ML19306H413
| ML19306H413 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/07/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML19306H414 | List: |
| References | |
| NPF-49-A-016 NUDOCS 8804200231 | |
| Download: ML19306H413 (9) | |
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NUCLEAR REGULATORY COMMISSION n
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NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.*
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 ffENDMENTTOFACILITYOPERATINGLICENSE Amendment No.16 License No. NPF-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated July 31, 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; 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 tha health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Comission's regulations; D.
The issuance of this a.bdment will not be inimical to the common defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 5' of the Comission's regulations and all applicable requirements base been satisfied.
- Northeast Nuclear Energy Company is authorized to act as agent and represent-ative for the following Owners: Central Maine Power Company, Central Vermont Public Service Corporation, Chicopee Municipal Lichting Plant, City of Burlington, Yemont, Connecticut Municipal Electric Light Company, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, The Village of Lyndonville Electric Department, Western Massachusetts Electric Company, and Vermont Electric Generation and Transmission Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, end paraaraph 2.C.(P) of Facility Operating License No. NPF-49 is hereby amended to read as follows:
(?) Technical Specifications The Technical Specifications contained in Appendix A, as revised s
through Amendment No.16
, and the Environmental Protection Plan contained in Appendix R, 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.
i 3.
This license amendment is effective as of the date of its issuance.
F R THE NUCLEAD EGULpTORYCOMMISSION oh ' F. Stolz, Director -
Pr fect Directorate I tvision of Reactor Pro.iects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 7,1988 a
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ATTACHVENT TO LICENSF AMENDMENT NO.16 FACILTIY OPERATING LTCENSE NO. NPF do i
l DOCKET NO. 50 A23 Replace the following pages of the Appendix A Technical Soecifications with the enclosed pages. The revised pages are identified by amendment number and j
contain vertical lines indicating the areas of chance. The correspondiro overleaf pages are provided to maintain document completeness.
Pomove Insert 3/4 7-24 3/4 7 94 3/4 7-27 3/4 7-27 i
B 3/4 7-6 B 3/4 7-6 l
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
Visual Inspection Acceptance Criteria i
Visual inspections shall verify that:
(1) there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasten-ers for attachment.of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespec-tive of type that may be generically susceptible; and (2) the affected snubber is functionally tested in tk as-found condition and deter-mined OPERABLE per Specification 4.7.10f.
All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
d.
Transient Event Inspection 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 Tests During the first refueling shutdown and at least once per 18 months thereafter during shutdown, a representctive 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 Regional Administrator shall be notified in' writing of the sample plan selected 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 j
more failures are found or until all snubbers of that type have
.i been functionally tested; or
)
MILLSTONE - Oh! 3 3/4 7-23 4
1 PLANT SYSTEMS SUEVEILLANCE REQUIREMENTS (Continued)
Functional Tests (Continued) e.
A representative sample of each type of snubber shall be func-2)
"C" is the
.tionally tested in accordance with Figure 4.7-1.
total number of snubbers of a type found not meet'ing the accept-The cumulative l
ance requirements of Specification 4.7.10f, Test number of snubbers of a type tested is denoted by "N".
results shall be plotted sequentially in the order of sample each snubber shall be plotted by its assigned assignment (i.e.
order in the random sample, not by the order of testing).
If at i
any time the point plotted falls in the " Accept" region, testing When the point dl of snubbers of that type may be terminated.
plotted lies in the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in i
the " Accept" region or the " Reject" region, or all the snubbers q
of that type have been tested; or An initial representative sample of 55 anubbers shall be func-l{
3)
For each snubber type which does not meet the
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tionally tested.
functional test acceptance criteria, another sample of at least one-half the size of the initial sample shall be tested-until i
the total number tested is equal to the initial sample size multiplied by the factor, 1 + C/2, where "C" is the number of snubbers found which do not meet the functional test acceptance The results from this sample plan shall be plotted l
criteria.
h using an " Accept" line which follows the equation N = 55(1
+ C/2). Each snubber point should be plotted as soon as the j
snubber is tested.
If the point plotted falls on or below the
" Accept" line, testing of that type of snubber may be If the point plotted falls above the " Accept" line, if terminated.
testing must continue until the point falls in the " Accept" l
4 region or all the snubbers of that type have been tested.
1 Testing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume anew at a
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later time provided all snubbers tested with the failed equipment i
The representative l
during the day of equipment failure are retested.
sample selected for the-functional test sample plans shall be w
randomly selected from the snubbers of each type and reviewes before The review shall ensure, as far as beginning the testing.
practicable, that they are representative of the various configurations, operating environments, range of site, and capacity Snubbers plac6d in the same location as of snubbers of each type.
snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be included in If during the functional testing, additional the sample plan.
sampling is required due to failure of only one type of snubber, the functional test results shall be reviewed at that time to determine 1
if additional samples should be limited to the type of snubber which has failed the functional testing.
