ML20155K602
| ML20155K602 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/23/1988 |
| From: | Black S NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20155K604 | List: |
| References | |
| NUDOCS 8806210298 | |
| Download: ML20155K602 (12) | |
Text
_ _ _ _ _ _ _
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'o UNITED STATES E"
NUCLEAR REGULATORY COMMISSION e
E WASHING TON, D. C. 20555
/
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQU0YAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Comission) has found tnat:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 27, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
e and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission'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 attachment to this license amendrent and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION lea E Su na Black, ssis ant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: May 23, 1988
i 1
ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 6-19 6-19 6-22 6-22 6-23 6-23 o
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ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance with 10 CFR 50.4.
STARTUP REPORT
- 6. 9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the olant.
- 6. 9.1. 2 The startup report sh611 address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitment 3 shall be included in this report.
o
- 6. 9.1. 3 Startup reports saall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial oower operation, or (3) 9 months following initial criticality, whichever is ettliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events l
have been completed.
1 SEQUOYAH - UNIT 1 6-19 Amendment No. 5% 72
l J
ADMINISTRATIVE CONTROLS determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM).
The annual radioactive effluent release report to be submitted after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed members of the public from reactor releases and other nearby ura-nium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Op-eration.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.
The semiannual radioactive effluent release reports shall include the following information for each type of solid waste identified in Regulatory Guide 1.21, Rev. 1, Table 3, Part A, which is shipped offsite during the report period:
a.
Total volume of containers, b.
Total curie quantity (specify whether determined by measurement or estimate),
c.
Principal radionuclides (specify whether determined by measurement or estimate),
d.
Type of quantity (e.g., LSA, Type A, Type B, etc.)
o The semiannual radioactive effluent release reports shall include unplanned re-
' '. leases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis and shall include any changes to the PROCESS CONTROL PROGRAM (PCP) and the Offsite Dose Calculation Manual (0DCM) macc during the reporting period.
It shall include the type of solidification agent used, if applicable.
MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly P sis no later than the 15th of each month following the calendar month covered by the report.
Any changes to the 0FFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.
In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the PORC.
SEQU0YAH - UNIT 1 6-22 Amendment No. M 72
ADMINISTRATIVE CONTROLS RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal operation shall be provided at least 60 days prior to cycle initial criticality.
In the event that these values would be submitted at some other time during core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.
Any information needed to suport W(z) will be by request from the NRC and need not be included in this report.
SPECIAL REPORTS 6.9.2.1 Special reports shall be submitted within the time period specified for each report, in accordance with 10 CFR 50.4.
6.9.2.2 Diesel Generator Reliability Improvement Program As a minimum the Reliability Improvement Program report for NRC audit, required by LC0 3.8.1.1, Table 4.8-1, shall include:
(a) a summary of all tests (valid and invalid) that occurred within the time period over which the last 20/100 valid tests were performed (b) analysis of failures and determination of root causes of failures (c) evaluation of each of the recommendations of NUREG/CR-0660, "Enhancement of Onsite Emergency Diesel Generator Reliability in Operating Reactors,"
with respect to their application to the Plant (d) identification of all actions taken or to be taken to 1) correct the root causes of failures defined in b) above and 2) achieve a general improvement of diesel generator reliability (e) the schedule for implementation of each action from d) above (f) an assessment of the existing reliability of electric power to engineered-safety-feature equipment A supplemental report shall be prepared within 30 days after each subsequent failure during a valid demand for so long as the affected diesel generator unit continues to violate the criteria (3/20 or 6/100) for the reliability improvement program remedial action.
The supplemental report need only update the failure / demand history for the affected diesel generator unit since the last report for that diesel generator.
The supplemental report shall also present an analysis of the failure (s) with a root cause determination, if possible, and shall delineate any further procedural, hardware or operational changes to be incorporated into the diesel generator improvement program and the schedule for implementation of those changes.
