ML20137E237
| ML20137E237 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/21/1997 |
| 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 | |
| ML20137E243 | List: |
| References | |
| DPR-70-A-192, DPR-75-A-175 NUDOCS 9703270116 | |
| Download: ML20137E237 (31) | |
Text
.
annqk UNITED STATES g9 j
NUCLEAR REGULATORY COMMISSION
[t WASHINGTON, D.C. 30666-0001 4
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Tf4 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.192 License No. DPR-70
{
1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
l A.
The application for amendment filed by the Public Service Electric &
i Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated January 11, 1996, as supplemented by letters dated February 26, May 22, June 27, July 12, December 23, 1996, and March 17, 1997, complies with the standards and requirements of the Atomic Energy Act i
of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 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: (i) that the activities authorized by l
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; 4
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-70 is hereby amended to read as follows:
i 9703270116 970321 PDR ADOCK 05000272 4
P PDR
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.192, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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In addition, the license is amended to add paragraph 2.C.(10) to the i
facility Operating License No. DPR-70 as follows:
(10) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.192, are hereby incorporated into this license.
Public Service Electric and Gas Company shall operate the facility in accordance with the Additional Conditions.
j 3.
This license amendment is effective as of its date of issuance and the change to the facility shall be implemented within 60 days from the date of issuance.
Implementation of this amendment shall include the J
relocation of certain technical specification requirements to the 1
l appropriate licensee-controlled documents as described in the Licensee's applicatien dated January 11, 1996, and its supplements dated February 26, May 22, June 27, July 12, December 23, 1996, and March 17, 1997, and evaluated in the staff's safety evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION
(
'll Jo F. Stolz, Dires or P oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
1.
Page 4b to License
- No. DPR-70 and page 1 to Appendix C of License
- DPR-70 2.
Changes to the Technical Specifications Date of Issuance: March 21, 1997 l
- Page 4b of the license and page 1 of Appendix C are attached, for convenience, for the composite license to reflect this change.
i ATTACHMENT TO LICENSE AMENDMENT NO.192 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 1.
Revise License as follows:
Remove Paae Insert Pace i
4b 2.
Insert Appendix C, page 1 j
3.
Revise Appendix A as follows:
Remove Paaes Insert Paaes XV XV XVIII XVIII XIX 6-1 6-1 6-2 6-2 6-7 6-7 6-0 6-8 6-9 6-9 through 6-14 6-10 6-11 6-12 6-13 6-14 6-15 6-15 6-16 6-16 6-17 6-17 6-26 6-26 7
1 4b I
I (10) Additional Conditions The Additional Conditions contained in Appendix C, as revised i
j through Amendment No.192, are hereby incorporated into this 1
license.
Public Service Electric and Gas Company shall operate the facility in accordance with the Additional Conditions.
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Amendment No.192 i
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l APPENDIX C ADDITIONAL CONDITIONS s
l OPERATING LICENSE NO. DPR-70 Public Service Electric and Gas Company, Philadelphia Electric Company, j'
Delmarva Power and Light Company, and Atlantic City Electric Company shall comply with the following conditions on the schedules noted below:
Amendment Additional Condition Implementation Number Date 192 The licensee is authorized to relocate certain The amendment Technical Specification requirements to shall be licensee-controlled documents.
Implementation implemented of this amendment shall include the relocation within 60 days of these technical specification requirements from March 21, i
to the appropriate documents, as described in 1997 the licensee's application dated January 11, 1996, as supplemented by letters dated
[
February 26, May 22, June 27, July 12, December 23, 1996, and March 17, 1997, and
)
evaluated in the staff's safety evaluation
]
attached to this amendment.
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1 Amendment No.192 s
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i INDEX
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j BASES l
SECTION F,,A_QE A
f 3/4.9 REFUELING OPERATIONS 1
i i
3/4.9.1 BORON CONCENTRATION.
. B 3/4 9-1 3/4.9.2 INSTRUMENTATION B 3/4 9-1 4
3/4.9.3 DECAY TIME B 3/4 9-1 l\\
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS B 3/4 9-1 j
3/4.9.5 COMMUNICATIONS B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE B 3/4 9-2 I
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4 9-2 4
4 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION. B 3/4 9-2 1
d 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF I
ISOLATION SYSTEM B 3/4 9-2 i
1 4
3/4.9.10 WATER LEVEL - REACTOR VESSEL i
and AND j
3/4.9.11 STORAGE POOL B 3/4 9-3 5
3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM.
