ML17306A572
| ML17306A572 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/04/1992 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17306A573 | List: |
| References | |
| NUDOCS 9203200221 | |
| Download: ML17306A572 (77) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 205SS ARIZONA PUBLIC SERVICE COHPANY ET A.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 AHENDHENT TO FACILITY OPERATING LICENSE 2.
Amendment No. 58 License No.
NPF-41 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison
- Company, Public Service Company of New Hexico, Los Angeles Department of Water and Power, and Southern Cal1fornia Public Power Authority (licensees),
dated August 28,
- 1991, and modified by letter dated December 30, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The faci 11ty will operate in conformity with the appl1cation, 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 Comm1ss1on's regulat1ons; D.
The issuance of this amendment will not be in1mical to the coIImon defense and security or to the health and safety of the publ1c; and E.
The 1ssuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
NPF-41 1s hereby amended to read as follows:
920320022i 9203047 f
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(2) Technical S ec1ficat1ons and Env1ronmental Protection Plan The Technical Specif1cat1ons contained 1n Appendix A, as revised through Amendment No. g8, and the Env1ronmental Protect1on Plan contained 1n Appendix 8, are hereby 1ncorporated 1nto th1s license.
APS shall operate the facility in accordance w1th the Technical Specifications and the Env1ronmental Protection Plan, except where otherwise stated 1n specific license condit1ons.
3.
This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days From the date of issuance.
FOR THE NUCLEAR REGULATORY COMHISSION
Attachment:
Changes to the Technical Specifications Theodore R. Quay, D1rector Prospect 01rectorate V
Division of Reactor Prospects III/IV/V Office of Nuclear Reactor Regulation Date of Issuance:
parch 4, 199'
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
NPF-41 DOCKET NO.
STN 50-528 Insert Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove 6-1 6-2 6-6 6-7 6-8 6-9 6-10 6-11 6-12 6-14 6-24 6-1 6-2 6-6 6-7 6-8 6-9 6-10 6"11 6-12a 6"12 6"14 6-24
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.ADMINISTRATIVE CONTROLS
- 6. 1 RESPONSIBILITY
- 6. 1. 1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the. succession to this responsibility during his absence.
- 6. 1.2 The Shift Supervisor, or during his absence from the Control
- Room, a
designated individual per Table 6.2-1, shall be responsible for the Control Room command function.
A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued to all station personnel on an annual basis.
- 6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS An offsite and an onsite organization shall be established for unit operation and corporate management.
The offsite and onsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.
Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.
These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).
b.
There shall be an individual executive position (Executive Vice President Nuclear) in the offsite organization having corporate responsibility for overall plant nuclear safety.
This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support in the plant so that continued nuclear safety is assured.
c.
There shall be individual management positions (Plant Managers) in the onsite organization having responsibility for overall unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.
d.
Although the individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.
6.2.2 UNIT STAFF a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
PALO VERDE - UNIT 1 6-1 AMENDMENT NO. 58
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ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.
Adequate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel work a nominal 40-hour week while the plant is operating.
- However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modifications, on a tem-porary basis, the following guidelines shall be followed (this ex-cludes the STA working hours):
1)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />
- straight, excluding shift turnover time.
2)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour
- period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
~3)
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work
- periods, including shift turnover time.
4)
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
C.
Any deviation from the above guidelines shall be authorized by any one of the following personnel:
Director, Technical Support; Director, PVNGS Services; General Manager, Site Radiation Protection; General Manager, Site Chemistry; General Manager, Training; Plant Manager; or their designees who are at the manager level or above, or higher levels of management, 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 in their respective groups shall be reviewed monthly by these authorized individuals or their designees to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
PALO VERDE - UNIT 1 6-2 AMENDMENT NO.
58
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s ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING DEPARTMENT ISE)
FUNCTION 6.2.3.1 The ISE Department shall function to selectively examine plant operating I
characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISE Department shall be composed of at least five, dedicated, full-time engineers located on site.
Each shall have a Bachelor's Degree in engineer-ingg or related science and at least two years professional level experience in his field.
RESPONSIBILITIES 6.2.3.3 The ISE Department shall be responsible for maintaining surveillance of selected plant activities to provide independent verification" that these activi-ties are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.
AUTHORITY
- 6. 2. 3.4 The ISE Department shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activi-ties or other means of improving plant safety to the Director, Nuclear Safety or designated alternate, Plant Manager, and the Chairman, Offsite Safety Review Committee (OSRC).
RECOROS 6.2.3.5 Records of activities performed by the ISE Oepartmeot shall be prepared, maintained, and forwarded each calendar month to the Director, Nuclear Safety or designated alternate.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical AdviSor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in MODE 1, 2, 3, or 4.
- 6. 3 UNIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI/ANS 3.1-1978 and Regulatory Guide 1.8, September
- 1975, except for the General
- Manager, Site Radiation Protection who shall meet or exceed the qualifications of Regulatory Guide 1.8, September
- 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engi-neering discipline with specific training in plant design and plant operating 6-6 "Not responsible for sign-off function.
PALO VERDE - UNIT 1 AMENDMENT NO. 58
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ADMINISTRATIVE CONTROLS
- 6. 3 UNIT STAFF UALIFICATIONS (Continued) characteristics, including transients and accidents.
An additional exception is that the Senior Reactor Operator (SRO) license requirement for the Operations Manager shall be met if either the Operations Manager or the Operations Super-visor holds a valid SRO license.
The holder of the SRO license shall direct the licensed activities of the licensed operators.
- 6. 4 TRAINING 6.4.1 A training program for the unit staff shall be maintained under the di-rection of the General
- Manager, Nuclear Training and shall meet or exceed the requirements of Section 5.0 of ANSI/ANS 3. 1, 1978 and 10 CFR 55.
The program shall include familiarization with relevant industry operational experience.
- 6. 5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)
FUNCTION 6.5.1. 1 The Plant Review Board shall function to advise the Vice President Nuclear Production or his designee on all matters related to nuclear safety.
COMPOSITION 6.5. 1.2 The PRB shall be composed of nine members from the Palo Verde management staff.
These positions will be designated by the Vice President Nuclear Production or his designee in Administrative Procedures.
