ML20245F221
| ML20245F221 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/31/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245F225 | List: |
| References | |
| NUDOCS 8908140207 | |
| Download: ML20245F221 (36) | |
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' i' k-UNITED STATES i
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NUCLEAR REGULATORY COMMISSION
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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 SALEMGENERATINGSTATION,UNITNO.J AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. DPR-70 1.
The Nuclear Regulatory Commission (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 July 15, 1988 and supplemented by letters dated April 25, 1989 and May 24, 1989 cemplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rJ1es 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-70 is hereby amer.ded to read as follows:
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. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
99, are hereby incorporated in the 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 45 days of the date of issuance.
FOR THE NUCLEAR REGULATORY C0hMISSION
/S/
Walter R. Butler, Director Project Directorate I--2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
July 31, 1989
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2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amencent do. 99 are' hereby incorporated in the 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 45 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications bateof_ Issuance:
July 31, 1989 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. DPR-70 l
DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Pages Insert Pages XVIII XVIII i
XIX XIX 6-1 6-1 6-la 6-2 6-2 6-3 6 - 6-8 6-8 6-9 6-9 6-9a 6-9a 6-10 6-10 6-11 6-11 6-12 6-12 6-12a 6-12a 6-12b M
h 9
4.
e.
INDEX ADMINISTRATIVE CONTROLS 333 33333333333333333333 32 23 3 33 WE 333 3 3 33 3 3 3 3 3 3 3 3 3 3 3 3333 33 52 2 3323 E EE E E E E E E E SECTION g
6.1 RESPONSIB(L(([...
6-1 6.2 ORGANIZATION Onsite and Offsite Organizations.............
6-Facility Statt......................
6-Shift Technical Advisor
................-'6-6.3 FACILITY STAFF QUALIFICATION 6-6 l
6.4 TRAINING.
6-6 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW CORMITTEE Function 6-7 Composition.....................
6-7 Alternates 6-7 Meeting Frequency......
6-7 1
Quorum 6-7 Responsibilities 6-8
- ~
Review Process 6-9 Authority.
6-9 Record-6-9 6.5.2 NUCLEAx 3AFETY REVIEW Function 6-9 Composition......................
6-9 Consultants.............
6-9a Off-Site Review Group...
6-9a Review 6-10 l
Audits 6-10 On-Site Safety Review Group..
6-11 Responsibilities 6-11 Authority...................... 6-12
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SALEM - UNIT 1 XVIII Amendment No.99 l
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INDEX ADMINISTRATIVE CONTROLS j-assessssssssssssssssssssssssssssssssssssssssazzmarsasassassassassassassas L
SECTION PAGE i
6.5.3 TECHNICAL REVIEW AND CONTROL............
6-12
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6.6 Pl[0RTABLE EVENT ACTION.
6-12b 6.7 SATETY LIMIT VIOLATION.................
6-12b 6.8 PROCEDURES AND PROGR AMS.................
6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6-15 6.9.2 SPECIAL REPORTS 6-21 6.10 RECORD RETENTION....................
6-21 6.11 RADIATION _ PROTECTION PROGRAM 6-23
......... r.....
6.12 HIGH RAOIATION AREA..............._,_...,. 6-23;.._
6.13 PROCESS CONTROL PROGRAM.
6-24 6.14 0FFSITE DOSE CALCULATION MANUAL...
6-24 6.15 MAJOR CFANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS...
6-25 6.16 ENVIRONMENTAL QUALIFICATION,
6-26 SALEM - UNIT 1 XIX Amendmen* No. 99
6.0 10M*%*3 ::-",E ::% ::.I l*
6.1 RESP 0NSIBILITV 6.1.1 The General Manager - Salem Ooerations shall be responsible 'or evers' facility operation and shall delegate, in writing, the success 4on to r.nis l
responsibility during 44s absence.
6.1.2 The Senior Nuclear Shift Supervisor, or during his absence from tne control room a designated individual, shall be responsible for the control room command function.
A management directive to this effect signed by the Vice President and Chief Nuclear Officer, shall be reissued to all stat;on l
personnel on an annual basis.
6.2 ORGANIZATION.
6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit aperation and corporate management, respectively.
The onsite and offsite organizations shall include positions
',r activities affecting the safety c f the nuclear ower plant.
a.
Lines of authority, responsibility, and communication shall be established and defined from the nighest 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 eouivalent forms of documentation.
