ML20085N557
| ML20085N557 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/06/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20085N565 | List: |
| References | |
| DPR-70-A-168, DPR-75-A-150 NUDOCS 9506300244 | |
| Download: ML20085N557 (19) | |
Text
o UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20066 4001
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NVCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 168 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated February 9, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tfMs as indicated in the attachment to this license amendment, and l
paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
9506300244 950606 PDR ADOCK 05000272 P
,;A-1.
2-1 (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.168, are hereby incorporated in the L
license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Ad. EnW 6f - John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 6, 1995 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 168 I
i FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272
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Revise Appendix A as follows:
~
Remove Paaes Insert Paaes-6-1 6-1 6-2 6-2 6-8 6-8 6-10 6-10 1
6-13 6-13 6-14 6-14 6-16 6-16 l
l
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager - Salem Operations shall be responsible for overall facility operation and shall delegate, in writing, the succession to this responsibility during his absence.
6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the control room, a designated individual, shall be responsible for the control room command function. A management directive to this effect, signed by.the Chief Nuclear Officer and President - Nuclear Business Unit, shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be established and defined from 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 shall be documented in the Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.71(e).
b.
The General Manager - Salem Operations shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c.
The Chief Nuclear Officer and President - Nuclear Business Unit l
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 health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
SALEM - UNIT 1 6-1 Amendment No.168
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i-i ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF The facility organization shall be subject to the following:
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 Reactor' Operator shall be in the control room when fuel is in the reactor.
In addition, at least one licensed Senior Reactor Operator shall be in the Control Room area at all times.
All CORE ALTERATIONS shall be observed and directly supervised by a c.
licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.
d.
The amount of overtime worked by plant staff members performing I
safety-related functions must be limited in accordance with the NRC Policy Statement on working hours-(Generic Letter No. 82-12).
e.
The Operating Engineer, Senior Nuclear Shift Supervisors, and Nuclear Shift Supervisors shall each hold a senior reactor operator l
license. The Nuclear Control Operators shall hold reactor operator i
- licenses, f.
The Operations Manager shall meet one of the following:
i 1
(1)
Hold an SRO license, i
(2)
Have held an SRO license for a similar unit (PWR).
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SALEM - UNIT 1 6-2 Amendment No. IbO l
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e, ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE (SOPC)
FUNCTION 6.5.1.1 The Station Operations Review Committee shall function to advise the General Manager - Salem Operations on operational matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Station Operations Review Committee (SORC) shall be composed of:
i Chairman:
General Manager - Salem Operations i
Member and Vice Chairman:
Maintenance Manager Member and Vice Chairman:
Operations Manager Member and Vice Chairman:
Technical Manager Member:
Radiation Protection Manager l
Member:
Operating Engineer Member:
Technical Engineer Member:
Maintenance Engineer Member:
Chemistry Manager Member Onsite Safety Review Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SORC
- Chairman, Only designated Vice Chairmen or the General Manager - Salem a.
Operations may act as Chairman of a SORC meeting.
b.
No more than two alternates to members shall participate as voting members in SORC activities at any one meeting.
Alternates shall only represent their respective departments.
c.
d.
Alternates for members will not make up part of the voting quorum when the members the alternate represents is also present.
MEETING FREOUENCY 6.5.1.4 The SORC shall meet at least once per calendar month and as convened by the SORC Chairman or his designated alternate.
OUORUM 6.5.1.5 The minimum quorum of the SORC necessary for the performance of the SORC responsibility and authority provisions of these technical specifications SALEM - UNIT 1 6-8 Amendment No. 168
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P
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l' ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued)
Review of all unplanned on-site releases of radioactivity to the m.
environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence.
n.
Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE l
DOSE CALCULATION MANUAL.
i SORC REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified reviewers shall function to perform the periodic or routine review of procedures and changes thereto. Details of this technical review process are provided in i
Section 6 5.3.
AUTHORITY 6.5.1.0 The Station Operations Review Committee shall:
Provide recommendations to the General Manager - Salem Operations a.
indicating written approval or disapproval of items considered under 6.5.1.6 above.
I b.
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 -
Nuclear Operations and the Director - Quality Assurance and Nuclear Safety Review of disagreement between the SORC and the General Manager - Salem Operations; however, the General Manager - Salem Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS AND REPORTS 6.5.2.9 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President -
Nuclear Operations, the Director - Quality Assurance and Nuclear Safety Review and the Manager - Nuclear Safety.
6.5.2 NUCLEAR SAFETY REVIEW AND AUDIT FUNCTION 6.5.2.1 The Nuclear Safety Department shall function to provide the independent safety review program and audit of designated activities.
