ML20059C186
| ML20059C186 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/22/1993 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20059C171 | List: |
| References | |
| NUDOCS 9401040420 | |
| Download: ML20059C186 (22) | |
Text
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ATTACIIM ENT 1 i
Proposed License Amendment No.186, Revision 1 Supplemental Infonnation i
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-l 9401040420 931222 B
DR ADOCK 05000312 y PDR 3;j
s RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS
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INDEX DESIGN FEATURES S.ECTION EAGE D5.1 SITE.........
05-1 D5.1.1 EMERGENCY PLANNING ZONE D5-1 05.1.2 SITE BOUNDARY FOR GASEOUS EFFLUENT.....
D5-1 05.1.3 BOUNDARY FOR LIQUID EFFLUENT...
D5-1" 05.2 SPENT FUEL STORAGE FACILITIES...
DS-1 D5.2.1 SPENT FUEL STORAGE RACKS AND FAILED FUEL STORAGE CONTAINER RACK.
D5-1 D5.2.2 SPENT FUEL POOL AND STORAGE RACK DESIGN.
D5-1 ADMINISTRATIVE CONTROLS SECTION EAGE D6.1 RES.'ONSIBILITY.
06-1 D6-1 D6.2 ORGANIZATION.
D6.2.1 CORPORATE AND ONSITE ORGANIZATION.
D6-1 06-2 D6.2.2 FACILITY STAFF.
06.3 FACILITY STAFF QUALIFICATIONS.............
06-3 D6.4 TRAINING......
06-3 D6.5 REVIEH AND AUDIT.
06-4 D6.5.1 PLANT REVIEW COMMITTEE (PRC)
D6-4 FUNCTION.
D6-4 COMPOSITION.
D6-4 MEMBERSHIP......
D6-4 MEETING FREQUENCY.....
06-4 QUORUM..............
D6-4 RESPONSIBILITIES......
D6-5 AUTHORITY....
D6-6 RECORDS.......
06-6 D6.5.2 MANAGEMENT SAFETY REVIEH COMMITTEE (MSRC).
06-6 FUNCTION.
D6-6 D6-6 i
COMPOSITION.....
MEMBERSHIP.........
D6-7 j
MEETING FREQUENCY..
06-7 u
D6-7 j
QUORUM..
REVIEH...
D6-7 AUTHORITY..
D6-8
.i RECORDS.
D6-8 06 5.3 TECHNICAL REVIEH AND CONTROL.
D6.
D6.5.4 AUDITS D6-10 06-11 06.6 LICENSEE EVENT REPORT.......
06.7
-NOT USED.
D6-11 D6.8 PROCEDURES, PLANS, MANUALS, AND PROGRAMS....
06-11 Amendment No. 119 DI-2 l
1
RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS INDEX ADMINISTRATIVE CONTROLS (Continued)
SECTION EAGE D6.9 REPORTING REQUIREMENTS D6-14 D6.9.1 ROUTINE REPORTS........
06-14 D6.9.2 ANNUAL RADIOLOGICAL REPORTS..
06...........
D6.9.3 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT....
06-15 D6.9.4 ANNUAL REPORT..
06-15 D6.9.5 LICENSEE EVENT REPORT.
D6-15 D6.9.6 ENVIRONMENTAL REPORTS.
06-15 D6.9.7 SPECIAL REPORTS..
06-16 06.10 RECORD RETENTION...................
D6-16 D6.11 RADIATION PROTECTION PROGRAM 06-17 06.12 HIGH RADIATION AREA......
06-18 06.13 PROCESS CONTROL PROGRAM (PCP).
D6-18 D6.14 0FFSITE DOSE CALCULATION AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUALS.......
06-19 LIST OF TABLES Table Eagg 01-1 SURVEILLANCE INTERVALS 01-4 D3.5-1 SPENT FUEL POOL HATER CHEMISTRY 03/4-6 D6.2-1 MINIMUM SHIFT CREH REQUIREMENTS D6-3 LIST OF FIGURES Fiaure EASA DS.1-1 EMERGENCY PLANNING ZONE D5-2 05.1-2 SITE BOUNDARY FOR GASEOUS EFFLUENT 05 05.1-3 SITE BOUNDARY FOR LIQUID EFFLUENT 05-4 Amendment No. 119 DI-3
RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS D6.0 ADMINISTRATIVE CONTROLS D6.1 RESPONSIBILITY D6.1.1 The Manager, Plant Closure & Decommissioning (Plant Manager) shall be responsible l
for the management of the overall facility, the operation and maintenance of the plant, and ensuring the safe storage of irradiated core components, and shall delegate in writing the succession of his responsibilities during his absences.