The Vice President Nuclear Production or his designee shall designate the Chairman and Vice-Chairmen in writing.
The Chairman and Vice-Chairmen may be from outside the members provided that they meet ANSI/ANS 3. 1, 1978.
ALTERNATES 6.5. 1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on.a temporary basis;
- however, no more than two alternates shall participate as voting members in PRB activities at any one time.
fll EIEE 6.5. 1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman, Vice-Chairmen, or his designated alternate.
PALO VERDE - UNIT 1 6-7 AMENDMENT NO. 58
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ADMINISTRATIVE CONTROLS QUDRUH 6.5. 1.5 The quorum of the PRB necessary for the performance of the PRB respon-sibility and authority provisions of these Technical Specifications shall consist of the Chairman, Vice-Chairmen, or his designated alternate and five members including alternates.
RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible'or:
b.
C.
d.
Review of all proposed changes to Appendix "A" Technical Specifications.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Offsite Safety Review Committee (OSRC).
Review of REPORTABLE EVENTS.
Review of unit operations to detect potential nuclear safety hazards.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President-Nuclear Production or PRB Chairman.
f.
Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last PRB meeting.
AUTHORITY 6.5. 1.7 The PRB shall:
a.
Render determinations in writing with regard to whether or not each item considered under Specification 6.5. 1.6b.
above constitutes an unreviewed safety question.
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 Executive Vice President Nuclear, Vice President Nuclear Production and OSRC of disagreement between the PRB and the Vice President Nuclear Produc-tion; however, the Vice President Nuclear Production shall have responsibility for resolution of such disagreements.
RECORDS 6.5. 1.8 The PRB shall maintain written minutes of each PRB meeting that, at a
minimum, document the results of all PRB activities performed under the responsi-bilityy and authority provisions of these Technical Specifications.
Copies shall be provided to the Executive Vice President-Nuclear, Vice President-Nuclear Production, and OSRC.
PALO VERDE - UNIT 1 6"8 AMENDMENT NO. 58
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0 ADMINISTRATIVE CONTROLS 6.5.2 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.2. 1 The Vice President Nuclear Production or his designee shall assure that each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes
- thereto, is prepared by a qualified individual/organization.
Each such procedure, and changes
- thereto, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or changes
- thereto, but who may be from the same organization as
. the individual/group which prepared the procedure, or changes thereto.
6.5.2.2 Phase I - IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Technical Support or his designee as previously designated by the Vice President-Nuclear Production.
Test results shall be approved by the Director, Technical Support or his designee.
6.5.2.3 Proposed modifications to unit nuclear safety-related str uctures, systems and components shall be designed by a qualified individual/organization.
Each such modifi.cation shall be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification.
Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant Manager; or by the Director, Technical Support as previously designated by the Vice President-Nuclear Production.
6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2. 1, 6.5.2.2, and 6.5.2.3 shall be identified in station administrative. pro-cedures.
Each such review shall include a determination of whether or not addi-tional, cross-disciplinary, review is necessary.
If deemed necessary, such review shall be performed by the appropriate designated review personnel.
6.5.2.5 Proposed tests and experiments which affect station, nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Vice President Nuclear Production or his designee.
6.5.2.6 The station security program and implementing pro'cedures shall be re-viewed.
Recommended changes shall be approved by the Director, PVNGS Services I
or designated alternate and transmitted to the Vice President-Nuclear Production and to the OSRC.
I 6.5.2.7 The station emergency plan and implementing procedures shall be re-viewed.
Recommended changes shall be approved by the Director, PVNGS Services or designated alter nate and transmitted to the Vice President-Nuclear Production and to the OSRC.
6.5.2.8 The General
- Manager, Site Radiation Protection shall assure the perform-ance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposition of the corrective action to prevent recurrence.
PALO VERDE - UNIT 1 6-9 AMENDMENT NO. 58
ADMINISTRATIVE CONTROLS TECHNICAL REVIEW AND CONTROL ACTIVITIES (Continued 6.5.2.9 The Vice President Nuclear Production or his designee shall assure the performance of a review by a qualified individual/organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment
- systems, and the Pre-planned Alternate Sampling Program.
6.5.2. 10 Reports documenting each of the activities performed under Specifica-tions 6.5.2. 1 through 6.5.2.9 above shall'be maintained.
Copies shall be pro-
. vided to the Vice President-Nuclear Production and the Offsite Safety Review Committee.
6.5.3 OFFSITE SAFETY REVIEW COMMITTEE OSRC)
FUNCTION 6.5.3. 1 The OSRC shall function to provide independent review and shall be responsible for the 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 and electrical engineering h.
quality assurance practices COMPOSITION 6.5.3.2 The OSRC shall be composed of the OSRC Chairman and a minimum of four OSRC members.
The Chairman and members are designated by the Executive Vice President, Nuclear and shall have the qualifications that meet the requirements of Section 4.7 of ANSIIANI 3.1; 1978.
CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the OSRC Chairman to provide expert advice to the OSRC.
REVIEW 6.5.3.4 The OSRC shall review:
a.
The safety evaluations program and its implementation for (1) changes to procedures, equipment, systems or facilities within the power block, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; PALO VERDE - UNIT 1 6-10 AMENDMENT NO. 58
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ADMINISTRATIVE CONTROLS REVIEW Continued b.
Proposed changes to procedures, equipment, systems or facilities within the power block which involve an unreviewed safety question as defined in 10 CFR 50.59; Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; Proposed changes to Technical Specifications or this Operating License; e.
Violations of codes, regulations,
- orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; g.
h.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; All REPORTABLE EVENTS requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification; All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,
- systems, or components that could affect nuclear safety; and Reports and meeting minutes of the PRB.
AUDITS 6.5.3.5 Audits of unit activities shall be per formed under the cognizance of the OSRC.
These audits shall encompass:
a ~
The conformance of unit operation 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 unit staff at least once per 12 months.
d.
e.
The results of actions taken to correct deficiencies occurring in unit equipment, structures,
- systems, or method of operation that affect nuclear safety at least once per 6 months.
The performance of activities required by the Operational equality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months.
0 Any other area of unit operation considered appropriate by the OSRC or the Executive Vice President Nuclear.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee gA personnel.