These requirements shall be documented in the Salem Updated Final Safety Analysis Report and updated in accorcance with 10 CFR 50.71(e).
b.
The General Manager - Salem Operations snall be responsible for overall unit safe operation and shall have control over nose onsite activities necessary for safe operation and maintenance of tne plant.
c.
The Vice President and Chief Nuclear Officer snail nave corporate responsibility for overall plart nuclear safety and shall take any measures needed to ensure accep;able 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 ouality assurance functions may recorc to :ne appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operat' g pressures.
I 6.2.2 ACILITY STAFF The facility organization shall be subject to the following:
l a.
Each on duty shift shall be composed of at least the minimum snift crew composition shown in Table 6.2-1; SALEM - UNIT 1 6-1 Amencment No. 99 l
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a ADMINISTRATIVE CONTROLS FACILITY STAFF (continued) b.
At least one licensed 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 l
c.
A health physics technician
- shall be on site when fuel is in the l
reactor.
d.
ALL CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation e.
A site Fire Brigade of at least 5 members shall be maintained onsite at all timesa. The Fire Brigade shall not include 4 members of the l-minimum shift crew nocessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.
f.
The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).
g.
The Operations Manager, Operating Engineer, Senior Nuclear Shift
' Supervisor, and Nuclear Shift Supervisor shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold
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reactor operator licenses.
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- The health physics technician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of the health physics technician and/or Fire Brig.Je members provided immediate action is taken to restore the health-physics technician and/or Fire Brigade to within the minimum requirements.
SALEM - UNIT 1 6-la Amendment No. 99 l
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Figure 6.2-1 CORPORATE HEADQUARTERS AND OFF-SITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT (Deleted) v b
SALEM - UNIT 1 6-2 Amendment No. 99
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i SALEM - UNIT 1 6-3 Amendment No. 99
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'E RESo0NSIBId ~!ES 6.5.1.6 The' Station Oper6tions Review Committee snall be resconsioie f:r:
a.
Review of: (1) Station Administrative procedures and enarges t9ereto and (2) Newly created procedures or cnanges to existing procecures that involve a significant safety issue as described in Section 6.5.3.2.d.
b.
Review of all proposed tests and' experiments that affect nuclear safety.
c.
Review of all proposed changes to Appendix "A" Technical Specifications.
d.
Review of all proposed changes or modifications to olant systems or ecuipment that affect nuclear safety, e.
Review of the safety evaluations that have been completed under the provisions of 10 CFR 50.59.
f.
Investigation of all violations of'the Technical Specifications including the preparation and forwarding of reports covering evaluation and recomrnendations to prevent recurrence to the Vice President and Chief Nuclear Officer and the General Manager -
Nuclear Safety Review.
g.
Review of all REPORTABLE EVENTS.
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h.
Review of facility operations to detect potential nuclear safety hazards.
i.
Performance of special reviews, investigatic,ns or analyses anc reports tnereon as requested by the General Manager - Salem Operations or General Manager - Nuclear Safety Review.
j.
Review of the Facility Security plan and implementing procedures anc submittal of recommended changes to the General Manager - Nuclear Safety Review.
k.
Review of the Facility Emergency Plan and implementing procedures and submittal of recommended changes to the General Manager -
Nuclear Safety Review.
1.
Review of the Fire Protection program and implementing procedures and submittal of recommended changes to the General Manager -
Nuclear Safety Review, m.
Review of all unplanned on-site releases of idioactivity to tne environs including the preparation of reports covering evaluation.
recommendations and disposition of the corrective action to orevent recurrence and the forwarding of these reports to the Vice presicen-and Chief Nuclear Officer and the General Manager - Nuclear 5&fety Review.
l SALEM - UNIT 1 6-8 Amendment No. 99
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- 9*5: 5~;;~:7E ::%~;:_3 RESPONSIBIL* TIES (continued)
Review of changes to the PROCESS CONTROL MANUAL and tne CFF-S: E n.
DOSE CALCULATION MANUAL.
SORC REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing Qualifie.d reviewers shall function to perform the periodic or routine review of procedures anc changes thereto. Details of this technical review process are provided in Section 6.5.3.
AUTHORITY 6.5.1.8 The Station Operations Reviaw Committee shall:
a.
Recommend to the General Manager - Salem Operations written approval or disapproval of items considered under 6.5.1.6 (a) througn (e) above.