COMPOSITION 6.5.2.2 The Nuclear Safety Department, under the cognizance of the Director
- Quality Assurance and Nuclear Safety Review, shall consist of the Manager -
Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG).
The OSR staff and the SRG each consist of at least four SALEM - UNIT 1 6-10 Amendment No.168 l
Y s:
ADMINISTRATIVE COlTTROLS AUDITS (continued) e.
The Facility Emergency Plan and implementing procedures at least once per 12 months.
f.
The Facility Security Plan and implementing procedures at least once per 12 months.
g.
Any other area of facility operation considered appropriate by the Director - Quality Assurance and Nuclear Safety Review or the Chief Nuclear Officer and President - Nuclear Business Unit.
h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i.
The fire protection and loss prevention program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer (s) or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least once per 36 months.
j.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
The above audits may be conducted by the Quality Assurance Department or an independent consultant.
Audit plans and final audit reports shall be reviewed by the OSR staff.
RECORDS AND REPORTS 6.5.2.4.4 Records of OSR activities shall be maintained. Reports of reviews and audits shall be prepared and distributed as indicated below:
a.
The results of reviews performed pursuant to Section 6.5.2.4.2 shall be reported to the Chief Nuclear Officer and President - Nuclear Business Unit at least monthly.
b.
Audit reports prepared pursuant to Section 6.5.2.4.3 shall be forwarded by the auditing organization to the Chief Nuclear Officer and President - Nuclear Business Unit and to the management positions responsible for the areas audited (1) within 30 days after completion of the audit for those audits conducted by the Quality Assurance Department, and (2) within 60 days after completion of the audit for those audits conducted by an independent consultant.
6.5.2.5 ON-SITE SAFETY REVIEV GROUP (SRG)
FUNCTION 6.5.2.5.1 The On-Site Safety Review Group (SRG) shall function to provide:
the review of plant design and operating experience for potential opportunities to improve plant safety; the evaluation of plant operations and SALEM - UNIT 1 6-13 Amendment No.168
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ADMINISTRATIVE CONTROLS FUNCTION (continued) maintenance activities; and advice to management on the overall quality and safety of plant operations.
The SRG shall make recommendations for revised procedures, equipment modifications, or other means of improving plant safety to appropriate station / corporate management.
RESPONSIBILITIES 6.5.2.5.2 The SRG shall be responsible for:
Review of selected plant operating characteristics, NRC issuances, a.
industry advisories, and other appropriate sources of plant design and operating experience information that may idicate areas for improving plant safety.
l b.
Review of selected facility features, equipment, and systems.
Review of selected procedures and plant activities including c.
maintenance, modification, operational problems, and operational analysis.
d.
Surveillance of selected plant operations and maintenance activities to provide independent verification
- that they are performed correctly and that human errors are reduced to as low as reasonably achievable.
bUTHORITY 6.5.2.6 The Nuclear Safety Department shall report to and advise tha Chief Nuclear Officer and President - Nuclear Business Unit on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.
6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Programs required by Technical Specification 6.8 and other procedures which affect nuclear safety as determined by the General Manager - Salem operations, other than editorial or typographical changes shall be reviewed as follows:
PROCEDURE REIATED DOCUMENTS 6.5.3.2 Procedures, Program and changes thereto Phall be reviewed as follows:
a.
Each newly created procedure, program or change thereto shall be independently reviewed by an individual knowledgeable in the subject area other than the individual who prepared the
- Not responsible for sign-off function SALEM - UNIT 1 6-14 Amendment No.168
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i ADMINISTRATIVE CONTROLS RECORDS AND REPORTS 6.5.3.4 Written records of reviews performed in accordance with item 6.5.3.2a above, including recommendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Manager - Salem Operations, SORC, the OSR staff and/or NRC as necessary when their reviews are required.
6.6 REPORTABLE EVENT ACTION 6.6.1 The follcaing actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and/or a report submitted pursuant co the requirements of Section 50.73 to 10CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the SORC and the resultant Licensee Event Report submitted to the OSR staff and the Chief Nuclear Officer and President - Nuclear Business Unit.
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 STANDBY within one hour.
b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Chief Nuclear Officer and President - Nuclear Business Unit and Director - Quality Assurance and Nuclear Safety Review shall be notified 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 SORC.
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 Director - Quality Assurance and Nuclear Safety Review and the Chief Nuclear Officer and President - Nuclear Business Unit within 14 days of the violation.
