ML20236A808
| ML20236A808 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/08/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236A803 | List: |
| References | |
| NUDOCS 8903200177 | |
| Download: ML20236A808 (5) | |
Text
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sE UNITED STATES
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- $5 p.
NUCLEAR REGULATORY COMMISSION.
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- WASHINGTON, D C.205S5
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NORTHEAST NUCLEAR' ENERGY COMPANY 3
1 DOCKET NO. 50-245
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MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.28 License No.:DPR-21
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1.
The Nuclear Regulatory Commission (the Commission) has found that-1 A.
The application for amendment by Northeast Nuclear Energy Company (the licensee), dated October 13, 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 j
Chapter ~I; 8.
The facil_ity will operate in conformity with the application, the I
provisions of the Act, and the rules and regulations of.the Commiss1on, C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and
'i safety of the public, and (ii) that such activities will.be j
conducted in compliance with the Coninission's regulations; O.
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,L he license is amended by changes to the Technical 2.
t Specifications as indicated in the attachment to this license amendment, and paragraph-2.C.(2) of Facility Operating License No. DPR-21 is hereby
. amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised j
through Amendment No. 28, 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 the date of issuance, to be implemented within 30 days of issuance.
~
FOR THE NUCLEAR REGUL TORY COMMISSION.
oh F. Stolz, Director i
Pr ject Directorate I 4 D' ision of Reactor. Projects I/II Office of ifuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date'of Issuance: March 8, 1989 l
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.pi ATTACHMENT TO LICENSE AMENDMENT NO. 28 11' FACILITY ~0PERATING LICENSE NO.:0PR-21 DOCKET N0. 50-245 Replace the following pages of the Appendix "A" Technical Specifications with.
the enclosed pages.
The revised pages are identified by amendment number and.contain vertical lines indicating the areas of change.
i Remove Insert
-3/4 6-15 3/4 6-15 l
3/4 6-16 3/4 6-16 i
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LIMITING CONDITION FOR OPERATION 3.6 PRIMARY SYSTEM ~ BOUNDARY I.
SNUBBERS 1.
During all modes of operation except COLD SHUTDOWN and REFUEL CONDITION, all safety-related snubbers shall be OPERABLE.
2.
If a snubber it d " mined to be inoperable, continued reactor i
operation is permi4 il ' only during the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following such l
determination unlee
'w snubber is sooner replaced, made 0PERABLE, or-an enginer ig evaluation determined the supported' system /componen' to be OPERABLE with the inoperable snubber.
3.
If the' requirements of 3.6.I.1 and 3.6.I.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the COLD 4
SHUTDOWN or REFUEL CONDITION within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
4.
If a snubber is determined t; be inoperable while the reactor is in the COLD SHUTDOWN or REFUEL CONDITION, the snubber shall be made OPERABLE, or replaced, prior to reactor startup.
SURVEILLANCE REQUIREMENT 4.6 PRIMARY SYSTEM BOUNDARY I.
SNUBBERS i
Each snubber shall be demonstrated OPERABLE by performance of the follow-ing augmented inservice inspection program.
1.
Visual Insoectio_q All snubbers shall be visually inspected in accordance with the following schedule.
i
- of Snubbers Found Inoperable During Inspection or During Next Required Inspection Interval Insoection Interval l
0 18 months 25%
1 12 months 25%
2 6 months 25%
3, 4 124 days 25%
5,6,7 62 days 25%
28 31 days 25%
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, that snubber may be exempted from being l
Millstone Unit 1 3/4 6 15 Amendment No. 7, %, 28
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SURVEILLANCE REQUIREMENT (Continued) counted as inoperable.
Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environ-mental conditions such as temperature, radiation, and vibration.
The required inspection interval shall not be lengthened more than one step at a time.
Snubbers may be categorized in two groups, mechanical and hydraulic.
Each group may be divided into two subgroups; those accessible and those inaccessible during reactor operation.
Each group and subgroup may be inspected independently in accordance with the above schedule.
2.
Visible Insoection Acceotance Criteria Visual inspections shall be conducted in the following manner:
(a) in the case where the attachments to the foundation or support-ing structure are found to be insecure, the cause of the rejection shall to clearly established and remedied for that particular snubber nnd for other snubbers that may be generically susceptible (snubbers found to have insecure attachments to their foundation or supporting structure shall not be included 'in the table of 4.6.I.1 for determination of the next inspection interval); or (b) if there are visual indications of damage or impaired OPERABILITY, the affected snubber shall be tested in the as-found condition and, if determined OPERABLE per specifications 4.6.I.4(a) or 4.6.I.4(b), as applicable, may be excluded from the number of snubbers counted as having failed the visual inspection.
Snubbers which appeared inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval provided that the above procedure is adhered to.
- However, when the fluid port is found to be uncovered, the snubber shall be determined to be inoperable and cannot be determined operable via functional testing for the purposes of establishing the next visual inspection interval.
Snubber Tests 3.
At least once per eighteen (18) months, during shutdown, a represen-tative sample (107 of the total of each type of snubbers, mechanical and hydraulic, in use in the plant) shall be tested either in place or in a bench test.
For each snubber that does not meet the test acceptance criteria of Specification 4.6.I.4(a) or 4.6.I.4(b), as applicable, an additional 57. of that type of snubber shall be tested.
Testing shall continue until no additional inoperable snubbers are found within a sample or until all snubbers have been tested.
The representative sample selected for testing shall include the various configurations, the range of size and capacity of snubbers, and the operating environment of'111 snubbers.
Millstone Unit 1 3/4 6-16 Amendment No. N 28
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