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 and Chief Nuclear Officer and the General Manager - 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 6.5.1.9 The Station Operations Review Committee shall maintain written fNnutes of each meeting.and copies shall be provided to the Vice pres dert anc Chief Nuclear Officer, the General Manager - Nuclear Safety Review ana :ne j
'anager - Off-Site Review.
6.5.2 NUCLEAR SAFETY AEVIEW l
FUNCTION 6.5.2.1 The Nuclear Safety Review Department (NSR) shall function to provide tne i'ncependent safety review program and audit of designated activities.
COMo0SITION 6.5.2.2 NSR shall consist of the General Manager - Nuclear Safety Review, tme Manager - On-Site Safety Review Group (SRG), wno is supported by at least four dedicated, full-time engineers located on-site, and the Manager Off-Site Review Group (OSR) who is supported by at least four dedicated, full-time engineers located off-site.* The OSR staff shall possess experience and competence in the general areas listed in Section 6.5.2.4. The General Manager and Managers shall determine wnen additional technical experts snould assis-in reviews of complex problems.
" Since the Nuclear Department is located on Artificial Island site, the terms "on-site" and "off-site" convey the distinction between inside and outside the station fence, respectively SALEM - UNIT 1 6-9 Amencment No. 99
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COMPOSITION (cont'nuec)
NSR shall-utilize a sys' tem of qualified reviewers from ctner tecrrica organizations to augment its expertise in the disciplines of Section 6.5.2.4 Such. qualified reviewers shall meet _the same qualification requirements as tre-NSR staff, and will not have been involved witn performance of_the original work.
The Manager - Off-Site Review and 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). The Manager - On Site Review and staff will meet or exceed the qualifications described in.Section 4.4 of ANS 3.1 (1981).
CONSULTANTS 6.5.2.3 Consultants shall be utilized as determined by the General Manager -
Nuclear Safety Review to provide expert advice to the NSR.
OFF-SITE REVIEW GROUP 6.5.2.4 The Off-Site Review Group (OSR) shall function to provide independent review and audit of designated activities in the areas of:
a, Nuclear Power Plant Operations
- b. Nuclear Engineering
- c. Chemistry-and Radiochemistry
- d. Metallurgy
- e. Instrumentation and Control
- f. Radiological Safety
-g. Mechanical Engineering
- h. Electrical Engineering
- i. Quality Assurance
- j. Nondestructive Testing
- k. Emergency Preparedness The OSR shall also function to examine plant operating characteristics. NP issuances, industry advisories, Licensee Event Reports, and otner sources which may indicate areas for improving plant safety.
SALEM - UNIT 1 6-9a Amendment No. 99
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REV:EW 6.5.2.4.1 The OSR shall review:
.a.
Safety Evaluations for 1)
Changes to procedures, equipment, or systems and 2)
Tests or experiments completed under the provisions of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedur.es, equipment, or systems that involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
c.
Proposed tests or experiments that involve an unreviewed safety question as defined in Section 50.59, 10CFR.
d.
Proposed changes o Technical Specifications or to the Operating License.
e.
Violations of codes, regulations, orders,. Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety'.
g.
Al[1REPORTABLEEVENTS.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems ur components'.
i.
Reports and meeting minutes of the Station Operations Review Committee.
AUDITS 6.5.2.4.2 Audits of facility activities that are req > aired to oe performeo under the cognizance of OSR are listed below; a.
The conformance of facility cperation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training, and qualifications of the entire f acility staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occure'-- in facility eouipment, structures, systems, or method of opera: :n trat affect nuclear safety at least once per 6 months, d.
The performance of activities required by :ne Operational Quality Assurance Program to meet the Criteria of Appendix "B",
10CFR50, at least once per 24 months.
j SALEM - UNIT 1 6-10 Amencment No. 99 l
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AUDITS (continuec)
The Facility Emergency Plan and implementing procecures at least e.
once per 12 months.
f.
The Facility Security plan and implementing procedures at least once per 12 months.
1 g.
Any other area _of facility operation considered appropriate by the General Manager - Nuclear Safety Review or the Vice President and Chief Nuclear Officer.
h.
The Facility Fire Protection Program and implementing procedures at l
least once per 24 months.
i..
An-independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either cualified offsite licensee personnel or an outsice fire protection firm.
j.