J MILLSTONE - UNIT 3 3/4 7-24 Amendment No.15 l
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CONTINUE TESTING 3
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ACCEPT 1
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0 10 20 30 40 50 60 70 80 90 100 N
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F]GURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCT30NAL TEST MILLSTONE - pHIT 3 3/4 7-27 Amendment No.16
PLANT SYSTEMS 3/4.7.11 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.11 Each sealed source containing radioactive material either in excess of 100 microCuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.
APPLICABILITY:
At all times.
ACTION:
With a sealed source having removable contamination in excess of the a.
above limits, immediately withdraw the sealed source from use and either:
1.
Decontaminate and repair the sealed source, or 2.
Dispose of the sealed source in accordance with Commission Regulations.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.7.11.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.
Test Frequencies - Each category of sealed sources (excluding 4.7.11.2 startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.
Sources in use - At least once per 6 months for all sealed sources a.
containing radioactive materials:
1)
With a half-life greater than 30 days (excluding Hydrogen 3),
and 2)
In any form other than gas.
MILLSTONE - UNIT 3 3/4 7-28
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PLANT SYSTEMS BASES 3/4.7.9 AUXILIARY BUILDING FILTER SYSTEM (Continued)
)
4 component cooling water pump and heat exchanger areas following a LOCA are filtered prior to reaching the environment. Operation of the system with the i
l i.
heaters operating for at least 10 continuous hours in a 31-day period is I
sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
l The operation of this system and the resultant effect on offsite dosage calculations was assumed in the safety analyses.
ANSI N510-1980 will be used as a procedural guide for surveillance testing.
3/4.7.10 SNUBBERS 1!'
All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is main-j tained during and following a seismic or other event initiating dynamic loads.
j For the purpose of declaring the affected system OPERABLE with the inoperable snubber (s), an engineering evaluation may be performed, in accordance with j
Section 50.59 of 10 CFR Part 50.
Snubbers are classified and grouped by design and manufacturer but not by size.
Snubbers of the same manufacturer but having different internal 1
mechanisms are classified as different types.
For example, mechanical snubbers j
utilizing the same design features of the 2-kip,10-kip and 100-kip capacity j
manufactured by Company "A" are of the same type. The same design mechanical i
snubbers manufactured by Company "B" for the purposes of this Technical i
Specification would be of a different type, as would hydraulic snubbers from I
either manufacturer.
A list of individual snubbers with detailed information of snubber locatior and size and of system affected shall be available at the plant in accordance i
with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall be determined and approved by the Plant Operations Review Committee.
The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g.,
j temperature, atmosphere, location, etc.), and the recommendations of Regulatary
' y Guides 8.8 and 8.10.
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant l
level of snubber protection to each safety-related system during an earthquake J
or severe transient. Therefore, the required inspection interval varies inversely with the observed snubber failures on a given system and is determined j
by the number of inoperarle snubbers found during an inspection of each system.
In order to establish the inspection frequency for each type of snubber on a safety-related system, it was assumed that the Trequency of snubber failures and initiating events is constant with time and that the failure of any snubber on that system could cause the system to be unprotected and to result in failure 4
during an assumed initiating event.
Inspections performed before that interval MILLSTONE - 1 NIT 3 8 3/4 7-5 r-
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PLANT SYSTEMS BASES SNUBBET.S (Continued) has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) =ay not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
The acceptance criteria are to be used in the visual inspection to determine OPERABILITY of the snubbers. For example, if a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.
l To provide assurance of snubber functional reliability, one of three functional testing methods is used with the stated acceptance criteria:
1.
Functionally test 10% of a type of snubber with an additional 5%
tested for each functional testing failure, or 2.
Functionally test a sa=ple size and determine sa:ple acceptance or continue testing using Figure 4.7-1, or 3
Functionally test a representative sample size and deter =ine sample t
acceptance or rejection using the stated equation.
Figure 4.7-1 was developed using "Vald's Sequential Probability Ratio Plan" as described in " Quality Control and Industrial Statistics" by Acheson J. Duncan.
16 i
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Permanent or other exemptions from the surveillance progra: for individual l
snubbers may be granted by the Commission if a justifiable basis for exe:ption is presented and, if applicable, snubber life destructive testips was performed to qualify the snubbers for the applicable design conditions at either the ec:-
pletion of their fabrication or at a subsequent date. Snubbers so exe pted
)
shall be listed in the list of individual snubbers indicating the extent of the exe=ptions.
/
l The service life of a snubber is established via mapdracturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical i
bases for future consideration of snubber service life.
3/4.7.11 SEALED SOURCE CONTAMINATION Thelimitationsonremovablecontaminationforsourcesreqdiringleak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for MILLSTONE - UNIT 3 B 3/4 7-6 Amendment No.16 i
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