ML20235U950
| ML20235U950 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/02/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235U952 | List: |
| References | |
| NUDOCS 8903090444 | |
| Download: ML20235U950 (13) | |
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UNITED STATES 9,
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NUCLEAR REGULATORY COMMISSION 7,
'j-WASHINGTON D. C. 20555
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT, UNIT 1, AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 2,1988, 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 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 publb:, 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 Comission's regulations and all applicable requirements have been satisfied.
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8903090444 890302 PDR ADOCK 05000327 P
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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. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A r.nd B, as revised through Amendment No.102, 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.
i FOR THE NUCLEAR REGULATORY COMMISSION WL >t.-%C A
Suzanne Mack, Assistant Director for Projects
{
TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 2, 1989 1
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 102 FACILITY OPERATING LICENSE NO. DPR-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. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4*
B 3/4 6-1 B 3/4 6-1 B 3/4 6-2 B 3/4 6-2*
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i
" CONTAINMENT SYSTEMS I
i SURVEILLANCE REQUIREMENTS
- 4. 6.1. 2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix'J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972; however, the methods of ANSI /ANS 56.8-1987 for mass point data analysis may be used in lieu of the methods specified in ANSI N45.4-1972.
1Property "ANSI code" (as page type) with input value "ANSI N45.4-1972.</br></br>1" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at Pa (12 psig) during each 10-jear service period.
The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection, b.
If any periodic Type A test fails to meet 0.75 L, the test schedule a
for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L '
a a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L at which time the above test a
schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of +.he Type A test by verifying that the difference between supp b ental and Type A test data is within 0.25 L
- a 2.
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at Pa (12 psig).
d.
Type B and C tests shall be conducted with gas at Pa (12 psig) at intervals no greater than 24 months except for tests involving:
1.
Air locks, 2.
Penetrations using continuous leakage monitoring systems, and 3.
Valves pressurized with fluid from a seal system.
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SEQUOYAH - UNIT 1 3/4 6-3 Amendment No.102
d CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.
The combined bypass leakage rate to the auxiliary building shall be determined to be less than or equal to 0.25 L by applicable Type B a
and C tests at least once per 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to Pa (12 psig) during each Type A test.
f.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
g.
Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.'i0 Pa (13.2 psig) and.the seal system capacity is adequate to maintain system pressure (or fluid head for the containment spray system and RHR spray system valves at penetrations 48A, 488, 49A and 49B) for at least 30 days.
h.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at Pa (12 psig) at intervals no greater than once per 3 years.
i.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
j.
The provisions of Specification 4.0.2 are not applicable.
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SEQUOYAH - UNIT 1 3/4 6-4 Amendment No.12, 7L 101,102
3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1 PRIMARY CONTAINMENT Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.
This i
restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during i
accident conditions.
I 3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P.
As an added conservatism, the a
measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during performance of the periodic tests to account for a
possible degradation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.
Due to the increased accuracy of the mass point method for containment integrated leakage testing, the mass point method referenced in ANSI /ANS 56.8-1987 can be used in lieu of the methods described in ANSI N45.4-1972.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance '.esting of the air lock seals provide assurance that the overall air lock let age will not become excessive due to seal damage during the intervals between air lock leakage tests.
3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.5 psig and 2) the SEQUOYAH - UNIT 1 B 3/4 6-1 Amendment No. 102
c:
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' CONTAINMENT SYSTEMS BASES containment peak pressure does not' exceed the maximum allowable internal pressure of 12 psig during LOCA conditions.
3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensurc that 1) the l
containment air mass is limited to an initial mass sufficiently low to prevent exceeding the maximum allowable internal pressure during LOCA conditions and
- 2) the ambient air temperature does not exceed that temperature allowable for the continuous duty rating specified for equipment and instrumentation located within containment.
The containment pressure. transient is sensitive to the initially contained air mass during a LOCA.
The contained air mass increases with decreasing temperature.
The lower temperature limits of 100 F for the lower compartment, 85 F for the upper compartment, and 60 F when less than or equal to 5% of RATED THERMAL POWER will limit the peak pressure to an acceptable value.
The upper temperature limit influences the peak accident temperature slightly during a LOCA; however, this limit is based primarily upon equipment protection and anticipated operating conditions. Both the upper and lower temperature limits are consisteret with the parameters used in the accident analyses.
3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 12 psig in the event of a LOCA.