An inspectior and audit of the fire protection and loss prevention program shall.be performed by a cualified outside fire. consultant at least once per 36 months.
k.
The radiological environmental monitoring program and the results thereof at least ence per 12 months.
'The above audits'shall be conducted by the Nuclear Quality Assurance Department or an independent consultant as required. Audit results and recommendations shall be reviewed by OSR.
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20N-SITE SAFETY REVIEW GROUP 6.5.2.5 The On-Site Safety Review Group (SRG) shall function to provide: the review of plant design and operating exe'erience for potential opportunities to improve plant safety; the evaluation of plant operations and maintenance activities; and acvice to management on the overall Quality and safety of plant operations.
The SRG shall make recommendations for revised procedures, ecuipment modifications, or other means of improving plant safety to appropriate station / corporate management.
RESPONSIBILITIES 6.5.2.5.1 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.
i SALEM - UNIT 1 6-11 Amendment No.99 m_
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ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued) c.
Review of selected procedures and plant activities including 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.
NSR AUTHORITY 6.5.2.6 NSR shall report to and advise the Vice President and Chief Nuclear Officer on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.
6.5.2.7 Records of NSR activities shall be prepared and maintained. Reports of reviews and audits shall be distributed as follows:
- a..
. Reports of reviews encompassed by Section 6.5.2.4.1 above, shall be prepared, approved and forwarded to the Vice President and Chief Nuclear Officer, within 14 days following completion of the review.
b.
' Audit reports encompassed by Section 6.5.2.4.2 above, shall be
' forwarded to the Vice President and Chief Nuclear Officer and to the l
management positions responsible for the areas audited within 30 days after completion of the audit.
6.5.3 TECHFICAL 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:
Each newly created procedure, program or change thereto shall be a.
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 procedure or procedure change. Procedures other than Station Administrative procedures will be approved by the appropriate Station Department Manager or by the Assistant General Manager - Salem Operations. Each Station Department Manager shall be responsible for a predesignated class of procedures. The General Manager - Salem Operations shall approve Station Administrative Procedures, Security Plan implementing procedures and Emergency Plan implementing procedures.
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- Not responsible for sign-off function SALEM - UNIT 1 6-12 Amendment No. 99
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1 p:iCCEDURE RE*_ATED DCCUMENTS (continuec) b On-the-spot changes to procedures which clearly do not change tre intent of the approved procedures shall be approved oy two memoers of the plart management staff, at least one of whom holds a Senior Reactor Operator License. Revisions to procedures which may involve a change in intent of the approved procedures, shall be reviewed in accordance with Section 6.5.3.2.a above, c.
Individuals responsible for reviews performed in accordance with item 6.5.3.2a above shall be approved by the 50RC Chairman and designated as Station Qualified Reviewers. A system of Station Qualified Reviewers, each of. whom shall possess qualifications that meet or exceed the requirements of Section 4.4 of ANSI N18 1 - 1971, shall be maintained by the 50RC Chairman. Each review shall incluce a written determination of whether or not additional cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel, d.
If the Department Manager determines that the documents involved contain significant safety issues, the documents shall be forwarded for 50RC review and also to NSR for an independent review to determine whether or not an unreviewed safety question is involved, Pursuant to 10CFR50.59, NRC approval of items involving unreviewed safety questions or Technical Specification changes shall be optained prior to implementation.
'NON-DROCEDURE RELATED DOCUMENTS
' 13. 5. 3. 3 Tests or experiments, changes to Technical Specifications, and
' changes to eouipment or' systems shall be forwarded for 50RC review and also to NSR for an independent review to determine whether or not an unreviewed safety auestion is involved. The results of NSR reviews will be provided to SORC.
Recommendations for approval are made by 50RC to the General Manager - Salem Operations. pursuant to 10CFR50.59, NRC approval of items involving unreviewed safety questions or recuiring Technical Specification cnanges snail be obtained prior to implementation.
RECORDS 6.5.3.4
'M tten records of reviews pertermed in accordance with itme 6.5.3.2a above, including recommendations for app ovai or disapproval, shall be maintained. Copies shall be provided to the General Manager - Salem Operations SORC, NSR and/or NRC as necessary when their reviews are requirec.
i.