D6.1.2 The Shift Supervisor (or a qualified, designated individual) shall be responsible for the control room command function. A management directive to that elTect, signed by the Plant Manager, shall be issued to all plant personnel on an ANNUAL basis.
i D6.2 ORGANIZATION D6.21 CORPORATE AND ON-SITE ORGANIZATIONS Corporate and on-site organizations shall be established for corporate management and facility operation respectively during the PERMANENTLY DEFUELED MODE. The orgamzations shall include the positions responsible for activities afTecting the safe storage ofirradiated core components and the overall safety of the facility.
Lines of authority, responsibility, and communication shall be established and defined for a.
the highest management levels through intermediate levels to and including all operating orgamzation 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. The organization and responsibilities shall be documented in the Defueled Safety Analysis Report (DSAR).
l b.
The Plant Manager shall be responsible for overall unit safe operation and shall have l
control over those on-site activities necessary for safe operation and maintenance of the plant.
The General Manager (GM), through the Assistant General Manager (AGM) and Chief c.
Operations Officer and the Deputy AGM, Operations, shall have corporate responsibility for overall safe op? ration of the facility and shall take any measures needed to ensure :
acceptable performance of the stalTin operating, maintaining, and providing technical support to the facility to ensure NUCLEAR SAFETY.
i d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate on-site manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures. The Quality organization has the authority to take any issue concerning the quality of operations at Rancho Seco to the Deputy AGM, Operations.
Proposed Amendment No.186 Revision 1 D6-1
RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTR ATIVE CONTROLS (Continued)
D612 FACII ITY STAFF The facility organization shall be as shown in the DSAR, and:
a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table D6.2-1.
b.
At least one individual qualified to stand watch in the Control Room (a Non-Certified Shutdown Control Room Operator or a Certified Fuel Handler) shall be in the Control Room when fuel is in the spent fuel pool.
An individual qualified in radiation protection practices and procedures shall be on site c.
during fuel handling operations when fuel is in the spent fuel pool.
d.
All fuel handling operations shall be directly supervised by a Certified Fuel Handler.
Administrative procedures shall be developed and im,lemented tc limit the working hours e.
of facility staff who perform functions important to t le safe storage ofirradiated fuel assemblies; e.g., Certified Fuel Handlers, radiation protection personnel, non certified operators, and key maintenance personnel.
Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal shift schedule. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or L
during major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, a.
excluding shift turnover time, b.
An individuS chould not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.
c.
A break of at least eight hours should be allowed between work periods, including shift turnover time.
d.
The use of overtime should be considered on an individual basis and not for the entire stafT on a shift.
Any deviation from the above guidelines shall be authorized by the Plant Manager or l
designee, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed semiannually by the Plant Manager or designee to l
assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.
Proposed Amendment No.186, Revisions 1 D6-2
RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS (Continued)
FACILITY STAFF (Continued) f.
The individual who directly supervises the Shift Supervisors shall be a Certified Fuel Handler.
TABLE D6.2-1 MINIMUM SHIFT CREW REQUIREMENTS
- NUMBER FOR POSITION PERMANENTLY DEFUELED MODE Shift Supervisor **
1 Non-Certified Operator 1
Minimum Total Personnel 2
In the event that any member of a minimum shift crew is absent or incapacitated due to illness or injury, a qualified replacement shall be designated to report on site within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Under these circumstances, the remaining shift crew member must stay in the control room until the replacement shift crew member arrives in the control room.
The Shift Supervisor shall be a Certified Fuel Handler.
l D6.3 FACILITY STAFF OUALIFICATIONS 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 assigned the function of the
{.
Radiation Protection Manager, who shall meet or exceed the qualifications of Regulatory _ Guide 1.8, September 1975.
D6.4 TRAINING A training program for the unit stafT shall be maintained under the direction of the Plant Manager and meet or exceed the requirements and recommendations of ANSI N18.1-1971, Section 5.5. A retraining and replacement training program for thb Certified Fuel Handlers shall be conducted in accordance with a NRC approved traimng program.