PALO VERDE - UNIT 1 6-11 AMENDMENT NO.
5Q
ADMINISTRATIVE CONTROLS AUDITS Continued g.
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AUTHORITY The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.
An outside independent fire protection consultant shall be used at least every third year.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
The performance of activities required by the Operations equality Assurance Criteria Manual to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975 at least once per 12 months.
6.5.3.6 The OSRC shall report to and advise the Executive Vice President Nuclear on those areas of responsibility specified in Specifications 6.5.3 '
and 6.5.3'.
RECORDS 6.5.3.7 Records of OSRC activities shall be prepared and maintained.
Report of reviews and audits shall be forwarded to the Executive Vice President Nuclear with distribution to the management positions responsible for the areas audited.
ALTERNATES 6.5.3.8 All alter nate members shall be appointed in writing by the OSRC Chairman to serve on a temporary basis;
- however, no more than two alternates shall par-ticipate as.voting members in OSRC activities at any one time.
MEETING FRE UENCY 6.5.3.9 The OSRC shall meet at least once per six months.
UORUM 6.5.3. 10 The quorum of the OSRC necessary for the performance of the OSRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four OSRC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
PALO VERDE - UNIT 1 6-12 AMENDMENT NO. 58
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ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6. 1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified pursuant to the requirements of Section 50.72 to 10 CFR Part 50, and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the
- PRB, and the results of this review shall be submitted to the Chairman, Offsite Safety Review Committee and the Vice President-Nuclear Production.
PALO VERDE - UNIT 1 6-12a AMENDMENT NO.
58
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1 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued h.
PROCESS CONTROL'PROGRAM implementation.
i.
OFFSITE DOSE CALCULATION MANUAL implementation.
j.
guality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975.
k.
Pre-planned Alternate Sampling Program implementation.
1.
Secondary water chemistry program implementation.
NOTE:
The licensee shall perform a secondary water chemistry monitoring and control program that is in conformance with the program discussed in Sec-tion 10.3.4. 1 of the CESSAR FSAR or another NRC approved program.
m.
Post-Accident Sampling System implementation.*
n.
Settlement Monitoring Program implementation.
NOTE:
The licensee shall maintain a settlement monitoring program throughout the life of the plant in accordance with the program presented in Table 2.5-18 of the PVNGS FSAR or another NRC approved program.
o.
CEA Reactivity Integrity Program implementation NOTE:
The licensee shall perform, after initial fuel load or after each reload, either a
CEA symmetry test or worth measurements of all full-length CEA groups to address Section 4.2.2 of the PVNGS SER dated November 11, 1981 Fuel Assembly Surveillance Program Implementation NOTE:
The licensee shall perform a fuel assembly surveillance program in con-formance with the program discussed in Section 4.2.4 of the PVNGS SER dated November ll, 1981.
6.8.2 Each program or procedure of Specification 6.8. 1, and changes
- thereto, shall be reviewed as specified in Specification 6.5 and approved prior to implementation.
- Programs, administrative control procedures and implementing procedures shall be approved by the Vice President-Nuclear Production, or designated alternate who is at supervisory level or above.
Programs and proce-dures of Specification 6.8. 1 shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of Specification 6.8. 1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant supervisory staff, at least one of whom is a Shift Supervisor or Assistant Shift Supervisor with an SRO on the affected unit.
c.
The change is documented, reviewed in accordance with Specifica-tion 6.5.2 and approved by the cognizant department
- head, as desig-nated by the Vice President-Nuclear Production, within 14 days of implementation.
"Not required until prior to exceeding 5X of RATED THERMAL POWER.
PALO VERDE - UNIT 1 6-14 AMENDMENT NO. 58
ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM PCP Continued 1)
Sufficiently detailed information to totally suport the rationale for the change without benefit of additional or supplemental information and 2)
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.
6.14 OFFSITE DOSE CALCULATION MANUAL ODCM
- 6. 14. 1 The ODCM shall be approved by the Commission prior to implementation.
- 6. 14.2 Licensee-initiated changes to the ODCM:
Shall be submitted -to the Commission i n the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made effective.
This submittal shall contain:
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-mental information.
Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);
and 2)
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations.
6.15 MAJOR CHANGES TO RADIOACTIVE LI UID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS
- 6. 15. 1 Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid);
Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change was imple-mented.
The discussion of each change shall contain:
1)
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.
2)
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- Licensees may chose to submit the information called for in this specification as part of the annual FSAR update.
PALO VERDE - UNIT 1 6"24 AMENDMENT NO.
58
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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINdTON, D. C. 20555 ARIZONA PUBLIC SERVICE COHPANY ET AL.
DOCKET NO.
STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
2'MENDMENT TO FACILITY OPERATING LICENSE Amendment No.
45 License No.
NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Pro5ect Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority (licensees),
dated August 28,
- 1991, and modified by letter dated December 30,
- 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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; 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 ED 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
NPF-51 is hereby amended to read as follows:
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(2) Technical S eciffcat1ons and Env1ronmental Protect1on Plan The'Technical Specificat1ons contained in Appendix A, as rev1sed through Amendment No. 4g, and the Environmental Protect1on Plan contained 1n Appendix B, are hereby incorporated 1nto th1s 11cense.
APS shall operate the fac111ty 1n accordance with the Techn1cal Specificat1ons and the Environmental Protect1on
- Plan, except where otherwise stated 1n spec1fic license condit1ons.
3.
This license amendment is effect1ve as of the date of issuance and must be fully implemented no later.than 45 days from the date of issuance..
FOR THE NUCLEAR REGULATORY COMHISSION Theodore R. Quay, D1rector Project Directorate V
Div1sion of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 4, 1992
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ATTACHMENT TO LICENSE AHENDMENT AHENDHENT NO.
TO FACILITY OPERATING LICENSE NO.
NPF" 51 DOCKET NO.
STN 50"529 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 6-1 6-2 6-6 6-7 6-8 6-9 6-10 6-11 6-12 6" 14 6-24 6-1 6-2 6-6 6"7 6-8 6-9 6-10 6-11 6-12a 6-12 6-14 6-24
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ADMINISTRATIVE CONTROLS
- 6. 1 RESPONSIBILITY
- 6. l. 1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
- 6. 1.2 The Shift Supervisor, or during his absence from the Control
- Room, a
designated individual per Table 6.2-1, shall be responsible for the Control Room command function.