B 3/4 9-3 i
1 j
3/4.10 SPECIAL TEST EXCEPTIONS i
j 3/4.10.1 SHUTDOWN MARGIN B 3/4 10-1 i
l 3/4.10.2 - GROUP HEIGHT, INSERTION AND POWER l-DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3-PHYSICS TESTS B 3/4 10-1 3/4.10.4 NO FLOW' TESTS B 3/4 10-1 SALEM.- UNIT 1-XV Amendment No.192
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY.
6-1 6.2 ORGANIZATION Onsite and Offsite Organizations 6-1 Facility Staff.
..................... 6-1 Shift Technical Advisor 6-7 6.3 FACILITY STAFF OUALIFICATIONS 6-7 6.4 TRAINING.........
6-7 6.5 REVIEW AND AUDIT (THIS SECTION DELETED).
6-8 6.6 REPORTABLE EVENT ACTION.
6-16 6.7 SAFETY LIMIT VIOLATION
. 6-16 6.8 PROCEDURES AND PROGRAMS 6-17 6.9 REPORTING REOUIREMENTS 6.9.1 ROUTINE REPORTS 6-20 6.9.2 SPECIAL REPORTS 6-24 6.10 RECORD RETENTION..
6-24 6.11 RADIATION PROTECTION PROGRAM 6-26 6.12 HIGH RADIATION AREA 6-26 6.13 PROCESS CONTROL PROGRAM (PCP) 6-27 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-28 6.15 MAJOR CHANGES TO RADIOACTIVE LIOUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6-28 6.16 ENVIRONMENTAL OUALIFICATION.
6-29 i
SALEM - UNIT 1 XVIII Amendment No.192 i
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ADMINISTRATIVE CONTROLS j
6.1 RESPONSIBILITY 6.1.1. The plant manager shall be responsible for overall facility operation l
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 senior corporate nuclear officer, shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION i
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 plant manager shall be responsible for overall unit safe l
operation and shall have control over those onsite activities i
necessary for safe operation and maintenance of the plant.
c.
The senior corporate nuclear officer shall have corporate responsibility for overall plant nuclear safety and shall take any i
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 i
organizational freedom to ensure their independence from operating pressures.
SALEM - UNIT 1 6-1 Amendment No.192
ADMINISTRATIVE CONTROLS j
l 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 i
shift crew composition shown in Table 6.2-1; j
b.
At least one licenced 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 j
c.
All CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.
d.
Administrative controls shall be developed and implemented to limit the working hours of personnel who perform safety-related functions (e.g.,
senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel, et al.).
The controls shall include guidelines on working hours that ensure that adequate shift coverage is maintained without heavy use of overtime for individuals.
Any deviation from the working hour guidelines shall be authorized in advance by the plant manager er his designee, in accordance with approved administrative procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedure such that overtime shall be reviewed monthly by the plant manager or his designee to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines shall not be authorized.
SALEM - UNIT 1 6-2 Amendment No.192
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i ADMINISTRATIVE CONTROLS l
6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to l
the Senior Nuclear Shift Supervisor on matters pertaining to the engineering I
aspects assuring safe operation of the unit.
6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in l
plant design and response and analysis of the plant for transients and accidents.
l 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the individual designated as the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, the individual designated as the Operations Manager who shall meet or exceed the j
minimum qualifications of ANSI N18.1-1971 except as modified by Specification 6.3.3, and the licensed operators who shall comply with the requirements of i
6.3.2 The Operations Manager or Assistant Operations Manager shall hold an SRO license.
The Senior Nuclear Shift Supervisors and Nuclear Shift i
j Supervisors shall each hold a senior reactor operator license. The Nuclear control Operators shall hold reactor operator licenses.
6.3.3 The Operations Manager shall meet one of the following:
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1)
Hold an SRO license, or 2)
Have held an SRO license for a similar unit (PWR), or
- 3) Have been certified at an appropriate simulator for equivalent senior operator knowledge.
I 64 TRAINING 2
6.4.1 A retraining and replacement training program for the facility staff i
shall:
l 1) be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Director -
l 2
Nuclear Training 1
2) meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 for all affected positions except licensed operators and 3
i 3) comply with the requirements of 10CFR55 for licensed operators.
