convention.
i 6-2 In paragraph 6.2.2.b " Operator" has been replaced with
" operator"; in paragraph 6.2.2.c " Operators" has been i
replaced with " operators"; and in paragraph 6.2.2.e " Senior Reactor Operator" has been replaced with " senior reactor operator" and " Senior Reactor Operator Limited to Fuel Handling" has been replaced with " senior reactor operator limited to fuel handling" to be consistent with titles used elsewhere. Under the page number "(Next page is 6-5)"
was moved to new page 6-3.
6-3 This page was added due to shifting as a result of added infonnation and format changes.
l 6-6 In paragraph 6.3.1 " Radiation Protection" has been replaced with " radiation protection" to be consistent with this term used elsewhere.
6-7 No additional changes are included.
6-22 In paragraph 6.12.2 " Shift Supervisor" has been replaced with " shift supervisor" to be consistent with titles used-elsewhere.
6-24 In paragraph 6.13.b " predesignated Manager" has been replaced with " predesignated manager" to be consistent with titles used elsewhere.
6-25 In paragraph 6.14.b " predesignated Manager" has been replaced with " predesignated manager" to be consistent with titles used elsewhere.
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