A management directive to this effect, signed by the Vice President"Nuclear Production shall be reissued to all station personnel on an annual basis.
- 6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS An offsite and an onsite organization shall be established for unit operation and corporate management.
The offsite and onsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.
Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.
These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).
b.
There shall be an individual executive position (Executive Vice President Nuclear) in the offsite organization having corporate responsibility for overall plant nuclear safety.
This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support in the plant so that continued nuclear safety is assured.
C.
There shall be individual management positions (Plant Managers) in the onsite organization having responsibility for overall unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.
d.
Although the individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.
6.2.2 UNIT STAFF a.
b.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor.
In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.
PALO VERDE - UNIT 2 6-1 AMENDMENT NO. 45
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ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.
Adequate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel work a nominal 40-hour week while the plant is operating.
- However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modifications, on a tem-porary basis, the following guidelines shall be followed (this ex-cludes the STA working hours):
1)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />
- straight, excluding shift turnover time.
2)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour
- period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
3)
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work
- periods, including shift turnover time.
4)
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
C.
Any deviation from the above guidelines shall be authorized by any one of the following personnel:
Director, Technical Support; Director, PYNGS Services; General Manager, Site Radiation Protection; General Manager, Site Chemistry; General Manager, Training; Plant Manager; or their designees who are at the manager level or above, or higher levels of management, 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 in their respective groups shall be reviewed monthly by these authorized individuals or their designees to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
PALO VERDE - UNIT 2 6-2 AMENDMENT NO. 45
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ADMINISTRATIVE CONTROLS
- 6. 2. 3 INDEPENDENT SAFETY ENGINEERING DEPARTMENT ISE FUNCTION 6.2.3. 1 The TSE gepartment shall function to selectively examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISE Department shall be composed of at least five, dedicated, full-time engineers located on site.
Each shall have a Bachelor's Degree in engi-neering or related science and at least two years professional level experience in his field.
RESPONSIBILITIES 6.2.3.3 The ISE Department shall be responsible for maintaining surveillance of selected plant activities to provide independent verification" that these activi-ties are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.
AUTHORITY
- 6. 2. 3.4 The ISE Department shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activi-ties or other means of improving plant safety to the Director, Nuclear Safety or designated alternate, Plant Manager, and the Chairman, Offsite Safety Review Committee (OSRC).
RECORDS 6.2.3.5 Records of activities performed by the ISE Department shall be prepared, maintained, and forwarded each calendar month to the Director, Nuclear Safety or designated alternate.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4. 1 The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are i'n MODE 1, 2, 3, or 4.
- 6. 3 UNIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI/ANS 3.1-1978 and Regulatory Guide 1.8, September 1975, except for the General Managers Site Radiation Protection who shall meet or exceed the qualifications of Regulatory Guide 1.8, September
- 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engi-neering discipline with specific training in plant design and plant operating "Not responsible for sign-off function.
PALO VERDE - UNIT 2 6-6 AMENDMENT NO. 45
. ADMINISTRATIVE CONTROLS
- 6. 3 UNIT STAFF UALIFICATIONS (Continued) characteristics, including transients and accidents.
An additional exception is that the Senior Reactor Operator (SRO) license requirement for the Operations Manager shall be met if either the Operations Manager or the Operations Super-visor holds a valid SRO license.
The holder of the SRO license shall direct the licensed activities of the licensed operators.
6.4 TRAINING 6.4, 1 A training program for the unit staff shall be maintained under the di-rection of the General
- Manager, Nuclear Training and shall meet or exceed the requirements of Section 5.0 of ANSI/ANS 3.1, 1978 and 10 CFR 55.
The program sha 1 l inc 1 ude fami 1 iari zati on with rel evant industry operati onal experi ence.
- 6. 5 REVIEW AND AUDIT
- 6. 5. 1 PLANT REVIEW BOARD (PRB FUNCTION 6.5. 1. 1 The Plant Review Board shall function to advise the Vice President Nuclear Production or his designee on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PRB shall be composed of nine members from the Palo Verde management staff.
These positions will be designated by the Vice President Nuclear Production or his designee in Administrative Procedures.
The Vice President Nuclear Production or his designee shall designate the Chairman and Vice-Chairmen in writing.
The Chairman and Vice-Chairmen may be from outside the members provided that they meet ANSI/ANS 3. 1, 1978.
ALTERNATES 6.5. 1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis;
- however, no more than two alternates shall participate as voting members in PRB activities at any one time.
MEETING FRE UENCY 6.5. 1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman, Vice-Chairmen, or his designated alternate.
PALO VERDE - UNIT 2 AMENDMENT NO. 45
ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 The quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman, Vice-Chairmen, or his designated alternate and five members including alternates.
- RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for:
a.
Review of all proposed changes to Appendix "A" Technical Specifications.
b.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Offsite Safety Review Committee (OSRC).
c.
Review of REPORTABLE EVENTS.
d.
Review of 'unit operations to detect potential nuclear safety hazards.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President-Nuclear Production or PRB Chairman.
Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass'ince the last PRB meeting.
AUTHORITY
- 6. 5. l. 7 The PRB shal 1:
a.
Render determinations in writing with regard to whether or not each item considered under Specification 6.5. 1.6b.
above constitutes an unreviewed safety question.
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 Executive Vice President
- Nuclear, Vice President Nuclear Production and OSRC of dis-agreement between the PRB and the Vice President Nuclear Production;
- however, the Vice President Nuclear Production shall have responsibil-ity for resolution of such disagreements.
RECORDS 6.5. 1.8 The PRB shall maintain written minutes of each PRB meeting that, at a minimum, document the results of all PRB activities performed under the responsi-bilityy and authority provisions of these Technical Specifications.
Copies shall be provided to the Executive Vice President-Nuclear, Vice President-Nuclear Production, and OSRC.
PALO VERDE - UNIT 2 6-8 AMENDMENT NO. 45
ADMINISTRATIVE CONTROLS 6.5.2 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.2. 1 The Vice President Nuclear Production or his designee shall assure that each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified individual/organization.