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SALEM - UNIT 1 6-7 Amendment No.192 1
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ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT (THIS SECTION DELETED) l l
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4 SALEM - UNIT 1 6-8 Amendment No.192
e ADMINISTRATIVE CONTROLS
=====..................................................................
4 PAGES 6-9 THROUGH 6-14 ARE DELETED.
SALEM - UNIT 1 6-9 through 6-14 Amendment No.192
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6 ADMINISTRATIVE CONTROLS l
===============............,,,,,,,,,,,,,,,,,_ ___
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THIS PAGE IS INTENTIONALLY BLANK, 1
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SALEM - UNIT 1 6-15 Amendment No.192 1
a 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/or a report submitted pursuant to the requirements of Section 50.73 to 10CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Station Operations Review Committee (SORC) and the resultant Licensee Event Report submitted to the Nuclear Review Board and the senic?. corporate nuclear officer.
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 senior corporate nuclear officer and senior management position with responsibility for independent nuclear safety assessment activities and quality program oversight 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, i
d.
The Safety Limit violation Report shall be submitted to the Commission, the senior management position with responsibility for independent nuclear safety assessment activities and quality program oversight and the senior corporate nuclear officer within 14 days of the violation.
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l SALEM - UNIT 1 6-16 Amendment No.192
a ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained l
covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory i
Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
i e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
i 1.
Quality Assurance Program for effluent and environmental monitoring.
l 6.8.2 Each procedure and administrative policy of 6.8.1 above, except 6.8.1.d and 6.8.1.e, and changes thereto, shall be reviewed and approved in accordance with requirements in Updated Final Safety Analysis Report (UFSAR) section 17.2 for SORC or for Technical Review and Control, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures. Procedures of 6.8.1.d and 6.8.1.e shall be reviewed and approved in accordance with the Facility's Security and Emergency Plans or requirements in Updated Final Safety Analysis Report (UFSAR) section 17.2 for Technical I
Review and Control, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures.
6.8.3 On-the-spot changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented and receives the same level of review and approval as the original procedure within 14 days of implementation.
l SALEM - UNIT 1 6-17 Amendment No.192 l
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ADMINISTRATIVE CONTROLS 4
c.
Records of radiation exposure for all individuals entering radiation control areas.
)
d.
Records of gaseous and liquid radioactive material released to the environs.
J e.
Records of transient or operational cycles for those facility components identified in Table 5.7-1.
i f.
Records of reactor tests and experiments, j
4 a
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Records of training and qualification for current members of the i
plant staff.
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h.
Records of in-service inspections performed pursuant to these
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Technical Specifications.
i 1.
i 1.
Records of Quality Assurance activities required by the QA Manual.
l j.
DELETED k.
Records of SORC meetings and activities of the Nuclear Review Board i
l (and activities of its predecessor, the Offsite Safety Review (OSR) j staff.)
j 1.
Records for Environmental Qualification which are covered under the j
provisions of Paragraph 6.16.
I m.
Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.
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n.
Records of secondary water sampling and water quality.
o.
Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the accuracy of j
the analysis at a later date. This should include procedures l
effective at specified times and QA records showing that these procedures were followed.
t x
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation' protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and d
adhered to for all operations involving personnel radiation exposure.
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SALEM' UNIT 1' 6-26 cmendmer,t No.192
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 3066Mm01 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO.50-31I SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.175 License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission 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 January 11, 1996, as supplemented by letters dated February 26, May 22, June 27, July 12, December 23, 1996, and March 17, 1997, 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; 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: (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-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:
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.175, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
In addition, the license is amended to add paragraph 2.C.(26) to the Facility Operating License No. DPR-75 as follows:
(26) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.175, are hereby incorporated into this license.
Public Service Electric and Gas Company shall operate the facility in accordance with the Additional Conditions.
3.
This amendment is effective as of its date of issuance and the change to the facility shall be implemented within 60 days from the date of issuance.
Implementation of this amendment shall include the relocation of certain technical specification requirements to the appropriate licensee-controlled documents as described in the Licensee's application -
dated January 11, 1996, and its supplements dated February 26, May 22, June 27, July 12, December 23, 1996, and March 17, 1997, and evaluated in the staff's safety evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION
(
n F. Stolz, Dir tor Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
1.
Page 21 to License
- No. DPR-75 and page 1 to Appendix C of License
- DPR-75 2.
Changes to the Technical Specifications Date of Issuance: March 21, 1997
- Page 21 of the license and page 1 of Appendix C are attached, for convenience, for the composite license to reflect this change.
s
a ATTACHMENT TO LICENSE AMENDMENT NO.17s FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 1.