1 i-l SALEM - UNIT 1 6-12a Amendment No. 99
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6.6 REDORTABLE EVENT ACTICN 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 50RC and the resultant Licensee Event Report submitted to NSR and the Vice President and Chief 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 STANOBY 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 Vice President and Chief Nuclear Officer and General Manager - 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 ta 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 oe submitted to the Commission, the General Manager - Nuclear Sr ety Review and the Vice President and. Chief Nuclear Officer within 14 days of the violation.
i SALEM - UNIT 1 6-12b Amencment No. 99
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM GENERATING STATION, UNIT NO. ?
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 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,(Delmarve. Power and Light Company and Atlantic City Electric Cerrpany the licensees) dated
. July 15, 1988 and supplemented by letters dated April 25, 1989 and
,- May 24, 1989 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; l-C.
There is reasonable assurance: (i) that the activities author-ized 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
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Chapter I; l
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.
i 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 folicws:
I
, (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76 are hereby incorporated in the e
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 45 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/S/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
- hanges to the Technical Specifications Date of Issuance:
July 31, 1989 n
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2 (i) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
76. are'hereby incorporated in the 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 45 days of the date of issuance.
l l
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler. Director Project Directorate I.2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Spec,ifications bateofIssuance:
July 31, 1989
l ATTACHMENT TO LICENSE AMENDMENT NO. 76 L
FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Pages Insert Pages l
XVIII XVIII XIX XIX 6-1 6-1 6-la 6-2 6-2 6-3 6-3 6-8 6-8 6-9 6-9 6-9a 6-9a 6-10 6-10 6-11 6-11 6-12 6-12 6-12a 6-12a 6-12b eAus b
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ADMINISTRATIVE; CONTROLS
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P.3.G1 6.1 RESPONSIBILITY.
6-1 6.2 ORGANIZATION f.
Onsite and Offsite Organizations.............
6-1 l
Facility Staff......................
6-1 Shift Technical Advisor 6-6
-6.3 FACILITY STAFF QUALIFICATION 6-6 l
6.4 TRAINING.
6-6 6.5' REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW C0%!!ITTEE Function 6-7 Composition.....................
6-7 Alternates 6-7 Meeting frequency.
6-7 Quorum 6-7 Responsibilities 6-8 Review Proce.is 6-9 Authority....
6-9 Record 6-9 6.5.2 NUCLEAR SAFETY REVIEW Function 6-9 Composition.....................
6-9 Consultants' 6-9a Off-Site Review Group.
6-9a Revieu 6-10 l
Audits 6-10 On-Site Safety Review Group.
6-11 Responsibilities 6-11 Authority......
6-12 l
SALEM - UNIT 2 XVIII Amendment No. 76
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TNDEX a
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f ADMINISTRATIVE CONTROLS
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SECTION PAGE 6.5.3 TECHNICAL REVIEW AND CONTROL............
6-12 6.6 REPORTABLE EVENT ACTION.
. 6-12a 6.7 SATETY LIMIT VIOLATION.................
6-12b 6.8 PROCEDURES AND PROGRAMS...
6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6-15 N
l 6.9.2 SPECIAL REPORTS 6-21 L
l 6.10 RECORD RETENTION 6-21 6.21 RADIATION PROTECTION PROGRAM 6-23 6.12 HIGH RADIATION AREA................._,..,. 6-23 6.13 PROCESS CONTROL PROGRAM,
6-24 6.14 OTTSITE DOSE CAI.CULATION MANUAL....
6-24
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6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS.
6-25 SALEM - UNIT 2 XIX Amendment No.76
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6.1 RESPONSIBILITY 6.1.1' The General Manager - Salem Operations snall be resoonsib:e for Ove T '
facility operation and.shall celegate in writing the succession to tnis responsibility during nis absence.
6.1.2 The' Senior Nuclear Shift Supervisor or, during h's esence from the Control Room, a designated incividual shall.,be responticle ?or the Control Room command function. A management directive to this effect, signec by the Vice President and Chief Nuclear Officer, shall be reissued to a
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 anc corcorate management, respectively.
The onsite and offsite organizations sha 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 lesels 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, anc job descriptions for key personnel positiuns, or in eouivalent forms of documentation.
These requirements shall be documented in the Salem Updated Final Sa:ety Analysis Report and updated in accorcance 7
with 10 CFR 50.71(e).
b.
The General Manager - S?lem Operations shall be responsible for overall facility safe oce. ration and shall nave control over tnose onsite activities necessary for safe operation anc maintenance of the plants.
c.