Proposed Amendment No.186, Revision 1 D6-3
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RANCHO SECO UNIT I PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS (Continued)
D6.5 REVIEW AND AUDIT D6.51 PLANT REVIEW COMMITTEE (PRC)
FUNCTION D6.5.1.1 The PRC shall function to advise the Plant Manager on matters related to NUCLEAR l
SAFETY.
COMPOSITION D6.5.1.2 The PRC shall be composed of a Chairman and a minimum of four members.
MEMBERSHIP D6.5.1.3 Membership of the PRC shall be as defined below:
A list of members made up of personnel filling positions in the Nuclear Organization and a.
others who meet or exceed the minimum qualifications of ANSI N18.1-1971, Section 4.2 or 4.4, shall be developed and approved by the Deputy AGM, Operations.
l b.
A list of alternate members of the PRC shall be developed and approved by the Deputy AGM, Operations.
The Chairman of the PRC shall be appointed by the Deputy AGM, Operations. When a l
c.
meeting is scheduled or an emergency meeting is necessary, and the PRC Chairman will be.
absent, an alternate Chairman may be designated by the PRC Chairman or the Deputy AGM, Operations from among the PRC members in Specification D6.5.1.2.
MEETING FREOUENCY D6.5.1.4 The PRC shall meet at least once per calendar month or more frequently as convened by the PRC Chairman, or as directed by the Plant Manager.
OUORUM D6.5.1.5 A Quorum of the PRC shall consist of a majority of the members in Specification D6.5.1.2 including the Chairman or alternate Chairman. No more than two alternates shall participate in PRC activities at any one time for the purpose of establishing a quorum, q
i Proposed I
Amendment No.186, Revision 1 D6-4
RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS
' ADMINISTR ATIVE CONTROLS (Continued)
RESPONSIBILITIES D6.5.1.6 The PRC shall be responsible for review of:
a.
The required safety evaluation of: (1) all procedures and programs required by Specification D6.8 and changes thereto, and (2) any other proposed procedures or programs or changes thereto which are as determined by the Plant Manager to affect l
NUCLEAR SAFETY.
b.
The safety evaluations of proposed tests and experiments that affect NUCLEAR SAFETY.
Proposed changes to the Technical Specifications or the Facility Operating License c.
(Possession Only).
d.
All safety evaluations of proposed changes or modifications to plant systems or equipment that affect NUCLEAR SAFETY. Items which are determined by a qualified reviewer as not involving an unreviewed safety question, a change of Technical Specifica'. ions, or a change in a licensing basis document need not be reviewed by the PRC.
Investigations of all violations of the Technical Specifications to determine adequacy of e.
corrective ac: ion and to detect any degrading trend.
f.
Facility operations to detect potential safety hazards.
Events requir' g a Licensee Event Report as defined by 10 CFR 50.73 and NUREG-1022 m
g.
to determine adequacy of corrective action and to detect any degrading trend. (See Specification D6.9.5.)
h.
Special investigations and reports thereon as requested by the Plant Manager, i.
The Physical Security Plan and changes thereto.
- j.
The Emergency Plan and changes thereto.
k.-
The Fire Protection Plan Program and changes thereto.
1.
Changes to the PROCESS CONTROL PROGRAM, the OFF-SITE DOSE CALCULATION M ANUAL and the RADIOLOGICAL ENVIRONMENTAL
. MONITORING PROGRAM MANUAL. (See Specifications D6.13 and D6.14.).
m.
Major changes to the Radioactive Waste Treatment Systems (Liquid, Gaseous and Solid).
Review of any accidental, unplanned, or uncontrolled release of radioactive material to the --
n.
environs, including the preparation and forwarding of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence. The PRC shall forward these reports to the Plant Manager and the MSRC.
Proposed Amendment No.186, Revision 1 D6-5
RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS (Continued)
AUTHORITY D6.5.1.7 The PRC shall:
Recommend in writing to the Plant Manager approval or disapproval ofitems considered l
a.
under Specification D6.5.1.6.
b.
Render determinations in writing with regard to whether or not each item considered under SpeciGcations D6.5.1.6a through e, and m above constitutes an unreviewed safety question.
4
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c.
Provide immediate written notiGeation to the MSRC Chairman of disagree. ment between the PRC and the Plant Manager; however, the Plant Manager shall have responsibility for l
resolution of such disagreements pursuant to SpeciGcation D6.5.1.1.
