ML20082N147

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Amend 62 to License NPF-49 Revising Facility Visual Insp Surveillance Requirements & Acceptance Criteria Associated W/Seismic Sway Arresters (Snubbers)
ML20082N147
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/03/1991
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Northeast Nuclear Energy Co (NNECO)
Shared Package
ML20082N154 List:
References
NPF-49-A-062 NUDOCS 9109090011
Download: ML20082N147 (8)


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NUCLEAR REGULATORY COMMISSION

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NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.

DOCKET NO. 50-423 MILLSTONE NUCLEAR p0WER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. NPF-49 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated June 25, 1991 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 thc health and safety of the public, and (ii) that such activities will be Londuct ed 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 ccordance with 10 CFR Part 51 of 1he Commission's regulations and all applicable requirements have been satisfied.

9109090011 910903 PDR ADOCK 0500 3

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Accordingly, the license is amended by changes to the Technical Specifications-as indicated in t he attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 62

, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuanse.

FOR THE NUCLEAR REGULATORY COMMISSION r

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John F. Stolz, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes t o the Technical Specifications Date of Issuance: September 3, 1991 l

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1 ATT ACHP.Et:T TO LIC_fpSE,_ AD,EpDMEt4], pp,.,62_

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.If.C)!.I.I.Y.9ff.R.A,TJ,hp, L1,C_E!!SE 110. NPF-49 DOC KE T NO._ (0,,4_2,3 Replace the following pages of 04 Appendix A Technical Specifications with the entiostd pages. The revised pages are identified by antendment nuriber and contein vertical lines indicating the areas of change.

Ret:ove ysert x

x 3/4 7-22 3/4 7-22 3/4 7-22a 3/4 7-23 3/4 7-23 3/4 7-26a 3/4 7-26b e:

IhDEX t

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION-M01 a

TABLE.3.7-3 STEAM LINE SAFETY VALVES PER L00P.....................

3/4 7 3 4,

f 4

Auxiliary Feedwater System..............

3/4 7-4 s

Demineralized Water Storage Tank.........................

3/4 7-6 Specific Activity........................................

3/4 7-7 TABLE 4.7-l' SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE

+

AND ANALYSIS P.R0 GRAM................

3/4 7 8 j

Main Steam Line I sol ation-Valves.........................

3/4 7-9

= 1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........

3/4 7-10 3

3/4.7.3 REACTOR PLANT COMPONENT COOLING WATER SYSTEM.............

3/4.7 -

-3/4.7.4 SERVICE WATER SYSTEM.....................................

3/4 7-12 l3/4.7.5 - ULTIMATE HEAT SINK..........................

3/4 7-13 3/4.7.6 FLOOD.PR01ECT!0N.........................................

3/4 7 14 3/4.7.7~ CONTROL ROOM EMERGENCY VENTILATION SYSTEM................

3/4 7-15 3/4.7.8 CONTROL ROOM ENVELOPE PRESSURIZATION SYSTEM..............

3/4 7-18 g

3/4.7.9 AUXILIARY BUILDING FILTER SYSTEM...........

3/4 7-20 I

3/4.7.10 SNUBBERS.................................................

3/4 7-22 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL...................

3/4 7-26a FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST...........

3/4 7-27 3/4.7 ll.-SEALED SCURCE CONTAMINATION..............................

3/4 7-28 3/4.7.12 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System............................

3/4 7-30 Spray and/or Sprinkl er Systems...........................

3/4 7-33 CO Systems..............................................

3/4 7-35 2

Halon Systems.........................-..................

3/4 7-37 Fire Hose Stations.......................................

3/4 7-38 TABLE 3.7-4 FIRE HOSE STATIONS....................................

3/4 7-39 Yard Fire Hydrants and Hydrant Hose Houses...............

3/4 7-40 TARLE 3.7-S YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES.

3/4 7-41 3/4.7.13 FIRE RATED ASSEMBLIES....................................