Each such procedure, and changes
- thereto, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or changes
- thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.
- 6. 5. 2.2 Phase I - IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Technical Support or his designee as previously designated by the Vice President-Nuclear Production.
Test results shall be approved by the Director, Technical Support or his designee.
6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual/organization.
Each such modification shall be reviewed by an individual/group other than the indi-vidual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification.
Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant Manager; or by the Director, Technical Support as previously designated by the Vice President-Nuclear Production.
6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2. 1,
- 6. 5. 2. 2, and 6. 5. 2. 3 shall be identified in station administrative procedures.
Each such review shall include a 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.
6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Vice President Nuclear Production or his designee.
6.5.2.6 The station security program and implementing procedures shall be reviewed.
Recommended changes shall be approved by the Director, PVNGS Services I
or designated alternate and transmitted to the Vice President-Nuclear Production and to the OSRC.
I 6.5.2.7 The station emergency plan and implementing procedures shall be reviewed.
Recommended changes shall be approved by the Director, PVNGS Services or designated alternate and transmitted to the Vice President-Nuclear Production and to the OSRC.
- 6. 5.2.8 The General Manager, Site Radiation Protection shall assure the per-formance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence.
PALO VERDE - UNIT 2 6-9 AMENDMENT NO.
45
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ADMINISTRATIVE CONTROLS TECHNICAL REVIEW AND CONTROL ACTIVITIES (Continued 6.5.2.9 The Vice President Nuclear Production or his designee shall assure the I
performance of a review by a qualified individual/organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment
- systems, and the Pre-planned Alternate Sampling Program.
6.5.2. 10 Reports documenting each of the activities performed under Specifica-tions 6.5.2. 1 through 6.5.2.9 above shall be maintained.
Copies shall be pro-vided to the Vice President-Nuclear Production and the Offsite Safety Review Committee.
6.5.3 OFFSITE SAFETY REVIEW COMMITTEE (OSRC FUNCTION 6.5.3.1 The OSRC shall function to provide independent review and shall be responsible for the 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 and electrical engineering h.
quality assurance practices COMPOSITION 6.5.3.2 The OSRC shall be composed of the OSRC Chairman and a minimum of four OSRC members.
The Chairman and members are designated by the Executive Vice President, Nuclear and shall have the qualifications that meet the requirements of Section 4.7 of ANSI/ANI 3.1; 1978.
CONSULTANTS
- 6. 5. 3. 3 Consultants shall be utilized as determined by the OSRC Chairman to provide expert advice to the OSRC.
REVIEW 6.5.3.4 The OSRC shall review:
The safety evaluations program and its implementation for (1) changes to procedures, equipment, systems or facilities within the power block, and (2) tests or experiments completed under the provision of 10 CFR 50'9, to verify that such actions did not constitute an unreviewed safety question; PALO VERDE - UNIT 2 6-10 AMENDMENT NO. 45
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ADMINISTRATIVE CONTROLS REVIEW Continued b.
Proposed changes to procedures, equipment, systems or facilities within the power block which involve an unreviewed safety question as defined in 10 CFR 50.59; C.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; d.
Proposed changes to Technical Specifications or this Operating License; Violati ons of codes, regul ati ons, orders, Techni ca 1 Speci ficati ons, license requirements, or of internal procedures or instructions having nuclear safety significance; Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; All REPORTABLE EVENTS requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification; h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,
- systems, or components that could affect nuclear safety; and Reports and meeting minutes of the PRB.
AUDITS 6.5.3.5 Audits of unit activities shall be performed under the cognizance of the OSRC.
These audits shall encompass:
The conformance of unit operation 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 unit staff at least once per 12 months.
The results of actions taken to correct deficiencies occurring in unit equipment, structures,
- systems, or method of operation that affect nuclear safety at least once per 6 months.
The performance of activities required by the Operational equality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months.
Any other area of unit operation considered appropriate by the OSRC or the Executive Vice President Nuclear.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee gA personnel.
PALO VERDE UNIT 2 6"11 AMENDMENT NO. 45
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ADMINISTRATIVE CONTROLS AUDITS Continued g ~
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AUTHORITY The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.
An outside independent fire protection consultant shall be used at least every third year.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
The performance of activities required by the Operations equality Assurance Criteria Manual to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975 at least once per 12 months.
6.6.3.6 The OSRC shall report to and advise the fxecutive Vice President Nuclear on those areas of responsibility specified in Specifications 6.5.3.4 and 6.5.3.5.
RECORDS 6.5.3.7 Records of OSRC activities shall be prepared and maintained.
Report of reviews and audits shall be forwarded to the Executive Vice President Nuclear with distribution to the management positions responsible for the areas audited.
ALTERNATES 6.5.3.8 All alternate members shall be appointed.in writing by the OSRC Chairman to serve on a temporary basis;
- however, no more than two alternates shall par-ticipate as. voting members in OSRC activities at any one time.
MEETING FRE UENCY 6.5.3.9 The OSRC shall meet at least once per six months.
UORUM 6.5.3. 10 The quorum of the OSRC necessary for the performance of the OSRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four OSRC members includ-ingg alternates.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
PALO VERDE - UNIT 2 6-12 AMENDMENT NO. 45
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ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION The following actions.shall be taken.for REPORTABLE EVENTS:
a.
The Commission shall be notified pursuant to the requirements of Section 50.72 to 10 CFR Part 50, and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the
- PRB, and the results of this review shall be submitted to the Chairman, Offsite Safety Review Committee and the Vice President-Nuclear Production.
PALO VERDE - UNIT 2 6-12a AMENDMENT NO.
45
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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued h.
PROCESS CONTROL PROGRAM implementation.
OFFSITE DOSE CALCULATION MANUAL implementation.
Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975.
Pre-planned Alternate Sampling Program implementation.
Secondary water chemistry program implementation.
NOTE:
The licensee shall perform a secondary water chemistry monitoring and control program that is in conformance with the program discussed in Sec-tion 10.3.4. 1 of the CESSAR FSAR or another NRC approved program.
m.
Post-Accident Sampling System implementation.*
n.