RECORDS D6.5.1.8 Minutes of each PRC meeting, including appropriate documentation of reviews encompassed by Specification D6.5.1.6e and g, shall be prepared, approved, and forwarded to the Plant Manager and to the MSRC Chairman within 14 days following each meeting.
.l D6.5.2 MANAGEMENT SAFETY REVIEW COMMITTEE (MSRC)
FUNCTION D6.5.2.1 The MSRC shall function to provide independent review and audit of designated activities in the areas of:
a.
Facility Operation b.
Engineering / Nuclear Engineering c.
Chemistry and Radiochemistry d.
Radiological Safety e.
Quality Assurance Practices COMPOSITION D6.5.2.2 The MSRC shall be composed of a Chairman and a minimum of four members. The MSRC membership shall be made up of direct reports to the Plant Manager or above as shown l
on the Nuclear Organization or of other personnel meeting or exceeding the minimum qualifications of ANSI /ANS 3.1-1981, Section 4.7.2.
Proposed Amendment No.186, Revision 1 D6-6
RANCHO SECO UNIT 1-PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTR ATIVE CONTROLS (Continued)
MEMBERSHIP D6.5.2.3 The Chairman of the MSRC shall be appointed by the AGM & Chief Operations Officer. A current list of members and alternates as described in Specification D6.5.2.2 shall be developed and approved by the AGM & Chief Operations OfGcer and maintained by the MSRC Secretary. In the absence of the Chairman, an Alternate Chairman may be desip,nated by the MSRC Chairman or the AGM & Chief Operations Officer. The Alternate Chairman shall be selected from among the MSRC members in SpeciGeation D6.5.2.2.
MEETING FREOUENCY D6.5.2.4 The MSRC shall meet at least once per calendar quarter and as convened by the MSRC Chairman or as directed by the Deputy AGM, Operations.
l OUORUM D6.5.2.5 A quorum of MSRC shall consist of a majority of the members in Specification.
D6.5.2.2, including the Chairman or alternate Chairman. No more than two alternates shall participate in MSRC activities at any one time for the purpose of establishing a quorum. No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW D6.5.2.6 The MSRC shall be responsible for review of:
The safety evaluation for (1) changes to procedures, equipment or systems, and (2) tests or a.
experiments completed under the provisions of 10 CFR 50.59 to verify that such actions do not constitute on unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
i Proposed tests or experiments which involve an unreviewed safety question as defined in c.
d.
Proposed changes in Technical Specifications or the Facility Operating License (Possession Only).
Violations of applicable statutes, codes, regulations, orders Technical Specifications, e.
license requirements, or ofinternal procedures or instructions having NUCLEAR SAFETY signiGeance, f.
Signincant operating abnormalities or deviations from normal and expected performance of plant equipment that affect NUCLEAR SAFETY.
LICENSEE EVENT REPORTS as defined by 10 CFR 50.73 and NUREG-1022.
g.
Proposed Amendment No.186, Revision 1 D6-7 9-
RANCHO SECO UNIT I PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTR ATIVE CONTROLS (Continued)
REVIEW (Continued) h.
Any indication of an identified significant deficiency in the design or operation of safety-related structures, systems, or components.
i.
Reports and meeting minutes of the PRC.
j.
Any facility activity brought to the attention of the MSRC by the District's executive management which may be indicative of conditions adverse to NUCLEAR SAFETY.
k.
The MSRC shall provide oversight review of:
The District Quality Program, including the Audit Program content, implementation and audit reports, The Radioactive Waste Control Program, and Effectiveness of the LICENSEE EVENT REPORT Program per Specification D6.6.
AUTHORITY D6.5.2.7 The MSRC shall:
Report to and advise the Deputy AGM, Operations of those areas of responsibility l
a.
specified in Specification D6.5.2.6.
b.
Recommend to the Deputy AGM, Operations other areas of facility operation for which l
the MSRC has determined the need for additional auditing per Specification D6.5.4g.
Advise the Deputy AGM, Operations of the need for independent auditing of facility l-c.
operations.
RECORDS D6.5.2.8 Minutes of each MSRC meeting and separate documentation of reviews encompassed by Specifications 6.5.2.6d through h shall be prepared, approved, and forwarded to the Deputy AGM, Operations within 14 days following each meeting.