SALEM - UNIT 1 6-16 Amendment No.168 l
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L UNITED STATES
'g NUCLEAR REGULATORY COMMISSION 5
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY j
DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT N0. 2 i
AMEiiDHENT TO FACILITY OPERATING LICENSE 4
Amendment No.150 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
)
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated February 9, 1995, complies with the standards and requirements of the 1
Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
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(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.150, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
i l
3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION dJd. /i2 i =
pJohnF.Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 6, 1995
1 t.
ATTACHMENT TO LICENSE AMENDMENT NO. 150 FACILITY OPERATING LICENSE NO. DPR-75 i
DOCKET NO. 50-311 Revise Appendix A as follows:
1 Remove Paaes Insert Paaes j
6-1 6-1
]
6-8 6-8 i
6-10 6-10 1
6-13 6-13 6-14 6-14 6-16 6-16 i
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i
W ADMINISTRATIVE COfTTROLS 6.1 PESPONSIBILITY 6.1.1 The General Manager - Salem Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the Control Room, a designated individual shall be responsible for the Control Room command function. A management directive to this effect, signed by.the Chief Nuclear Officer and President - Nuclear Business Unit, shall be reissued l
to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONE Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.
Lines of authority, responsibility, and communication shall be a.
established and defined from 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 shall be documented in the Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.71(e),
b.
The General Manager - Salem Operations shall be responsible for overall facility safe operation and shall have control over those 1
onsite activities necessary for safe operation and maintenance of
{
the plants.
l c.
The Chief Nuclear Officer and President - Nuclear Business Unit shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable j
i performance of the staff in operating, maintaining, and providing l
technical support to the plants to ensure nuclear safety.
i d.
The individuals who train the operating staff and those who carry
{
out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITY STAFF The Facility organization shall be subject to the following:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
SALEM - UNIT 2 6-1 Amendment No.150 l
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'l ADMINISTRATIVE CONTROLS I
i 6.5 EEZEW AND AUDIT I
6.5.1 STATION OPERATIONS REVIEW COMMITTEE (SORC)
FUNCTION 6.5.1.1 The Station Operations Review Committee shall function to advise the General Manager - Salem Operations on operational matters related to nuclear safety.
l COMPOSITION
~l 6.5.1.2 The Station Operations Review Committee (SORC) shall be composed of:
i I
Chairman:
General Manager-- Salem Operations Member and Vice Chairman:
Maintenance Manager Member and Vice Chairman:
Operations Manager Member and Vice Chairman:
Technical Manager l
Member:
Radiation Protection Manager l
Member:
Operating Engineer Member:
Technical Engineer Member:
Maintenance Engineer Member:
Chemistry Manager l
Member:
Onsite Safety Review Engineer l
ALTERNATES 1
6.5.1.3 All alternate members shall be appointed in writing by the SORC Chairman.
1 Only designated'Vice Chairmen or the General Manager - Salem a.
Operations may act as Chairman of a SORC meeting.
b.
No more than two alternates to members shall participate as voting members in SORC activities at any one meeting.
Alternates shall only represent their respective departments, c.
d.
Alternates for members will not make up part of the voting quorum when the members the alternate represents is also present.
MEETING FREQUENCY 6.5.1.4 The SORC shall meet at least once per calendar month and as convened by the SORC Chairman or his designated alternate.
OUORUM 6.5.1.5 The minimum quorum of the SORC necessary for the performance of the SORC responsibility and authority provisions of these technical specifications shall consist of the chairman or his designated alternate and four members including alternates.
I SALEM - UNIT 2 6-8 Amendment No.150 I
l ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued)
Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE n.
DOSE CALCULATION MANUAL.
SORC REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified reviewers shall function to perform the periodic or routine review of procedures and changes thereto. Details of this technical review process are provided in Section 6.5.3.
AUTHORITY 6.5.1.8 The Station Operations Review Committee shall:
Provide recommendations to the General Manager - Salem Operations a.
indicating written approval or disapproval of items considered under 6.5.1.6.
b.
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
- Nuclear Operations and the Director - Quality Assurance and Nuclear Safety Review of disagreement between the SORC and the General Manager - Salem Operations; however, the General Manager -
Salem Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS AND REPORTS 6.5.1.9 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President -
Nuclear Operations, the Director - Quality Assurance and Nuclear Safety Review and the Manager - Nuclear Safety.
6.5.2 NUCLEAR SAFETY REVIEW AND AUDIT FUNCTION 6.5.2.1 The Nuclear Safety Department shall function to provide the independent safety review program and audit of designated activities.
COMPOSITION 6.5.2.2 The Nuclear Safety Department, under the cognizance of the Director - Quality Assurance and Nuclear Safety Review, shall consist of the Manager - Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG).
The OSR staff and the SRG each consist of at leact four dedicated, full-time engineers.
