ML20209C735
| ML20209C735 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/29/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20209C741 | List: |
| References | |
| DPR-57-A-134, NPF-05-A-072, TAC 64157, TAC 64158 NUDOCS 8702040329 | |
| Download: ML20209C735 (9) | |
Text
UNITED STATES 8"
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'+,.....,o GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 134 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated November 20, 1986 as supplemented January 27, 1987 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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. DPR-57 is hereby amended to read as follows:
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.134, 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 t'
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Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 29, 1987 l
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ATTACHMENT TO LICENSE 'llENDMEM~N0.134
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FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.
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3/4.6.L.
SNU8BERS SURVEILL*NCE REQUIREMENTS (Continued) 2 systems associated with the safety-related mechanical snubbers shall be inspected to determine if there has been a severe dynamic event.
(b) In the event of a severe dynamic event, snubbers in that system j
1 which experienced the event shall be inspected during the refueling l
outage to assure the snubbers have freedom of movement and are not frozen up. The inspection shall consist of verifying freedom of motion using one of the following:
(1) Manually induced snubber movement; (ii) stroking the mechanical snubber through its full range of travel.
If one or more mechanical snubbers are found to be i
frozen up during this inspection, those snubbers shall be replaced (or overhauled) before returning to power. Re-inspection shall l
subsequently be performed according to the schedule of 4.6.L.1., but the scope of the examination shall be limited to the systems associated with the safety-related mechanical snubbers. 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 i
l affected snubber is functionally tested in the "as found" condition and determined OPERABLE per Specification 4.6.L.4. or 4.6.L.5., as i
applicable. However, if a hydraulic snubber is found to contain less than the required minimum volume of reserve fluid, the snubber shall be 1
determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
3.
Functional Tests 1
At least once per 18 months during shutdown, a representative sample of 10% of the total of each type (hydraulic or mechanical) safety-related snubber in use in the plant shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.6.L.4. or 4.6.L.S., an additional sample of at least 1/2 the size of the initial lot of that type of snubber shall be functionally tested.
Functional testing shall continue until no additional inoperable snubbers of a particular type are found within a sample or until all safety-related snubbers of that type have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. The representative sample shall be selected randomly from the total population of safety-related snubbers. At least 25% of the snubbers in the HATCH - UNIT 1 3.6-10b qwndnent No. H, U, 1/2, 134
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WASHINGTON, D. C. 20655 9
4,.....,o GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72' License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated November 20, 1986 as supplemented January 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 Comission; C.
There is reasonable assurance (1) 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. NPF-5 is hereby amended to read as follows:
1
, (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 C0 ISSION k4d Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to 1.ne Technical Specifications Date of Issuance: January 29, 1987
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ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines. The overleaf page is provided for convenience.
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[t, PIRrr SYS'IIMS 3/4.7.4 SNUBEIPS LIMITING CDCITION FOR OPEATION 3.7.4 All snukers* shall be operable. The only snuRers excluded from this rsluirment are those instaned on non-safety,related systers and then only if their faiure or failure pf the system on which they are installed would have no adverse effect on any safety-re)ated syste.
APPLICABILITi Conditions 1, 2, and 3.
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPDAE2 status and perform an engineering evaluation per specification 4.7.4.c on the supported component or declare the supported syste inoperable and fonow the appropriate ACTION statstant
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SLMTILINCE MUJIRDG2TTS 4.7.4 Each snutbar shall be deonstrated OPDABE by performance of the following inservice inspection progra and the requirments of Specification 4.0.5.
a.
Visual Inspections All safety-related anubbers shah be visuaHy exmined to verify anubber operability.
Visual inspections shan be performe! in accordance with the following schedule:
No. Inoperable Snubbers Subestuent Visual per Inspection Period Inspection Period **I 0
18 months + 254 1
12 months 7 254 2
6 months 7 254*
3, 4 124 days 7 254 5,6,7 62 days 7 25%
8 or more 31 days
_7 254 The snutbers may be categorized into two groups: those accessible and those inaccessible during reactor operation. Each group say he inspected independently in accordance with the above schedule.
- The applicable snutbers shall be identified in plant proceduras.
- 2he inspection interval shall not be lengthened more than one step at a tine.
- 2he provisions of specification 4.0.2 are not applicable.
HA201-UNIT 2 3/4 7-U Amendment No.51
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SURVEILLANCE REQUIREMENTS (Continued) i b.
Visual Inspection Acceptance Criteria i
Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) for mechanical snubbers where snubber movement can be manually induced, the snubbers shall be inspected as follows: (a) At each refueling, systems associated with the safety related mechanical snubbers shall be inspected to determine if there has been a severe dynamic event.
(b) In the event of a severe dynamic event, snubbers in that system which experienced the i
event shall be inspected during the refueling outage to assure j
the snubbers have freedom of movement and are not frozen up.
i The inspection shall consist of verifying freedom of motion using one of the following: (1) Manually induced snubber 1
i movement; (ii) stroking the mechanical snubber through its i
full range of travel.
If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced (or overhauled) before returning to power.
Re-inspection shall subsequently be performed according to the schedule of 4.7.4.a. but the scope of the examination shall be i
(
limited to the systems associated with the safety-related mechanical snubbers. Snubbers which appear inoperable as a 1
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 j
and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the "as found" condition and determined OPERABLE per Specification 4.7.4.d or 4.7.4.e. as applicable. However, if.a hydraulic snubber is found to contain less than the required minimum volume of reserve fluid, the snubber shall be determined inoperable and l
cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
c.
Functional Tests At least once per 18 months during shutdown, a representative sample of 10% of the total of each type (hydraulic or mechanical) safety-related snubber in use in the plant shall be functionally tested either in place or in a bench test.
For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.4.d or 4.7.4.e, an additional sample of at least 1/2 the size of the initial lot i
of that type of snubber shall be functionally tested.
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HATCH - UNIT 2 3/4 7-12 Amendment No. 51, 72 e