Proposed Amendment No.186, Revision 1 D6-8
RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS (Continued)
D613 TECHNICAL REVIEW AND CONTROL i
Activities which afTect NUCLEAR SAFETY shall be conducted as follows:
Procedures, plans, manuals, and programs required by Specification D6.8 and other a.
procedures, plans, manuals, and programs which affect plant NUCLEAR SAFETY, and changes thereto, shall be prepared, reviewed and approved. Each such procedure, plan, manual, and program or change thereto shall be reviewed by an individual (s) other than the preparer, but who may be from the same organization as the preparer of the procedure, plan, manual and program or change thereto. Programs, plans, manuals, and procedures other than plant administrative procedures will be approved as delineated in writing by the Plant Manager, but not lower than a direct report to the Plant Manager.
l Such procedures, plans, manuals and programs shall be reviewed periodically in accordance with administrative procedures.
The Plant Manager will approve plant administrative procedures, Security Plan l
Implementing Procedures and Emergency Plan implementing Procedures.
Approval of temporary procedure changes which clearly do not change the intent of the approved procedure can be made by two members of the plant management staff, at least one of whom is a Certified Fuel Handler. The change shall be documented, reviewed and approved by the procedure's approval authority within 14 days ofimplementation.
b.
Proposed changes or modifications to plant systems or equipment that affect NUCLEAR
)
SAFETY shall be reviewed by an individual (s) other than the individual (s) who designed j
the modification, but who may be from the same organization as the individual (s) who designed the modifications. Such modifications shall be approved by the Plant Manager
]
or his designee as delineated in writing, but not lower than a direct report to the Plant Manager.
)
Proposed tests and experiments which affect plant NUCLEAR SAFETY and are not c.
addressed in the DSAR shall be reviewed by an individual (s) other than the individual (s) l who prepared the proposed test or experiment. Such tests or experiments shall be approved by the Plant Manager or his designee as delineated in writing, but not lower i
l than a direct report to the Plant Manager.
d.
Individuals responsible for reviews performed in accordance with Specification D6.5.3a, b and c shall meet or exceed the qualification requirements of Section 4.4 of ANSI i
N18.1-1971. Each such review shall include a determination of whether or not additional, cross-disciplinary review is necessary. If deemed necessary, such a review shall be performed by the review personnel of the appropriate discipline. A list of qualified reviewers for the independent reviews described in D6.5.3a, b and c above shall be established by the Plant Manager.
Proposed Amendment No.186, Revision 1 D6-9
RANCHO SECO UNIT I PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS et ADMINISTR ATIVE CONTROLS (Continued)
TECHNICAL REVIEW AND CONTROL (Continued)
Events reportable pursuant to Specification D6.9.5 and violations of Technical e.
Specifications shall be investigated and a report prepared which evaluates the event and which provides recommendations to prevent recurrence. Such reports shall be reviewed by the PRC and forwarded to the Plant Manager and the MSRC Chairman.
l D6.5.4 AUDITS Audits of facility activities shall be performed under the cognizance of the Quality organization supervisor. These audits shall encompass:
a.
The conformance of facility o wration to provisions contained within the Technical Specifications and applicable icense conditions at least once per year.
b.
The performance and qualifications of the entire Rancho Seco facility technical stafT at.
least once per year.
c.
The result of actions taken to correct deficiencies occurring in facility equipment, structures, systems or methods of operation that affect NUCLEAR SAFETY at least once per 6 MONTHS for those changes not previously audited.
d.
The performance of activities required by the Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix B at least once per 2 years.
e.
The Facility Emergency Plan and implementing procedures at least once per year.
f.
The Facility Security Plan and implementing procedures at least once per year.
g.
Any other area of facility operation considered appropriate by the Plant Manager or the Deputy AGM, Operations.
h.
Compliance with fire protection requirements and implementing procedures at least once per 2 years.
i.
An independent fire protection and loss prevention inspection and audit shall be performed ANNUALLY using either qualified off-site 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 an outside qualified fire consultant at intervals no greater than 3 years.
k.
The Radiological Environmental Monitoring Program (REMP) and the results thereof at least once per year.
1.
The ODCM and implementing procedures at least once per 2 years.
Proposed Amendment No.186, Revision 1 D6-10
i RANCHO SECO UNIT 1 f
PERMANENTLY DEFUELED
]
i TECHNICAL SPECIFICATIONS ADMINISTR ATIVE CONTROL S (Continued)
AUDITS (Continued)
The PCP and implementing procedures for processing and packaging of radioactive m.
wastes from liquid systems at least once per 2 years.