The Manager - Nuclear Safety and the Offsite Safety Review staff shall meet or exceed the qualifications described in Section 4.7 of ANS 3.1 - 1981 and shall be guided by the provisions for independent review described in Section 4.3 of ANSI N18.7 - 1976 (ANS 3.2),
SALEM - UNIT 2 6-10 Amendment No.150 l
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cz 1l ADMINISTRATIVE CONTROLS
===========================================================
AUDITS (continued) e.
The Facility Emergency Plan and implementing procedures at least once per 12 months.
l f.
The Facility Security Plan and implementing procedures at least once per 12 months.
g.
Any other area of f acility operation considered appropriate by the Director - Quality Assurance and Nuclear Safety Review or the Chief Nuclear Officer and President - Nuclear Business Unit.
h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i 1.
The fire protection and loss prevention program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer (s) or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least once per 36 months.
j.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
The above audits may be conducted by the Quality Assurance Department or an independent consultant. Audit plans and final audit reports shall be reviewed by the OSR staff.
RECORDS AND REPORTS 6.5.2.4.4 Records of OSR activities shall be maintained. Reports of reviews and audits shall be prepared and distributed as indicated below:
a.
The results of reviews performed pursuant to Section 6.5.2.4.2 shall be reported to the Chief Nuclear Officer and President -
Nuclear Business Unit at least monthly, b.
Audit reports prepared pursuant to Section 6.5.2.4.3 shall be forwarded by the auditing organization to the Chief Nuclear Officer and President - Nuclear Business Unit and to the management positions responsible for the areas audited (1) within 30 days after completion of the audit for those audits conducted by the Quality Assurance Department, and (2) within 60 days after completion of the audit for those audits conducted by an independent consultant.
6.5.2.5 ON-SITE SAFETY REVIEW GROUP (SRG)
FUNCTION 6.5.2.5.1 The On-Site Safety Review Group (SRG) shall function to provide:
the review of plant design and operating experience for potential opportunities to improve plant safety; the evaluation of plant operations and SALEM - UNIT 2 6-13 Amendment No.150 l
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ADMINISTRATIVE CONTROLS FUNCTION (continued)-
. maintenance activities; and advice to management on the overall quality and safety of plant operations. The SRG shall make recommendations for revised procedures, equipment modifications, or other means of improving plant safety to appropriate station / corporate management.
' RESPONSIBILITIES 6.5.2.5.2 The SRG shall be responsible for:
a.
Review of selected plant operating characteristics, NRC issuances, industry advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety.
b.
Review of selected facility features, equipment, and systems.
Review of selected procedures and plant activities including f
c.
maintenance, modification, operational problems, and
]
operational analysis, j
d.
Surveillance of selected plant operations and maintenance activities to provide independent verification
- that they are performed correctly and that human errors are reduced to as low as reasonably achievable.
NSR AUTHORITY 6.5.2.6 The Nuclear Safety Department shall report to and advise the Chief Nuclear Officer and President - Nuclear Business Unit on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.
6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Programs required by Technical Specification 6.8 and other procedures which affect nuclear safety as determined by the General Manager - Salem Operations, other than editorial or typographical changes shall be reviewed as follows:
PROCEDURE RELATED DOCUMENTS 6.5.3.2 Procedures, Program and changes thereto shall be reviewed as follows:
a.
Each newly created procedure, program or change thereto shall be independently reviewed by an individual knowledgeable in the subject area other than the individual who prepared the procedure, program or procedure change, but who may be from the same organization as the individual / group which prepared the
- Not responsible for sign-off function SALEM - UNIT 2 6-14 Amendment No.150 l
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A*MINISTRATIVE CONTROLS RECORDS AND REPORTS 6.5.3.4 Written records of reviews performed in accordance with item 6.5.3.2a above, including recommendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Manager - Salem Operations, SORC, the OSR staff and/or NRC as necessary when their reviews are required.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
The Commission shall be notified and/or a report submitted pursuant a.
to the requirements of Section 50.73 to 10CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the SORC and the resultant Licensee Event Report submitted to the OSR staff and the Chief Nuclear Officer and President - Nuclear Business Unit.
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 STANDBY within one hour.
b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Chief Nuclear Officer and President - Nuclear Business Unit and Director -
Quality Assurance and Nuclear Safety Review shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, A Safety Limit Violation Report shall be prepared. The report c.
shall be reviewed by the SORC.
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 Director - Quality Assurance and Nuclear Safety Review and the Chief Nuclear Officer and President - Nuclear Business Unit within 14 days of the violation.
SALEM - UNIT 2 6-16 Amendment No.150
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