The Vice President and Chief Nuclear 0?ficer shall have corporate responsibility for overall plant nuclear safety and snall take any measures needed to ensure acceptable performance of the staff in ~
eperating, maintaining, and oroviding technical support to the plantr 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 reoort to tne appropriate onsite manager; newever, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 ACILITY STAFF The facility organization shall be subject to the following:
l a.
Each on duty shift shall be composed of at least tne minimum snift crew composition shown in Table 6.2-1.
I SALEM - UNIT 2 6-1 Amencment No.76
ADMINISTRATIVE CONTROLS
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FACILITY STAFF (Continued) b.
At least one licensed 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.
A health physics technician
- shall be on site when fuel is in the l
reactor.
d.
ALL CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.
e.
A site Fire Brigade of at least 5 members shall be maintained onsite at all times *. The Fire Brigade shall not include 4 members of the l
minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency, f.
The amount of overtime worked by plant staff members performing safety-related fune.tions must be limited in accordance with the NRC Policy Statement en working hours (Generic Letter No. 82-12).
g..
The Operations Manager, Operating Engineer, 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.
- The nealth physics technician and Fire Brigade composition may be l
less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unersected absence of the nealth pnysics technician and/or Fire Brigade members provided immediate action is taken to restore the health physics tecnnician and/or Fire Brigade to within the minimum requirements.
SALEM - UNIT 2 6-la Amendment No. 76 1
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I Figure 6.2-1 CORPORATE HEADQUARTERS AND OFF-SITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT (Deleted)
SALEM - UNIT 2 6-2 Amendment No. 76
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e FIGURE 6.2-2 FACILITY ORGANIZATION e
(Deleted) 7
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SALEM - UNIT 2 6-3 Amendment No.76
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.g, Resp 0NSIBILI'IES-6.5.1.6 The Station Operations Review Committee shall be responsible ':c:
a.
Review of: (1) Station Administrative procedures and changes theret:
and (2) Newly created procedures or changes to existing proceoures that involve a significant safety issue as described in Section 6.5.3.2.d.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to Appendix "A" Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
e.
Review of the safety evaluations that have been completed under the provisions of 10CFR50.59.
-f.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluatio6 and reconnendations to prevent recurrence to the Vice President and Chief Nuclear Officer and the General Manager -
Nuclear Safety Review.
g.
Re. view of all REPORTABLE EVENTS.
h.
Review of facility operations to detect potential nuclear safety hazards.
i.
performance of special reviews, investigations or analyses anc reports thereon as requested by the General Manager - Salem Operations or General Manager - Nuclear Safety Review.
j.
Review of the Facility Security Plan and implementing procecures anc submittal of recommended changes to the General Manager - Nuclear Safety Review.
k.
Review of the Facility Emergency Plan and implementing procecures and submittal of recommended changes to the General Manager -
Nuclear Safety Review.
1.
Review of the Fire Protection Program and implementing procedures and submittal of recommended changes to the General Manager -
Nuclear Safcty Review.
m.
Review of all unplanned on-site releases of radioactivity to tne environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent l
recurrence and the forwarding of these reports to the Vice Presicent and Chief Nuclear Officer and the General Manager - Nuc' ear Safety Review.
SALEM - UNIT 2 6-8 Amendment No. 76
ry s:5 ;1. :!E ::50.3 RESP 0NSIBILITIES (continuec)
)
n.
Review of cnanges to the PROCESS CONTROL MANUAL and the OF~-5:~:
J DOSE CALCULATION MANUAL.
j SORC REVIEW PROCESS 6.5.1.7 t, 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:
a.
Recommend to the General Manager - Salem Operations written aceroval or disapproval of items considered under 6.5.1.6 (a) througn (e) above.
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 and Chief Nuclear Officer and the General Manager - Nuclear Safety Review of disagreement between the 50RC and the General Manager -
Salem Operations; however, the General Manager - Salem Operations shall haveresponsibility for resolution of such disagreements l
pursuant to 6.1.1 above.
RECORDS 6.5.1.9 The Station Operations Review Committee shall maintain written finutes of each meeting.and copies shall be provided to the Vice Presideat an::
Chief Nuclear Officer, the General Manager - Nuclear Safety Review anc :ne Manager - Off-Site Review.