Revise License as follows:
Remove Paae Insert Pace
]
21 21 2.
Insert Appendix C, page 1 i
3.
Revise Appendix A as follows:
Remove P'aaes Insert Paaes XVIII XVIII i
XIX 6-1 6-1 6-2 6-2 6-7 6-7
- 6-8 6-8 6-9 6-9 through 6-14 6-10 6-11 6-12 6-13 6-14 6-15 6-15 6-16 6-16 6-17 6-17 6-26 6-26
l ~
(n)
Revised Small-Break loss-of-Coolant-Accident Methods (Section 22.3. II.K.3.30) 4 PSE&G shall comply with the requirements of this position as specified in NUREG-0737, " Clarification of TMI Action Plan Requirements."
(o)
Compliance With 10 CFR Part 50.46 (Section 22.3. II.K.3.31)
PSE&G shall perform plant-specific calculations using NRC-approved models for small-break loss-of-coolant accidents (LOCAs) to show compliance with 10 CFR Part 50.46.
PSE&G shall submit these calculations by January 1,1983, or one year after NRC approval of LOCA analysis models, whichever is later, only if model changes have been made.
(p)
Emeraency Support Facilities (Section 22.3. III.A.I.2)
PSE&G shall maintain in effect an interim Technical Support Center and an interim Emergency Operations Facility until such time as the final facilities are complete, j
(26) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.175, are hereby incorporated into this license.
Public Service Electric and Gas Company shall operate the facility in accordance with the Additional Conditions.
D.
An exemption from certain requirements of Appendix J to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No. 4.
This exemption was authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest. The exemption, therefore, remains in effect. The granting of the exemption was authorized with the issuance of the License for Fuel-Loading and Low-Power Testing, dated April 18, 1980. The facility will operate, to the extent authorized herein, in conformity with the application as amended, the provisions of the Act, and the regulations of the Commission.
Amendment No.175
l l
APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-75 Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company, and Atlantic City Electric Company shall comply with the following conditions on the schedules noted below:
Amendment Additional Condition Implementation Number Date 175 The licensee is authorized to relocate certain The amendment Technical Specification requirements to shall be licensee-controlled docuwnts.
Implementation implemented of this amendment shall include the relocation within 60 days of these technical specification requirements from March 21, to the appropriate documents, as described in 1997 the licensee's application dated January 11, 1996, as supplemented by letters dated February 26, May 22, June 27, July 12, December 23, 1996, and March 17, 1997, and evaluated in the staff's safety evaluation attached to this amendment.
l 1
Amendment No.175 i
e INDEX ADMINISTRATIVE CONTROLS
=............. =........... = = = = = = =............ = = = =............ = = = = = = = =
SECTION h
6.1 RESPONSIBILITY............................................. 6-1 6.2 OPGANIZATION Onsite and Offsite Organizations 6-1 Facility Staff............................................
6-1 l
Shift Technical Advisor...................................
6-7 6.3 FACILITY STAFF OUALIFICATIONS 6-7 1
1 6.4 TRAINING 6-7 j
l 6.5 REVIEW AND AUDIT (THIS SECTION DELETED)....................
6-0 j
6.6 REPORTABLE EVENT ACTION.................................... 6-16 i
i 6.7 SAFETY LIMIT VIOLATION 6-16 6.8 PROCEDURES AND PROGRAMS 6-16 6.9 REPORTING REOUIREMENTS 6.9.1 ROUTINE REPORTS 6-19 6.9.2 SPECIAL REPORTS 6-23 6.10 RECORD RETENTION 6-23 6.11 RADIATION PROTECTION PROGRAM 6-25 6.12 HIGH RADIATION AREA........................................ 6-25 6.13 PROCESS CONTROL PROGRAM (PCP) 6-26 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-27 6.15 MAJOR CHANGES TO RADIOACTIVE LIOUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6-27 SALEM - UNIT 2 XVIII Amendment No.175
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 responsibility during his absence.
6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the j
Control Room, a designated individual shall be responsible for the Control Room command function. A management directive to this effect, signed by the senior corporate nuclear officer, 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).
l b.
The plant manager shall be responsible for overall facility safe operation and shall have control over those onsite activities J
necessary for safe operation and maintenance of the plants.
j c.
