ML20065L813
| ML20065L813 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/18/1994 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065L818 | List: |
| References | |
| NUDOCS 9404210299 | |
| Download: ML20065L813 (11) | |
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S UNITED STATES 5'
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NUCLEAR REGULATORY COMMISSION l
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WASHINGTON, D.C. 2055b0001 g
f TENNESSEE VALLEY AUTHORITY l
DOCKET N0. 50-327 SEOU0YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 179 License No.-DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated' February 7, 1994, 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 (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.
9404210299 940418 PDR-ADOCK 05000327 p
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w s 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 Sossifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.179, 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, to be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
[
Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 18, 1994 I
r--
i ATTACHMENT TO LICENSE AMENDMENT NO.179 FACILITY OPERATING LICENSE N0. DPR-77 DOCKET N0. 50-327 Revise the Appendix A Technical Specifications by remosing 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 7-22 3/4 7 3/4 7-24 3/4 7-24 3/4 7-25 3/4 7-25
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PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) c.
Visual Inspection Performance and Evaluation Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILTY, (2) bolts attaching the snubber to the fmandation or supporting structure are secure, and (3) snubbers attached
- ections of safety-related systems that have experienced unexpected etially damaging transients since the last inspection period shall be eu.uated for the possibility of concealed damage and functionally tested, if applicable, to confirm operability.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection val, providing that (1) the cause of the rejection is clearly es' "
.ed and remedied for that particular snubber and for other snubk.. c. hat may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined l
OPERABLE per Specification 4.7.9.e.
Hydraulic snubbers with inoperable single or common fluid reservoirs which have uncovered fluid ports shall be declared inoperable.
l Also, snubbers which have been made inoperable as the result of unexpected transients isolated damage or other such random events, when the provisions of 4.7.9.
i 4.7.9.h have been met and any other appropriate corrective action im).
.ented, shall not be counted in determining the next visual inspection interval.
d.
Functional Test Schedule. Lot Size. and Composition During each refueling outage, a representative sample of 10% of the total of the safety-related snubbers in use in the plant shall be functionally tested either in place or in a bench test.
SEQUOYAH - UNIT 1 3/4 7-22 Amendment No. 12, 153, 179
PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) f.
Functional Test Failure Analysis and Additional Test lots (Continued)
If more than two snubbers do not meet the functional test acceptance criteria, an additional lot equal to one-half the original lot size shall be functionally tested for each failed snubber in excess of the two allowed failures. An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. The result of this analysis shall be used, if applicable, in selecting snubbers to be tested in the subsequent lot in an effort to determine the operability of other snubbers which may be subject to the same failure mode.
(Selection of snubbers for future testing may also be based'on the failure analysis.) Testing shall continue until not more than one additional inoperable snubber is found within a subsequent required lot or all snubbers of the original inspec-tion group have been tested, or all suspect snubbers identified by the failure analysis have been tested, as applicable.
The discovery of loose or missing attachment fasteners will be evaluated to determine whether the cause may be localized or generic. The result of the evaluation will be used to select other suspect snubbers for verifying the attachment fasteners, as applicable.
Snubbers shall not be subjected to prior maintenance specifically for the purpose of meeting functional test requirements.
g.
Functional Test Failure - Attached Comoonent Analysis For snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are restrained by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components restrained by the snubber (s) were adversely affected by the inoperability of the snubber (s), and in order to ensure that the restrained component remains capable of meeting the designed service.
h.
Functional Testino of Repaired and Soare Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced.
Replacement snubbers and snubbers which have repairs which might affect the functional test results shall be tested to meet the functional test criteric before installation in the unit.
These snubbers shall have met the acceptare criteria subsequent to their most recent service, and the functional tesi. must have been performed within 12 months before being installed in the unit.
i.
Snubber Service life Proaram The service life of hydraulic and mechanical snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections.
The maximum expected service life for various seals, springs, and other critical parts shall be determined and established SEQUOYAH - UNIT 1 3/4 7-24 Amendment No. 12, j
179 i
PLANT SYSTEMS SVRVEILLANCE RE0VIREMENTS (Continued) 1.
Spubber Service Life Proaram (Continued) based on engineering information and shall be extended or shortened based on monitored test results and failure history.
Critical parts shall be replaced so that the maximum service life will net be exceeded during a period when the snubber is required to be OPERABLE. The parts replacements shall be documented and the documentation shall be retained in accordance with Specification 6.10.2.n.
J.
Exemotion From Visual Insoection or Functional Tests Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and if applicable snubber life destructive testing was performed to qualify snubber operability for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
SEQUOYAH - UNIT 1 3/4 7-25 Amendment No. 39,179
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v UNITED STATES 5:
'i NUCLEAR REGULATORY COMMISSION t
,/
WASHINGTON, D.C. 2055W1 y
TENNESSEE VALLEY AUTHORITY QQCKET NO. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 171 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 February 7, 1994, 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; 8.
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 bo 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.
1
V 4 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-79 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 171, 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, to be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION f
f Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 18,1994
m==-
ATTACHMENT TO LICENSE AMENDMENT NO.171 FACILITY OPERATING LICENSE N0. OPR-79 DOCKET N0. 50-328 Revise the Appendix A Technical Specifications by removing the pages l
identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendr ent number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 7-22 3/4 7-22 3/4 7-25 3/4 7-25 I
PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS c.
Visual Insoection Performance and Evaluation Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) bolts attaching the snubber to the foundation or supporting structure are secure, and (3) snubbers attached to sections of safety-related systems that have experienced unexpected potentially damaging transients since the last inspection period shall be evaluated for the possibility of concealed damage and functionally tested, if applicable, to confirm operability.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found l
condition and determined OPERABLE per Specification 4.7.9.e.
Hydraulic snubbers with inoperable single or common fluid reservoirs which have uncovered fluid ports shall be declared inoperable.
i l
l SEQUOYAH - UNIT 2 3/4 7-22 Amendment No. 2, 143, 171
e PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) g.
Functional Test Failure - Attached Comoonent Analysis For snubbers (s) found inoperable, an engineering evaluation shall be performed on the components which are restrained by the snubber (s).
The purpose of this engineering evaluation shall be to determine if the components restrained by the snubber (s) were adversely affected by the inoperability of the snubbers (s), and in order to ensure that the restrained component remains capable of meeting the designed service.
h.
Functional Testina of Reoaired and Soare Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced.
Replacement snubbers and snubbers which have repairs which might affect the functional test results shall be tested to meet the funtional test criteria before installation in the unit. These snubbers shall have met the acceptance criteria subsequent to their most recent service, and the functional test must have been performed within 12 months before being installed in the unit.
1.
Snubber Service Life Proaram The service life of hydraulic and mechanical snubbers shall be moni-tored to ensure that the service life is not exceeded between surveil-lance inspections.
The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history.
Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE.
The parts replacements shall be documented and the documen-tation shall be retained in accordance with Specification 6.10.2.n.
j.
Exemotion From Visual Insoection or Functional Tests Permanent or other exemptions form the surveillance program for individual snubbers may be granted by the Commission if a justifiable bhsis for exemption is presented and if applicable snubber life destructive testing was performed to qualify snubber operability for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
SEQUOYAH - UNIT 2 3/4 7-25 Amendment No. 31, 104, 171