6.5.2 NUCLEAR SAFETY REVIEW FUNCTION 6.5.2.1 The Nuclear Safety Review Department (NSR) shall function to provide tne independent safety review program and audit of designated activities.
COMP 0SITION 6.5.2.2 NSR shall consist of the General Manager - Nuclear Safety Review. toe Manager - On-Site Safety Review Group (SRG), wno is supported by at least fce dedicated, full-time engineers located on-site, and the Manager Off-Site Review Group (OSR) who is supported by at least four dedicated, full-time engineers located off-site.* The OSR staff shall possess exper"nce and competence in the general areas 14 tted in Section 6.5.2.4. The General Manager and Managers shall determine whe' wtional technical experts snould assist a
in reviews of complex problems.
Since the Nuclear Department is located on Artificial Island site.
the terms "on-site" and "off-site" convey the distinction between inside and outside the station fence, respectively.
SALEM - UNIT 2 6-9 Amencment No. 76
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- /E :,' :.5 COMP 0SITION ', continued)
NSR shall utilize a system of qualified reviewers from other tecnnical organizations to augment its expertise in the disciplines of Section 6.5.2.4 Such qualified reviewers shall meet the same qualification requirements as tne NSR staff, and will not have been involved with performance of the origir.al work.
The Manager - Off-Site Review and Staff sh'll meet or exceed the a
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). The Manager - On Site Review and staff will meet or exceed the Qualifications described in Section 4.4 of ANS 3.1 (1981).
CONSULTANTS 6.5.2.3 Consultants shall be utilized as determined by the General Manager -
Nuclear Safety Review to provide expert advice to the NSR.
OFF-SITE REVIEW GROUP 6.5.2.4 The Off-Site Review Group (OSR) shall function to provide independent review and audit of designated activities in the areas of:
- a. Nuclear Power Plant Operations
- b. Nuclear Engineering
- c. Chemistry and Radiochemistry 7
- d. Metallurgy
- e. Instrumentation and Control
- f. Radiological Safety
- 9. Mechanical Engineering
- h. Electrical Engineering i. Quality Assurance j Nondestructive Testing
- k. Emergency Preparedness The OSR shall also function to examine plant operating characteristics. NRC issuances, industry advisories. Licensee Event Reports, and other sources wnicn may indicate areas for improving plant safety.
SALEM - UNIT 2 6-9a Amendment No. 76 A
,I REVIEW
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6.5.2.4.1 The OSR shall review:
- i..
Safety Evaluations for 1)
Changes to procedures, equipment, or systems and 2)
Tests or exper.iments completed under the provisions of Section 50.59, 10CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as definec in Section 50.59, 10CFR.
c.
Proposed tests or experiments that involve an unreviewed safety question as defined in Section 50.59, 10CFR.
d.
Proposed changes to Technical Specifications or to the Operating
- License, e.
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
g.
A[llREPORTABLEEVENTS.
h.
All recognized indications of an unanticipated deficiency in some 7
aspect of design or operation of safety-related structures, syste-'s or components.
i.
Reports and meeting minutes of the Station Operations Review Committee.
AUDITS 6.5.2.4.2 Audits of facility activities that are required to be performec under the cognizance o' OSR are listed below:
a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions t_t least once per 12 months.
b.
The performance, training, and qualifications of the entire facility staff at least once per 12 montns.
c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or methoc of operation :nat affect nuclear safety at least once per 6 months, d.
The performance of activities recuired by tne Operational Quali ty Assurance Program to meet the Criteria of Appendix "B",10CFR50, at least once per 24 months.
SALEM - UNIT 2 6-10 Amencment No. 76 i
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' AUDITS (continued) e.
The Facility. Emergency plan and implementing procedures at least once per 12 montns.
f.
The Facility Security plan and implementing procedures at least once per 12 months.
g.
Any othet area of facility operation considered appropriate by the General Managar - Nuclear Safety Review or the Vice president and Chief '.uclear Officer.
h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i.
An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 montns utilizing either cualified offsite licensee personnel or an outside fire protection firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consulcant at least once per 36 months.
k.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
.The above audits shall be conducted by the ' Nuclear Quality Assurance Department or an inhpendent consultant as required. Audit results and recommendations shall be reviewed by OSR.
IN-SITE SAFETY REVIEW GROUP 6.5.2.5 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 maintenance activities; and advice to management c' 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.
RESP 0NSIBILITIES 6.5.2.5.1 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, eouipment, and systems.