The senior corporate nuclear officer 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 plants 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 i
the appropriate onsite manager; however, they shall have l
sufficient crganizational freedom to ensure their independence l
from operating pressures.
l 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.
I l
SALEM - UNIT 2 6-1 Amendment No.175 l
l
M INISTRATIVE CONTROLS
==......................................===.====================......
i FACILITY STAFF (Continued) 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.
c.
All CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.
d.
Administrative controls shall be developed and implemented to limit the working hours of personnel who perform safety-related functions (e.g.,
senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel, et al.).
The controls shall include guidelines on working hours that ensure that adequate shift coverage is maintained without heavy use of overtime for individuals.
Any deviation from the working hour guidelines shall be authorized in advance by the plant manager or his designee, in accordance with i
approved administrative procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedure such that overtime shall be reviewed monthly by the plant manager or his designee to ensure that excessive hours have not been assigned. Routine deviation from i
the above guidelines shall not be authorized.
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6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the Senior Nuclear Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.
6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the individual designated as the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, the individual designated as the operations Manager who shall meet or exceed the minimum qualifcations of ANSI N18.1-1971 except as modified by Specification 6.3.3, and the licensed operators who shall comply with the requirements of 10CFR55.
6.3.2 The Operations Manager or Assistant Operations Manager shall hold an SRO license.
The Senior Nuclear Shift Supervisors and Nuclear Shift Supervisors shall each hold a senior reactor operator license.
The Nuclear Control Operators shall hold reactor operator licenses.
6.3.3 The Operations Manager shall meet one of the following:
1)
Hold an SRO license, or 2)
Have held an SRO license for a similar unit (PWR), or 3)
Have been certified at an appropriate simulator for equivalent senior operator knowledge.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall:
- 1) be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Director - Nuclear l
Training
- 2) meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 for all affected positions except licensed operators and
- 3) comply with the requirements of 10CFR55 for licensed operators, l
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l SALEM - UNIT 2 6-15 Amendment No.175
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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/or a report submitted pursuant to the requirements of Section 50.73 to 10CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Station Operations Reivew Committee (SORC) and the resultant Licensee Event Report i
submitted to the Nuclear Review Board and the senior corporate nuclear officer.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is i
violated:
)
l 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 senior corporate nuclear officer and senior management position with responsibility for independent nuclear safety assessment activities and quality program oversight 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.
3 d.
The Safety Limit Violation Report shall be submitted to the Commission, the senior management position with responsibility for independent nuclear safety assessment activities and quality program oversight and the senior corporate nuclear officer within 14 days of the violation.
SALEM - UNIT 2 6-16 Amendment No.175
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i 6.8 PROCEDURES AND PROGRAMS l
6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced belows a.
The applicable procedures recommended in Appendix "A"
of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation, i.
Quality Assurance Program for effluent and environmental monitoring.
6.8.2 Each procedure and administrative policy of 6.8.1 above, except 6.8.1.d and 6.8.1.e, and changes thereto, shall be reviewed and approved in accordance with requirements in Updated Final Safety Analysis Report (UFSAR) section 17.2 for SORC or for Technical Review and Control, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures.
Procedures of 6.8.1.d and 6.8.1.e shall be reviewed and approved 1
in accordance with the Facility's Security and Emergency Plans or requirements in Updated Final Safety Analysis Report (UFSAR) section 27.2 for Technical Review and Control, as appropriate, prior to implementation and reviewed l
periodically as set forth in administrative procedures.
6.8.3 On-the-spot changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
Th'e change is documented and receives the same level of review and approval as the original procedure under within 14 days of implementation.
SALEM - UNIT 2 6-17 Amendment No.175
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c.
Records of radiation exposure for all individuals entering radiation j
control areas.
1 d.
Records of gaseous and liquid radioactive material released to the environs.
Records of transient or operational cycles for those facility e.
components identified in Table 5.7-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
1.
Records of Quality Assurance activities required by the QA Manual, j.
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Records of SORC meetings and activities of the Nuclear Review Board (and activities of its predecessor, the Offsite Safety Review (OSR) staff).
1 1.
Records for Environmental Qualification which are covered under the provisions of Paragraph 2.C(7) and 2.C(8) of Facility Operating License DPR-75.
m.
Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.
n.
Records of secondary water sampling and water quality, o.
Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the accuracy of the analysis at a later date.
This should include procedures effective at specified times and QA records showing that these procedures were followed.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
SALEM - UNIT 2 6-26 Amendment No.175
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