Settlement Monitoring Program implementation.
NOTE:
The licensee shall maintain a settlement monitoring program throughout the life of the plant in accordance with the program presented in Table 2.5-18 of the PVNGS FSAR or another NRC approved program.
o.
CEA Reactivity Integrity Program implementation NOTE:
The licensee shall perform, after initial fuel load or after each reload, either a
CEA symmetry test or worth measurements of all full-length CEA groups to address Section 4.2.2 of the PVNGS SER dated November ll, 1981.
p.
Fuel Assembly Surveillance Program Implementation NOTE:
The licensee shall perform a fuel assembly surveillance program in con-formance with the program discussed in Section 4.2.4 of the PVNGS SER dated November ll, 1981.
- 6. 8.2 Each program or procedure of Specification
- 6. 8. 1, and changes
- thereto, shall be reviewed as specified in Specification 6.5 and approved prior to implementation.
- Programs, administrative control procedures and implementing procedures shall be approved by the Vice President-Nuclear Production, or de-signated alternate who is at supervisory level or above.
Programs and proce-dures of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of Specification 6.8. 1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant supervisory staff, at least one of whom is a Shift Supervisor or Assistant Shift Supervisor with an SRO on the affected unit.
c.
The change is documented, reviewed in accordance with Specification 6.5.2 and approved by the cognizant department
- head, as designated by the Vice President-Nuclear Production, within 14 days of imple-mentation.
~Not required until prior to exceeding 5X of RATED THERMAL POWER.
PALO VERDE - UNIT 2 6-14 AMENDMENT NO. 45
ADMINISTRATIVE CONTROLS 6.14 OFFSITE DOSE CALCULATION MANUAL ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
- 6. 14.2 Licensee-initiated changes to the ODCM:
Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made effective.
This submittal shall contain:
1)
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-mental information.
Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);
and 2)
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations.
- 6. 15 MAJOR CHANGES TO RADIOACTIVE LI UID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS
- 6. 15. 1 Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):
Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change was imple-mented.
The discussion of each change shall contain:
1)
A summary of the evaluation that led to the'etermination that the change could be made in accordance with 10 CFR 50.59.
2)
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; 3)
A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; 4)
An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;
- Licensees may chose to submit the information called for in this specification as part of the annual FSAR update.
PALO VERDE - UNIT 2 6-24 AMENDMENT NO.
45
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C: 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License No.
NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Pro5ect Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority (licensees),
dated August 28,
- 1991, and modified by letter dated December 30, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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; 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
NPF-74 is hereby amended to read as follows:
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(2) Technical S ecificat1ons and Environmental Protection Plan The Technical Specificat1ons contained 1n Append1x A, as revised through Amendment No. 31
, and the Env1ronmental Protection Plan contained in Append1x B, are hereby incorporated into th1s license.
APS shall operate the fac111ty in accordance with the Techn1cal Specificat1ons and the Environmental Protect1on Plan, except where otherw1se stated 1n specific 11cense cond1t1ons.
3.
This license amendment 1s effect1ve as of the date of 1ssuance and must be fully implemented no later than 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COHHISSION Theodore R. Quay, D1rector Project D1rectorate V
Division of Reactor Projects III/IV/V Off1ce of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 4, 1992
ATTACH ENT TO LICENSE AHENDHENT AHENDHENT NO.
31 TO FACILITY OPERATING LICENSE NO.
NPF-74 DOCKET NO.
STN 50-530 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 6-1 6"2 6-6 6-7 6-8 6-9 6-10 6-11 6-12 6-14 6-24 6-1 6-2 6-6 6-7 6-8 6-9 6-10 6-11 6-12a 6-12 6-14 6-24
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-- ADMINISTRATIVE CONTROLS
- 6. 1 RESPONSI BI I ITY
- 6. 1.1 The Plant Manager shall., be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
- 6. 1.2 The Shift Supervisor, or during his absence from the Control
- Room, a
designated individual per Table 6.2-1, shall be responsible for the Control
'Room command function.
A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued to all station personnel on an annual basis.
- 6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS An offsite and an onsite organization shall be established for unit operation and corporate management.
The offsite and onsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
a ~
Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.
Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.
These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).
b.
There shall be an individual executive position (Executive Vice President Nuclear) in the offsite organization having corporate responsibility for overall plant nuclear safety.
This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support in the plant so that continued nuclear safety is assured.
c.
There shall be individual management positions (Plant Managers) in the onsite organization having responsibility for overall unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.
d.
Although the individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.
6.2.2 UNIT STAFF a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
PALO VERDE - UNIT 3 6-1 AMENDMENT NO.
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ADMINISTRATIVE CONTROLS UNIT STAFF (Continued}
b.
Adequate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel work a nominal 40-hour week while the plant is operating.
- However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modifications, on a tem-porary basis, the following guidelines shall be followed (this ex-cludes the STA working hours):
1)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour
- period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
3}
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work
- periods, including shift turnover time.
4)
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
C.
Any deviation from the above guidelines shall be authorized by any one of the following personnel:
Director, Technical Support; Director, PVNGS Services; General
- Manager, Site Radiation Protection; General Manager, Site Chemistry; General Manager, Training; Plant Manager; or their designees who are at the manager level or above, or higher levels of management, 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 in their respective groups shall be reviewed monthly by these authorized individuals or their designees to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
PALO VERDE - UNIT 3 6-2 AMENDMENT NO.
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ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING DEPARTMENT ISE FUNCTION 6.2.3.1 The ISE Department shall function to selectively examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISE Department shall be composed of at least five, dedicated, full-time engineers located on site.
Each shall have a Bachelor's Degree in engineer-ing or related science and at least two years professional level experience in his field.
RESPONSIBILITIES 6.2.3.3 The ISE Department shall be responsible for maintaining surveillance of selected plant activities to provide independent verification* that these activi-ties are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.
AUTHORITY
- 6. 2.3.4 The ISE Department shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activi-ties or other means of improving plant safety to the Director, Nuclear Safety or designated alternate, Plant Manager, and the Chairman, Offsite Safety Review Committee (OSRC).