SALEM - UNIT 2 6-11 Amendment No. 76
0:N'*3*M :'fE : W :iC.S Resp 0NSIBILITIES (continued) c.
Review of selected procedures and plant activities inclucing 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.
NSR AUTHORITY 6.5.2.6 NSR shall report to and advise the Vice President and Chief Nuclear Officer on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.
6.5.2.7 Records of NSR activities shall be prepared and maintained. Reports of reviews and audits shall be distributed as follows:
a.
Reports of reviews encompassed by Section 6.5.2.4.1 above, shall be prepared, approved and forwarded to the Vice President and Chief Nuclear Officer, within 14 days following completion of the review, b.
Audit recorts encompassed by Section 6.5.2.4.2 above, shall be forwardec to the Vice President and Chief Nuclear Officer and to the management positions responsible for the areas aualled within 30 days after completion of the audit.
_-5.3 ' TECHNICAL REVIEW AND CONTROL 6
ACTIVITIES 6.5.3.1 Programs recuired by Technical Specification 6.8 and other procecures 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 I
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 l
independently reviewed by an individual knowledgeable in the subject l
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 procedure or procedure change. Procedures other than Station Administrative procedures wili
)
be approved by the appropriate Station Department Manager or by the l
Assistant General Manager - Salem Operations. Each Station Department Manager shall be responsible for a predesignated class of procedures. The General Manager - Salem Operations snall approve Station Admir,istrative procedures, Security Plan implementing procedures and Emergency Plan implementing procedures.
- Not responsible for sign-off function SALEM - UNIT 2 6-12 Amendment No. 76
ACW N*S~RA* pie CN'RC.S a
PROCEDURE RELATED DOCUMENTS (continued) i b.
On-the-spot changes to procedures which clearly do not cnange tre
)
intent of the approved procedures shall be approved by two memoers I
of the plant management staff, at least one of whom nolds a Senior
{
Reactor Operator License. Revisions to procedu:es which may involve l
a change in intent of the approved procedures, shall be reviewed in j
accordance with Section 6.5.3.2.a.above.
c.
Individuals responsible for reviews performed in accordance with item 6.5.3.2a above shall be approved by the SORC Chairman and designated as Station Qualif.ied Reviewers. A system of Station Qualified Reviewers, each of whom shall possess qualifications that meet or exceed the requirements of Section 4.4 of ANSI N18.1 - 1971, shall be maintained by the SORC Chairman. Each review shall include a written determination of whether or not additionel i
cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel.
d.
If the Department Manager determines that the documents involved contain significant safety issues, the documents Srill be forwarded for SORC review and also to NSR for an independent review to determine whether or not an unreviewed safety question is involved, Pursuant to 10CFR50.59, NRC approval of items involving uweviewed safety questions or Technical Specification changes shall be obtained prior to implementation.
'NON-PROCEDURE RELATED DOCUMENTS f:r. 5. 3. 3 Tests or experiments, changes to Technical Specifications, and
' changes to equipment or systems shall be forwarded for 50RC review and also to NSR for an independent review to determine whether or not an unreviewed safety question is involved. The results of NSR reviews will be providea to 50RC.
Recommendations for approval are made by SORC to the General Manager - Sa em Operations. Pursuant to 10CFR50.59, NRC approval of items involving unreviewed safety questions or requiring Technical Specification changes shall ce obtained prior to implementation.
RECORDS 6.5.3.4 Written records of reviews performed in accordance with itme 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, NSR and/or NRC as necessary when their reviews are reouirec.
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 oursvar-to the requirements of Section 50.73 to 10CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the SORC and tne resultant Licensee Event Report submitted to NSR and the Vice President and Chief Nuclear Officer.
SALEM - UNIT 2 6-12a Amencment No. 76
r-Trw.3c5~wa"!vY C09F 0;S
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6.7 SAFETY LIMIT VIOLATION 6.7.1 The 'ollowing actions shall be taken in the event a safety Limit is violated:
a.
The unit shall be placed in at least :10r 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 Vice President and Chief Nuclear Officer and General Manager.- 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 Linist Violation Report shall be prepared. The report shall be reviewed by the 50RC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility cemponents, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the General Manager - Nuclear Safety Review and the Vice President and Chief Nuclear Officer within 14 days of the violation.
SALEM - UNIT 2 6-12b Amencment No. 76 1
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