SEQUOYAH - UNIT 1 6-23 Amendment No. @ 72
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o UNITED STATES "g
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NUCLEAR REGULATORY COMMISSION g
t WASHINGTON, D. C. 20555 e
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May 23, '958 TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. OPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 27, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i
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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission'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. OPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained ir Appendices A and B, as revised through Amendment No. 64, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
@e l
S a ne Black,
- ant tor f
Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: May 23, 1988
1 e
ATTACHMENT T0 i.ICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. OPR-79 DOCKET NO 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal i
lines indicating the area of change.
REMOVE INSERT 6-20 6-20 6-23 6-23 6-24 6-24 l.'
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ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance with 10 CFR 50.4.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
- 6. 9.1. 2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and,a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this renort.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whiche 1r is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
1 l
SEQUOYAH - UNIT 2 6-20 Amendment No. XWX 64
ADMINISTRATIVE CONTROLS exposure time and location) shall be included in these reports.
The mete-orological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measure-ment) shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The annual radioactive effluent release report to be submitted af ter January 1 of each year shall also include an assessment of radiation doses to the likely most exposed members of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.
1 The semiannual radioactive effluent release reports shall include the following
)
information for each type of solid waste identified in Regulatory Guide 1.21, Rev.1, Table 3, Part A, which, is shipped offsite during the report period:
)
a.
Total volume of containers, b.
Total curie quantity (specify whether determined by measurement or estimate),
c.
Principal radionuclides (specify whether determined by measurement or estimate),
d.
Type of quantity (e.g., LSA, Type A, Type B, etc.)
The semiannual radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis, and shall include any changes to the PROCESS CONTROL PROGRAM (PCP) and the Offsite Dose Calculation Manual (ODCM) made during the reporting period.
It shall include the type of solidification agent used, if applicable.
MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.
Any changes to the OFFSITE 00SE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.
In addition, a report of any major changes to the radioactive waste treatment systems shall be s' mitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the PORC.
SEQUOYAH - UNIT 2 6-23 Amendment No. 55 64
ADMINISTRATIVE CONTROLS RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal operation shall be provided at least i
60 days prior to cycle initial criticality.
In the event that these values would be submitted at some other time during core life, it will be submitted
'60 days prior to the date the values would become effective unless otherwise exempted by the Commission.
Any information needed to suport W(z) will be by request from the NRC and need not be included in this report.
SPECIAL REPORTS 6.9.2.1 Special reports shall be submitted within the time period specified for each report in accordance with 10 CFR 50.4.
6.9.2.2 Diesel Generator Reliability Improvement Program As a minimum the Reliability Improvement Program report for NRC audit, required by LCO 3.8.1.1, Table 4.8-1, shall include:
(a) a summary of all tests (valid and invalid) that occurred within the time period over which the last 20/100 valid tests were performed i
(b) analysis of failures and determination of root causes of failures (c) evaluation of each of the recommendations of NUREG/CR-0660, "Enhancement i
of Onsite Emergency Diesel Generator Reliability in Operating Reactors,"
with respect to their application to the Plant (d) identification of all actions taken or to be taken to 1) correct the root causes of failures defined in b) above and 2) achieve a general improvement of diesel generator reliability (e) the schedule for implementation of each action from d) above (f) an assessment of the existing reliability of electric power to engineered-safety-feature equipment A supplemental report shall be prepared within 30 days after each subsequent failure during a valid demand for so long as the affected diesel generator unit continues to violate the criteria (3/20 or 6/100) for the reliability improvement program remedial action.
The supplemental report need only update the failure / demand history for the affected diesel generator unit since the last report for that diesel generator.
The supplemental report shall also present an analysis of the failure (s) with a root cause determination, if possible, and shall delineate any further procedural, hardware or operational changes to be incorporated into the diesel generator improvement program and l
the schedule for implementation of those changes.
SEQUOYAH - UNIT 2 6-24 Amendent tio. M 64
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