3/4 7-42 3/4.7.14 AREA TEMPERATURE MONITORING..............................

3/4 7-44 TABLE 3.7-6 AREA TEMPERATURE MONITORING...........................

3/4 7-45 MILLSTONE - UNIT 3 x

Amendment No. 62

flANT SYSTEMS J/4.7.10 SNUBBERS LIMITING CONDITION FOR OPERATION 3,7.10 All snubbers shall be OPERABLE.

The only snubbers excluded from the requirements are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

APPLICABillTY: H0 DES 1, 2, 3, and 4.

MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.

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With one or more snubbers inoperable on any system, 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 OPERABLE status and perform an engineering' evaluation per Specification 4.7.109. on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.10 Each snubber shall be demonstrated OPERABLE by performance of the folicwing augmented inservice inspection program and the requirements of Spedfication 4.0.5.

I a.

Inspection Tvoes As used in this specification, " type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity, b.

Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation.

Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7-2.

The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criterion shall be based upon the previous inspection interval as established by the requirements in ef fect before Amendment 62 c.

Visual Insoection Acceptance Criteria Visual inspections shall verify that (1) the snubbec has no visible indicatione of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional.

Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that

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(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of MILLSTONE - UNIT 3 3/4 7-22 Amendment No. Jg, 62 5

I f1 ANT S1Sl WS S R YU LLANCE REQUIREMENTS (C mtinuedl type that may be generically susceptible; and (2) the affected snubber is functienally tested in the as-found condition and determined OPERABLE per Spectfication 4.7.10.f.

All snuobers found connected to an inoperable commun hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspe: tion interval.

A review and evaluation shall bc performed and documented to justify continued operation with an unacceptable snubber.

If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.

d.

Transient Event Insoection An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 6 months following such an event.

in addition to satisfying the visual inspection acceptance criteria, freedom-of motion of mechanical snubbers shall be verified using at least one of the following:

(1) manually induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel, e.

Functional Testi During the first refueling shutdown and at least once per 18 raonths thereafter during shutdown, a representative sample of snubbers of each type shall be tested using one of the following sample plans.

The sample plan for each type shall be selected prior to the test period and cannot be changed during the test period.

The NRC Regiona'

.dministrator shall be notified in writing of the sample pla: selet ad for each snubber type prior to the test period or the sample plan used in the prior test period shall be implemented:

1)

At least 10% of the total of each type of snubber shall be functionally tested either in-place or in a bench test.

For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.10f., an additional 5%

of that type of snubber shall be functionally tested until no more tailures are found or until all snubbers of that type have been functionally tested; or

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MILLSTONE - UNIT 3 3/4 7-23 Amendment No. 62

TABLE 4.7-2 SNUBBER VISUAL INSPECT'ON INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval (Notes 1 and 2)

(Nn'.es 3 apJ 6)

(Nptes 4 and 6)

(Notes 5 and 61 1

0 0

1 80 0

0 2

100 0

1 4

150 0

3 8

200 2

5 13 300 5

12 25 400 8

18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1:

The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval.

Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.

These categories may be examined separately or jointly.

However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.

Note 2:

Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.

Use next lower integer for the value of the limit for Columns A, B, or C if that integer included a fractional value of unacceptable snubbers as determined by interpolation.

Note 3:

If the number of unacceptable snubbers is equal to or less than the number in Column A, the ne.-t inspection interval may be twice the previous interval but no greater than 48 months.

Note 4:

If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.

Note 5:

If the number of unacceptable snubbers is equal to or greater than the number in Column C,

the next inspection interval snall be two-thirds of the previous interval.

However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.

MILLSTONE - UNIT 3 3/4 7-26a Amendment No. 62

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TABLE 4.7 2 SNVBBER VISUAL INSPECTION INTERVAL Note 6:

The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.

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MILLSTONE - UNIT 3 3/4 7 26b Amendment NO. 62 i

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