A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6.1.7 SHIELD BUILDING STRUCTURAL INTEGRITY i
This limitation ensures that the structural integrity of the containment shield building will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to provide 1) protection for the steel vessel from external missiles, 2) radiation shielding in the event of a LOCA, and 3) and annulus surrounding the steel vessel that can be maintained at a negative pressure during accident conditions.
Amendment No. 102 SEQUOYAH - UNIT 1 B 3/4 6-2 Revised 8/18/87
a nou
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- UNITED STATES
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g NUCLEAR REGULATORY COMMISSION j;;
'l WASHINGTON. D. C. 20555 l-i TENNESSEE VALLEY AUTHORITY l
DOCKET NO. 50-328 SE000VAH NUCLEAR PLANT, UNIT 2 AMENDMO:.,T,0 FACILITY OPERATING LICENSE Amendment No. 91 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 2,1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; 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 (1) that the activities authorized by I
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; 1
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 l
been satisfied.
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l i-U_______-._-_.__-__.__-________---
e
. i 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 in Appendices A and B. as revised through Amendment No. 91, 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 I
$ e e FA c/C Suzanne ack, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
1 Changes to the Technical Specifications Date of Issuance:
March 2, 1989 l
ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE N0. DPR-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 lines indicating the area of change.
REMOVE INSERT 3/4 6-3 3/4 6-3 B 3/4 6-1 B 3/4 6-1 B 3/4 6-2 B 3/4 6-2*
' CONTAINMENT SYSTEMS I
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972; however, the methods of ANSI /ANS 56.8-1987 for mass point data analysis may be used.in lieu of the methods specified in ANSI N45.4-1972.
a.
Three Type A tests (0verall Integrated Containment Leakage Rate) shall'be conducted at 40 10-month intervals during shutdown at P,, 12 psig, during each 10 year service period.
The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection.
I b.
If any periodic Type A test fails to meet 0.75 L, the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L,,
a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L at which time the above test a
schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L '
a 2.
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or l
bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P, 12 psig.
a d.
Type B and C tests shall be conducted with gas at P, 12 Psig, at a
intervals no greater than 24 months except for tests involving:
1.
Air locks, 2.
Penetrations using continuous leakage monitoring systems, and SEQUOYAH - UNIT 2 3/4 6-3 Amendment No. 91
3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1 PRIMARY CONTAINMENT Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from.the containment atmosphere will be restricted to those leakage paths and associated leak. rates assumed in the accident analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the. accident analyses at the peak accident pressure, P,.
As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during performance of the periodic tests to account for a
possible degradation of toe containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.
Due to the increased accuracy of the mass point method for containment integrated leakage testing, the mass point method referenced in ANSI /ANS 56.8-1987 can be used in lieu of the methods described in ANSI N45.4-1972.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the j
containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.5 psig and 2) the SEQUOYAH - UNIT 2 B 3/4 6-1 Amendment No. 91
(
' CONTAINMENT SYSTEMS BASES INTERNAL-PRESSURE (Continued) containment peak pressure does not exceed the maximum allowable internal pressure of 12 psig during LOCA conditions.
3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that 1) the containment air mass is limited to an initial mass sufficiently low to prevent exceeding the maximum allowable internal pressure'during LOCA conditions and
- 2) the ambient air temperature does not exceed'that temperature allowable for the continuous duty rating specified for equipment and instrumentation located within containment.
The containment pressure transient is sensitive to the initially contained air mass during a LOCA.
The contained air mass increases with decreasing temperature.
The lower temperature limits of 100 F for the lower compartment, 85 F for the upper compartment, and 60 F when less than or equal to 5% of RATED THERMAL POWER will limit the peak pressure to an acceptable value.
The upper temperature limit influences the peak accident temperature slightly during a LOCA; however, this limit is based primarily upon equipment protection and anticipated operating conditions. Both the upper and lower temperature limits are consistent with the parameters used in the accident analyses.
3/4.6.1.b CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel wili be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 12 psig in the event of a LOCA.
A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6.1.7 SHIELD BUILDING STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment shield building will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to provide
- ~
- 1) protection for the steel vessel from external missiles, 2) radiation shield-ing in the event of a LOCA, and 3) an annulus surrounding the steel vessel that can be maintained at a negative pressure during accident conditions.
1 Amendment No. 91 SEQUOYAH - UNIT 2 B 3/4 6-2 Revised 08/18/87 l
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