RECORDS
- 6. 2. 3. 5 Records of activities performed by the ISE Department shall be prepared, maintained, and forwarded each calendar month to the Director, Nuclear Safety or designated alternate.
- 6. 2. 4 SHIFT TECHNICAL ADVISOR 6.2.4. 1 The Shift Technical AdviSor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in MODE 1, 2, 3, or 4.
- 6. 3 UNIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI/ANS 3.1-1978 and Regulatory Guide 1.8, September
- 1975, except for the General
- Manager, Site Radiation Protection who shall meet or exceed the qualifications of Regulatory Guide 1.8, September
- 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engi-neering discipline with specific training in plant design and plant operating "Not responsible for sign-off function.
PALO VERDE - UNIT 3 6"6 AMENDMENT NO.
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ADMINISTRATIVE CONTROLS
- 6. 3 UNIT STAFF UALIFICATIONS (Continued) characteristics, including transients and accidents.
An additional exception is that the Senior Reactor Operator (SRO) license requirement for the Operations Manager shall be met if either the Operations Manager or the Operations Super-visor holds a valid SRO license, The holder of the SRO license shall direct the licensed activities of the licensed operators.
- 6. 4 TRAINING 6.4.1 A training program for the unit staff shall be maintained under the di-rection of the General
- Manager, Nuclear Training and shall meet or exceed the requirements of Section 5.0 of ANSI/ANS 3. 1, 1978 and 10 CFR 55.
The program shall include familiarization with relevant industry operational experience.
- 6. 5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD PRB FUNCTION 6.5. 1. 1 The Plant Review Board shall function to advise the Vice President Nuclear Production or his designee on all matters related to nuclear safety.
COMPOSITION 6.5. 1.2 The PRB shall be composed of nine members from the Palo Verde management staff.
These positions will be designated by the Vice President Nuclear Production ot his designee in Administrative Procedures.
The Vice President Nuclear Production or his designee shall designate the Chairman and Vice-Chairmen in writing.
The Chairman and Vice-Chairmen may be from outside the members provided that they meet ANSI/ANS 3. 1, 1978.
ALTERNATES 6.5. 1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis;
- however, no more than two alternates shall participate as voting members in PRB activities at any one time.
MEETING FRE UENCY 6.5. 1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman, Vice-Chairmen, or his designated alternate.
PALO VERDE " UNIT 3 6-7 AMENDMENT NO 31
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ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 The quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman, Vice-Chairmen, or his designated alternate and five members including alternates.
RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for:
a.
Review of all proposed changes to Appendix "A" Technical Specifications.
b.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Offsite Safety Review Committee (OSRC).
C.
d.
Review of REPORTABLE EVENTS.
Review of unit operations to detect potential nuclear safety hazards.
e.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President-Nuclear Production or PRB chairman.
Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last PRB meeting.
AUTHORITY 6.5.1.7 The PRB shall:
a.
Render determinations in writing with regard to whether or not each item considered under Specification 6.5. 1.6b.
above constitutes an unreviewed safety question.
RECORDS 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 Executive Vice President
- Nuclear, Vice President Nuclear Production and OSRC of dis-agreement between the PRB and the Vice President Nuclear Production;
- however, the Vice President Nuclear Production shall have responsibi 1-ity for resolution of such disagreements.
6.5. 1.8 The PRB shall maintain written minutes of each PRB meeting that, at a
minimum, document the results of all PRB activities performed under the responsi-bilityy and authority provisions of these Technical Specifications.
Copies shall be provided to the Executive Vice President-Nuclear, Vice President-Nuclear Production, and OSRC.
PALO VERDE " UNIT 3 6"8 AMENDMENT NO.
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- 6. 5. 2 TECHNICAL REVIEM AND CONTROL ACTIVITIES 6.5.2. 1 The Vice President Nuclear Production or his designee shall assure that each procedure and program required by Specification 6 '
and other procedures which affect nuclear
- safety, and changes
- thereto, is prepared by a qualified individual/organization.
Each such procedure, and changes
- thereto, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or changes
- thereto, but who may be from the same organization as
.the individual/group which prepared the procedure, or changes thereto.
6.5.2.2 Phase I - IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Technical Support or his designee as previously designated by the Vice President-Nuclear Production.
Test results shall be approved by the Director, Technical Support or his designee.
6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual/organization.
Each such modification shall be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification.
Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant Manager; or by the Director, Technical Support as previously designated by the Vice President-Nuclear Production.
6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2. 1, 6.5.2.2, and 6.5.2.3 shall be identified in station administrative. pro-cedures.
Each such review shall include a determination of whether or not addi-tional, cross-disciplinary, review is necessary.
If deemed necessary, such review shall be performed by the appropriate designated review personnel.
6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Vice President Nuclear Production or his designee.
6.5.2.6 The station security program and implementing procedures shall be re-viewed.
Recommended changes shall be approved by the Director, PYNGS Services or designated alternate and transmitted to the Vice President-Nuclear Production and to the OSRC.
6.5.2.7 The station emergency plan and implementing procedures shall be re-viewed.
Recommended changes shall be approved by the Director, PVNGS Services or designated alternate and transmitted to the Vice President-Nuclear Production and to the OSRC.
- 6. 5.2.8 The General
- Manager, Site Radiation Protection shall assure the perform-ance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs inc1uding the preparation and forwarding of reports covering the evaluation, recommendations and disposition of the corrective action to prevent recurrence.
PALO VERDE " UNIT 3 AMENDMENT NO 31
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. ADMINISTRATIVE CONTROLS TECHNICAL REVIEW AND CONTROL ACTIVITIES Continued 6.5.2.9 The Vice President Nuclear Production or his designee shall assure the performance of a review by a qualified individual/organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment
- systems, and the Pre-planned Alternate Sampling Program.
6.5.2. 10 Reports documenting each of the activities performed under Specifica-tions 6.5.2. 1 through 6.5.2.9 above shall be maintained.
Copies shall be pro-vided to the Vice President-Nuclear Production and the Offsite Safety Review Committee.
6.5.3 OFFSITE SAFETY REVIEW COMMITTEE (OSRC FUNCTION 6.5.3. 1 The OSRC shall function to provide independent review and shall be responsible for the 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 and electrical engineering h.
quality 'assurance practices COMPOSITION 6.5.3.2 The OSRC shall be composed of the OSRC Chairman and a minimum of four OSRC members.