The performance of activities required by the Quality Assurance Program for Effluent n.
Control and Environmental Monitoring at least once per year.
Audit reports of reviews encompassed by Specification D6.5.4 shall be forwarded to the Deputy AGM, Operations, the Plant Manager, the MSRC Chairman, and the management positions responsible for the areas reviewed within 30 days after completion.
D6.6 LICENSEE EVENT REPORT ACTION The following actions shall be taken for events which are reportable as LICENSEE EVENT REPORTS:
a.
The Commission shall be notified and a report submitted per Specification D6.9.5, pursuant to the requirements of 10 CFR 20.405,50.73, and appropriate portions of 73.71 (as described in the Rancho Seco Physical Security Plan) and b.
Each LICENSEE EVENT REPORT shall be reviewed by the PRC and the results of this review submitted to the MSRC. Each LICENSEE EVENT REPORT shall be reviewed and approved by the Plant Manager or designee.
l D.fL2 -NOT USED-D6.8 PROCEDURES. PLANS. M ANUAI_S. AND PROGRAMS D6.8.1 Written procedures, plans, manuals, and programs shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Safety Guide 33, November a.
1972 b.
Irradiated Core Component Storage, Fuel Movement Operations, Decommissioning, and Decontamination Surveillance and test activities on equipment required for long-term safe storage of 3
c.
irradiated core components d.
Security Plan implementation e.
Emergency Plan unplementation f.
Fire Protection Program Plan implementation J.
PCP implementation i
ODCM implementation i.
REMP MANUAL implementation j.
Quality Assurance Program for Effluent Control and Environmental Monitoring using the guidance of Regulatory Guide 4.15, Revision 1, February 1979 k.
Certified Fuel Handler Training Program implementation L
Quality Assurance Programimplementation m.
Radiation Protection Program unplementation Proposed Amendment No.186, Revision 1 D6-ll
RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS (Continued)
PROCEDURES. PLANS. MANUALS. AND PROGRAMS (Continued)
D6.8.2 Each procedure, plan, manual, and program of Specification D6.8.1 above and changes thereto shall be reviewed and approved as set forth in Specification.06.5.
D6.8.3 The following programs shall be established, implemented, and maintained:
a.
Radioactive Effluent Controls Proaram A program shall be provided confctming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBER (S) 0F THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program (1) shall be contained in the ODCM,.(2) shall be implemented by Administrative, Chemistry, and Operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
1)
Limitations on the operability of racioactive 11guld and gaseous monitoring instrumentation including surveillance tests and setpoint
~
determination in accordance with the methodology in the ODCM, 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B Table II, Column 2, 3)
Monitoring, sampling, and analysis of radioactive 11guld and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, 4)
Limitations on the annual and quarterly doses or dose commitment to MEMBER (S) 0F THE PUBLIC from radioactive materials in 11guld effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar-year in accordance with the methodology and parameters in the 00CM at least every 31 days, 6)
Limitations on the OPERABILITY and use of the gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the i
projected doses in a 31-dav period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR 50, Amendment No. 119 D6-12
RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTRATTVE CONTROLS (Continued)
PROCEDURES. PLANS. MANUALS. AND PROGRAMS (Continued) 7)
Limitations on the OPERABILITY and use of the liquid effluent treatment system to ensure that the-appropriate portions of this system are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 8 1/3 percent (1/12) of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR 50.
8)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR 20, Appendix B, Table II, Column 1, 9)
Limitations on the annual and quarterly air doses resulting'from noble gases released in gaseous effluents from each unit to areas beyond-the SITE BOUNDARY conforming to Appendix I to 10 CFR 50, 10)
Limitations on the annual and quarterly doses to a HEMBER(S) 0F THE PUBLIC from Tritium and all radiontclides in pa.-ticulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR 50, 11)
Limitations on the annual dose or dose commitment to MEMBER (S) 0F THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
b.
Radioloaical Environmental Monitorina Proaram (REMP)
A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.
The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
The program shall (1) be contained in the REMP HANUAL, (2) conform to the guidance of Appendix I to 10 CFR 50, and (3) include the following:
1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the REMP MANUAL, 2)
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and i
Amendment No. 119 D6-13
4 RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS I
ADMINISTRATIVE CONTROLS (Continued)
PROCEDURES. PLANS. MANUALS. AND PROGRAMS (Continued) 3)
Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample-matrices are performed as part of the quality assurance program for env;.~vomenhal monitoring.
