ML17303A609
| ML17303A609 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/29/1987 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | Arizona Public Service Co |
| Shared Package | |
| ML17303A610 | List: |
| References | |
| NPF-41-A-022, NPF-51-A-012, NPF-65-A-002 NUDOCS 8710080388 | |
| Download: ML17303A609 (24) | |
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~ UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-41 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment, dated July 1, 1987 (as supplemented by letter dated August 7, 1987),
by the Arizona Public Service Company (APS) on behalf of itself and the Salt Rive~ Project Agricultural Improvement and Power District, El Paso Electric
- Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Mater and Power, and Southern California Public Power Authority (licensees),
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 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 Comnission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2;C.(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
22, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
APS shall operate
.the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
'This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications eorge nighton, Dir tor Project directorate V
Division of Reactor Projects - III, IV, V and Special Projects Date of Issuance:
September 29, 1987
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September 29, 1987 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
22 TO FACILITY OPERATING LICENSE NO. NPF-41 DOCKET NO.
STN 50-528 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Also to be replaced is the following overleaf page to the amended page.
Amendment Pa e
6-14 Overleaf Pa e
6-13
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ADMINISTRATIVE CONTROLS
- 6. 7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President-Nuclear Production, PVNGS Plant Manager and Supervisor of Nuclear Safety Group shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PRB.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components,
- systems, or structures, and (3) corrective action taken to prevent recurrence.
c.
The Safety Limit Violation Report shall be submitted to the Commission, the Supervisor of the NSG and the Vice President-Nuclear Production within 14 days of the violation.
d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8. 1 Mritten procedures shall be establ'ished, implemented, and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, and those required for implementing the requirements of NUREG-0737.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.-
g.
Modification of Core Protection Calculator (CPC) Addressable Constants.
NOTE:
Modification to the CPC Addressable Constants based on information obtained through the Plant Computer -
CPC data link shall not be made without prior approval of the PRB.
h.
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.
k.
Pre-planned Alternate Sampling Program implementation.
Secondary water chemistry program implementation.
PALO VERDE - UNIT 1 6-13
ADHINISTRATIVE CONTROLS PROCEDURES AND PROGRAHS (Continued 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 PVNGS Plant Manager, or designated alternate who is at supervisory level or above.
Programs and procedures of Specifica-tion 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 PVNGS plant manager or cognizant department
- head, as designated by the PVNGS plant manager, within 14 days of implementation.
6.8.4 The following programs shall be established, implemented, maintained, and shall be audited under the cognizance of the NSG at least once per 24 months:
a.
Primar Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the recirculation portion of the high pressure safety injection system, the shutdown cooling portion of the low pressure safety injection system, the post-accident sampling subsystem of the "Not required until prior to exceeding 5X of RATED THERMAL POWER.
PALO VERDE - UNIT 1 6-14 AMENDMENT NO.
22
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UNITED STATES NUCLEAR REGUL'ATORY COMMISSION WASHINGTON, O. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-529 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 12 License No. NPF-51 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated July 1, 1987 (as supplemented by letter dated August 7, 1987),
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 Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority (licensees),
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 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.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-51 is hereby amended to read as follows:
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
12, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications George W
- nighton, D
ctor project irectorate Division of Reactor Projects - III, IV, V and Special Projects Date of Issuance:
September 29, 1987
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September 29, 1987 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
12 TO FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO.
STN 50-529 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Also to be replaced is the following overleaf page to the amended page.
Amendment Pa e
6-14 Overleaf Pa e
6-13
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ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be'notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President-Nuclear Production, PVNGS Plant Manager and Supervisor of Nuclear Safety Group shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PRB.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components,
- systems, or structures, and (3) corrective action taken to prevent recurrence.
c.
The Safety Limit Violation Report shall be submitted to the Commission, the Supervisor of the NSG -and the Vice President-Nuclear Production within 30 days of the violation.
d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8. 1 Mritten procedures shall be established, implemented,,and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, and those required for implementing the requirements of NUREG-0737.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
Modification of Core Protection Calculator (CPC) Addressable Constants--These procedures should include provisions to ensure that sufficient margin is maintained in CPC Type I Addressable Constants to avoid excessive operator interaction with the CPCs during reactor operation.
NOTES:
(1) Modification to the CPC Addressable Constants based on information obtained through the Plant Computer CPC data link shall not be made without prior approval of the PRB.
(2) Modifications to the CPC software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Proce-dure," that has been determined to be applicable to the facility.
Additions or deletions to CPC Addressable Constants or changes to Addressable Constant soft-ware limit values shall not be implemented without prior NRC approval.
PALO VERDE - UNIT 2 6-13
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued h.
k.
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 PVNGS Plant Manager, or designated alternate who is at supervisory level or above.
Programs and procedures of Specifica-tion 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 PVNGS plant manager or cognizant department
- head, as designated by the PVNGS plant manager, within 14 days of implementation.
"Not required until prior to exceeding 5X of RATED THERMAL POWER.
PALO VERDE - UNIT 2 AMENDMENT NO.
12
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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. 2 License No. NPF-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated July 1, 1987 (as supplemented by letter dated August 7, 1987),
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 Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority (licensees),
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 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.
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-'2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-65 is hereby amended to read as follows:
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
2, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULAT RY COllMISSION
Enclosure:
Changes to the Technical Specifications George I
- nighton, Di ctor Project Directorate U
Division of Reactor Projects - III, IV, V and Special Projects Date of Issuance:
September 29, 1987
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September 29, 1987 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
2 TO FACILITY OPERATING LICENSE NO. NPF-65 DOCKET NO.
STN 50-529 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Also to be replaced is the following overleaf page to the amended page.
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6-14
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ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President-Nuclear Production, PVNGS Plant Manager and Supervisor of Nuclear Safety Group shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Limit Violation Report shall be prepared.
The report shall b'e reviewed by the PRB.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components,
- systems, or structures, and (3) corrective action taken to prevent recurrence.
c.
The Safety Limit Violation Report shall be submitted to the Commission, the Supervisor of the 'NSG and the Vice President-Nuclear Production within 30 days of the violation.
d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8. 1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, and those required for implementing the requirements of NUREG-,0737.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
Modification of Core Protection Calculator (CPC) Addressable Constants--These procedures should include provisions to ensure that sufficient margin is maintained in CPC Type I Addressable Constants to avoid excessive operator interaction with the CPCs during reactor operation.
NOTES:
(1) Modification to the CPC Addressable Constants based on information obtained through the Plant Computer CPC data link shall not be made without prior approval of the PRB.
(2) Modifications to the CPC. software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Proce-dure," that has been determined to be applicable to the facility.
Additions or deletions to CPC Addressable Constants or changes to Addressable Constant soft-ware limit values shall not be implemented without prior NRC approval.
PALO VERDE - UNIT 3 6-13
ADHINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) h.
PROCESS CONTROL PROGRAM implementation.
i.
OFFSITE DOSE CALCULATION MANUAL implementation.
j.
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.
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 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 PVNGS Plant Manager, or designated alternate who is at supervisory level or above.
Programs and procedures of Specifica-tion 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.
b.
C.
The intent of the original procedure is not altered.
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.
The change is documented, reviewed in accordance with Specification 6.5.2 and approved by the PVNGS Plant Manager or cognizant department
- head, as designated by the PVNGS Plant Manager, within 14 days of implementation.
- Not required until prior to exceeding 5X of RATED THERMAL POMER.
PALO VERDE - UNIT 3 6-14 AMENDMENT NO.
2