The Chairman and members are designated by the Executive Vice President, Nuclear and shall have the qualifications that meet the requi rements of Section 4.7 of ANSI/ANI 3.1; 1978.
CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the OSRC Chairman to provide expert advice to the OSRC.
REVIEW 6.5.3.4 The OSRC shall review:
a
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The safety evaluations program and its implementation for (1) changes to procedures, equipment, systems or facilities within the power block, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; PALO VERDE - UNIT 3 6-10 AMENDMENT NO. 31
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ADMINISTRATIVE CONTROLS REVIEM Continued b.
Proposed changes to procedures, equipment, systems or facilities within the power block which involve an unreviewed safety question as defined in 10 CFR 50.59; C.
d.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; Proposed changes to Technical Specifications or this Operating License; g.
Violations of codes, regulations,
- orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; All REPORTABLE EVENTS requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification; h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,
- systems, or components that could affect nuclear safety; and Reports and meeting minutes of the PRB.
AUDITS 6.5.3.5 Audits of unit activities shall be performed under the cognizance of the OSRC
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These audits shall encompass:
a.
The conformance of unit operation 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 unit staff at least once per 12 months.
C.
The results of actions taken to correct deficiencies occurring in unit equipment, structures,
- systems, or method of operation that affect nuclear safety at least once per 6 months.
The performance of activities required by the Operational guality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months.
Any other area of unit operation considered appropriate by the OSRC or the Executive Vice President Nuclear.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee gA personnel.
PALO VERDE " UNIT 3 6-11 AMENDMENT NO 3i
ADMINISTRATIVE CONTROLS AUDITS Continued g.
h.
The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.
An outside independent fire protection consultant shall be used at least every third year.
The radiological. environmental monitoring program and the results thereof at least once per 12 months.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
The performance of activities required by the Operations equality Assurance Criteria Manual to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975 at least once per 12 months.
AUTHORITY 6.5.3.6 The OSRC shall report to and advise the Executive Vice President Nuclear on those areas of responsibility specified in Specifications 6.5.3.4 and 6.5.3.5.
RECORDS 6.5.3.7 Records of OSRC activities shall be prepared and maintained.
Report of reviews and audits. shall be forwarded to the Executive Vice President Nuclear with distribution to the management positions responsible for the areas audited.
ALTERNATES
- 6. 5. 3. 8 All alter nate members shall be appointed in writing by the OSRC Chairman to serve on a temporary basis;
- however, no more than two alternates shall par-ticipate as voting members in OSRC activities at any one time.
6.5.3.9 The OSRC shall meet at least once per six months.
gUORUM 6.5.3.10 The quorum of the OSRC necessary for the performance of the OSRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four OSRC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
PALO VERDE - UNIT 3 6-12 AMENDMENT NO.
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ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION The following actions shall be taken for REPORTABLE EVENTS:
a e b.
The Commission shall be notified pursuant to the requirements of Section 50.72 to 10 CFR Part 50, and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and Each REPORTABLE EVENT shall be reviewed by the
- PRB, and the results of this review shall be submitted to the Chairman, Offsite Safety Review Committee and the Vice President-Nuclear Production.
PALO VERDE " UNIT 3 6-12a AMENDMENT NO 31
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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued J
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PROCESS CONTROL PROGRAM implementation.
OFFSITE DOSE CALCULATION MANUAL implementation.
guality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1. 21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975.
Pre-planned Alternate Sampling Program implementation.
Secondary water chemistry program implementation.
NOTE:
The licensee shall perform a secondary water chemistry monitoring and control program that is in conformance with the program discussed in Sec-tion 10.3.4. 1 of the CESSAR FSAR or another NRC approved program.
m.
Post-Accident Sampling System implementation.*
n.
Settlement Monitoring Program implementation.
NOTE:
The licensee shall maintain a settlement monitoring program throughout the life of the plant in accordance with the program presented in Table 2.5-18 of the PVNGS FSAR or another NRC approved program.
o.
CEA Reactivity Integrity Program implementation NOTE:
The licensee shall perform, after initial fuel load or after each reload, either a
CEA symmetry test or worth measurements of all full-length CEA groups to address Section 4.2.2 of the PVNGS SER dated November ll, 1981.
p.
Fuel Assembly Surveillance Program Implementation NOTE:
The licensee shall perform a fuel assembly surveillance program in con-formance with the program discussed in Section 4.2.4 of the PVNGS SER dated November ll, 1981.
- 6. 8. 2 Each program or procedure of Specification
- 6. 8. 1, and changes
- thereto, shall be reviewed as specified in Specification 6.5 and approved prior to imple-mentation.
- Programs, administrative control procedures and implementing proce-dures shall be approved by the Vice President-Nuclear Production, or designated alternate who is at supervisory level or above.
Programs and procedures of Specification 6.8. 1 shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of Specification 6.8. 1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant supervisory staff, at least one of whom is a Shift Supervisor or Assistant Shift Supervisor with an SRO on the affected unit.
c.
The change is documented, reviewed in accordance with Specification 6.5.2 and approved by the cognizant department
- head, as designated by the Vice President-Nuclear Production, within 14 days of implementation.
"Not required until prior to exceeding 5X of RATED THERMAL POWER.
PALO VERDE - UNIT 3 6"14 AMENDMENT NO. 3"
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ADMINISTRATIVE CONTROLS 6.14 OFFSITE DOSE CALCULATION MANUAL ODCM
- 6. 14. 1 The ODCM shall be approved by the Commission prior to implementation.
- 6. 14.2 Licensee-initiated changes to the ODCM:
Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made effective.
This submittal shall contain:
1)
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-mental information.
Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);
and 2)
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations.
6.15 MAJOR CHANGES TO-RADIOACTIVE LI UID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS
- 6. 15. 1 Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):
Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change was imple-mented.
The discussion of each change shall contain:
1)
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.
2)
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; 3)
A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; 4)
An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; "Licensees may chose to submit the information called for in this specification as part of the annual FSAR update.
PALO VERDE - UNIT 3 6-24 AMENDMENT NO. 31