D6.8.4 Each program in Specification D6.8.3 and changes thereto shall be reviewed and approve 0 as set forth in Specification D6.5 and D6.14.
D6.9 REPORTING REQUIREMENTS D6.9.1 ROUTINE REPORTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Region V Office unless otherwise noted.
D6.9.2 ANNUAL RADIOLOGICAL REPORTS Annual reports covering the activities of the unit, as described below,.for the previous calendar year shall be submitted as follows:
D6.9.2.1 Annual Occuoational Radiation Exoosure Reoort The annual Occupational Radiation Exposure Report for the previous calendar year shall be submitted to the Commission within the first calendar quarter of each calendar year in compilance with 10 CFR 20.407.
D6.9.2.2 Annual Exoosure Reoort The Annual Exposure Report for the previous calendar year shall be submitted to the Commission within the first calendar quarter of each calendar year in accordance with the guidance contained in Regulatory Guide 1.16.
D6.9.2.3 Annual Radiolooical Environmental Ooeratina Reoort The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May.1 of each year.
The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.
The material provided shall be consistent with the objectives outlined in (1) the ODCM, (2) the REMP MANUAL, and (3)
Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR 50.
Amendment No. 119 D6-14
?
1 RANCHO SECO UNYT 1 PERMANENTLY DEFUELED 1
TECHNICAL SPECIFICATIONS j
ADMINISTRATIVE CONTROLS (Continued)
D6.9.3 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The Semlannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months shall be submitted within 60 days after January 1 and July 1 of each year.
The report shall include a summary of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR 50.
D6.9.4 ANNUAL REPORT A routine report consisting of shutdown statistics, a narrative summary of shutdown experience, major maintenance of structures, systems, and components required for long-term safe storage of irradiated fuel assemblies, and tabulations of facility changes, tests or experiments required pursuant to 10 CFR 50.59(b) shall be submitted on an annual basis to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Office, postmarked no later than 30 days following the twelve month period covered by the report.
D6.9.5 LICENSEE EVENT REPORT The types of events listed in 10 CFR 20.405, 50.73 and the appropriate portions of 73.71 (as described in the Rancho Seco Physical Security Plan) shall be the subject of LICENSEE EVENT REPORTS, submitted to the U.S. Nuclear Regulatory Commission (NRC), Document Control Oesk Washington, D.C. 20555, within the time requirements of 10 CFR 20.405, 50.73 and 73.71. An additional copy shall also be submitted to the Regional Administrator of the Region V Office.
The written report shall include a completed copy of a LICENSEE EVENT REPORT form, pursuant to 10 CFR 20.405, 50 73 and 73.71 and the guidance of NUREG-1022, and a description of corrective actions and measures to prevent recurrence.
Supplemental reports may be required to fully describe final resolution of the occurrence.
For corrected or supplemental reports, a-LICENSEE EVENT REPORT shall be completed and reference shall be made to the original report date, pursuant to the requirements of 10 CFR 20.405, 50.73 or 73.71 as appropriate.
D6.9.6 ENVIRONMENTAL REPORTS a.
When a change to the plant design or to the plant operation is planned which would have a significant adverse effect on the environment or.which involves an environmental matter or question not previously reviewed and evaluated by the NRC, a report on the change will be made to the NRC prior to implementation.
The report will include a description and evaluation-of the change, including a supporting benefit-cost analysis.
1 Amendment No. 119 D6-15 j
RANCHO SFC0 UNfT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS (Continued)
EEylBONMENTAL REPORTS (Continued) b.
Changes or additions to permits and certificates required by Federal, State, local and regional authorities for the protection of the environment will be reported.
When the required changes are submitted to the concerned agency for approval, they will also be submitted to the NRC for information.
The submittal will include an evaluation of the environmental impact of the change.
D6.9.7 SPECIAL REPORTS Special reports shall be submitted to the Regional Administrator of the Region V Office within the time period specified for each report.
D6.10 RECORD RETENTION D6.10.1 The following records. shall be retained for at least 5 years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to NUCLEAR SAFETY.
c.
LICENSEE EVENT REPORTS.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of reactor tests and experiments.
f.
Records of changes made to Operating Procedures.
)
g.
Records of radioactive shipments.
h.
Records of sealed source leak tests and results.
1.
Records of annual physical inventory of all sealed source _ material of.
record.
j.
Records and logs of facility activities in the PERMANENTLY DEFUELED MODE.
j D6.10.2 The following records shall be retained-for the duration of the j
Facility Operating License.
a.
Record and drawing changes reflecting facility design modifications made
'l to systems and equipment described in the Updated Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
Amendment No. 119 D6-16
-1 RANCHO SECO UNIT 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS (Continued)
RECORD RETENTION (Continued) c.
Records of facility radiation and contamination surveys.
d.
Records of radiation exposure for all individuals entering radi&cion i
control areas.
i e.
Records of gaseous and liquid radioactive material released to the environs.
l f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
g.
Records of training and qualification for current members of the plant operating staff.
h.
Records of in-service inspections previously performed pursuant to the Appendix A Technical Specifications.
1.
Records of quality assurance activities required by the QA Manual.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PRC and MSRC.
1.
Records of the environmental qualification of safety related electrical equipment previously generated pursuant to the Appendix A Technical Specifications.
m.
Records for the Radiological Environmental Monitoring Program.
n.
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.
o.
Records of reviews performed for changes made to the ODCM, REMP-MANUAL, and the PCP.
p.
Records of Plant Closure and Decommissioning activities performeo.
D6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR 19 and 10 CFR 20, and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
Amendment No. 119 D6-17 I
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RANCHO SECO UNIT 1 PERMANENTLY DEFUELED g
TECHNICAL SPECIFICATIONS f
ADMINISTR ATIVE CONTROLS (Continued)
D6.12 HIGH RADIATION AREA D6.12.1 In lieu of the " control device" or " alarm signal" required by 10 CFR 20.203(c)(2).
a.
Each High Radiation Area in which the intensity of radiation is equal to or greater than 100 mrem /hr but less than 1,000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area, and entrance thereto shall be controlled by issuance of a Radiation Work Permit. Any individual or group ofindividuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
Each High Radiation Area in which the intensity of radiation is equal to or greater than 1,000 mrem /br shall be subject to the provisions of Specification D6.12.la above, and, in addition, locked doors shall be provided to prevent unauthorized entry into such area.
The keys shall be maintained under the administrative control of the on duty Shift Supervisor. In lieu oflocked doors, certain areas within the Reactor Building, where no enclosure exists for the purpose oflocking, and where no enclosure can be reasonably constructed, shall be barricaded, conspicuously posted, and a conspicuous visible or audible signal shall be activated such that an individual is made aware of the presence of the High Radiation Area (>l,000 mrem /hr).
D6.13 PROCESS CONTROL PROGRAM (PCP)
D6.13.1 The required content of the PCP is defined in Specification DI.6.
D6.13.2 Licensee-initiated changes to the PCP:
Shall be documented and records of reviews performed shall be retained as required by a.
Specification D6.10.2.o. This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)
A determination that the change will maintain the overall conformance of the processed waste product to existing requirements of Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the PRC and approval by the Plant Manager.
Proposed Amendment No.186, Revision 1 D6-18
E 1
RANCHO SECO UNIT 1
+
PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS (Continued)
D6.14 OFF-SITE DOSE CALCULATION AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUALS D6.14.1 The required content of the ODCM is defined in Specification DI.7.
l D6.14.2 The required content of the REMP MANUAL is defined in DI.10.
D6.14.3 Licensee-initiated changes to the ODCM or REMP MANUALi
- i Shall be documented and records of reviews performed shall be retained as required by-a.
Specification D6.10.2.o. This documentation shall contain:
'j l)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)
A determination that the change will maintain the level of radioactive efTluent control required by 10 CFR 20.106,40 CFR 190,10 CFR 50.36a, and Appendix I-to 10 CFR 50 and not adversely impact the accuracy or reliability of efTluent dose.
1 or setpoint calculations.
b.
Shall become effective after review and acceptance by the PRC and approval by the Plant
- Manager, c.
Shall be submitted to the Commission in the fonn of a complete, legible copy of the entire ODCM and/or REMP MANUAL as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM and/or REMP MANUAL was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that-was changed, and shall indicate the date (e.g., month / year) the change was implemented.
J s
l Proposed Amendment No.186, Revision 1
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D6-19 i
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