ML20006B684
| ML20006B684 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/23/1990 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006B682 | List: |
| References | |
| GL-84-13, NUDOCS 9002050244 | |
| Download: ML20006B684 (8) | |
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UNITED STATES 2%
NUCLEAR REGULATORY COMMISSION 1
gi WASHING TON, D. C. 20555 4%i#:,Vff sy. J YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO.50-029
-YANKEE NUCLEAR POWER STATION J
AMENDMENT TO FACILITY OPERATING LICENSE-1 Amendment No.129 u
License No. DPR-3 1.
The Nuclear Regulatory Comission'(the Comission or..the NRC) has found' that:
A.
The application for amendment filed by Yankee Atomic Electric' Company (the licensee) dated November.22,.1989,-complies with the standards and'. requirements of the Atomic Energy Act-of 1954, as amended. (the Act), and the Comission's rules Eand regulations: set -
l forth in 10.CFR Chapter I; B.
The facility will operate in conformity with the application,.the 1
provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance: (i) that the' activities authorized by g
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 set.forth in 10 CFR Chapter I;
~0.
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-l the Comission's regulations and all' applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment.to thisl license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to-read'as follows:
(2) Technical Specifications-
'The Technical Specifications contained in Appendix A, as' revised through Amendment'No.129, are hereby incorporated in the -license.
The licensee shall operate the facility -in accordance with the j
Technical Specifications.
.j 9002050244 900123 PDR ADOCK 05000029 1
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This license amendment is effective as of its date'of' issuance.-
l-L FOR THE NUCLEAR REGULATORY COMMISSION J
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TN Richard H. Wessman, Director L
Project Directorate I-3 Division of Reactor Projects =I/II' Office of Nuclear Reactor Regulation L
Attachment:
Changes to the Technical-L Specifications Date of Issuance:
January 23, 1990 1
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ATTACHMENT TO LICENSE AMENDMENT NO.129 FACILITY OPERATING LICENSE N0. OPR-3 l
DOCKET N0;50-029 1
Replace the following pages of the Appendix A Technical Specifications with-the attached pages.
The revised pages-are identified by Amendment' number and contain vertical l. lines indicating the area of change.
Remove Insert.
3/4 7 3/4 7-27 3/4 7-29 3/4 7-29 3/4'7-29a 3/4 7-29a B 3/4 7-6 B 3/4 7-6 6-24' 6-24 P
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-PEANT SYSTEMS m
3/4.7.9 SNUBBERS l'
LIMITING CONDITION F0F ef ERATION 3.7.9 All snubbers shall be OPERABLE. The only snubbers excluded from this requirement 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.
APPLICABILITY: MODES 1, 2, 3 and-4.
(MODES 5 and 6 for snubbers located on-systems required OPERABLE in those MODES).
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 OPERABLE status and perform an engineering evaluation per Specification 4.7.9.c on the supported component or declare the supported s
system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REOUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.
a.
Visual Inspections The first inservice visual inspection of snubbers shall be performed after June 3, 1982 but before December 3, 1982 and'shall include all snubbers.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months 3 25% from the date of the first inspection. Otherwise subsequent visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period *#
0 18 months 25%
1 12 months 1 25%
2 6 months + 25%
3, 4 124 days 25%
5,6,7 62 days 2 25%
8 or more 31 days ! 25%
The snubbers may be categorized into two groups: Those accessi,,ble and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
- The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
Yankee Rowe 3/4 7-27 Amendment No. #I, /d,129
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PLANT SYSTEMS-SURVEILLANCE REOUIREMENTS' '(Continued) l:
Snubbers that are especially difficult to remove' or in high radiation zones during shutdown shall also be~ included in the represer.tative sample.*
In addition to the regular sample, snubbers which failed the s
previous functional test'shall be retested during the next test y
. period.
If a spare snubber has been installed in place of a failed Q
snubber,. then both the f ailed snubber (if it is repaired and.
installed in.another position) and the spare snubber shall be retested. Test results of these snubbers may not be included for.
the re-sampling.
If any snubber selected for functiona'1Ltesting either fails to lockup or fails to move, i.e.,
frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency:all snubbers of the same~ design subject to the same defect shall be functionally tested. This testing requirement shall be-independent of the requirements stated above for snubbers not meeting the.
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functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on-the components which are supported.by.the snubber (s). The purpose of this engineering evaluation shall be to determine -if the components supported by the. snubber (s) 'were 3
l-adversely affected by the inoperability of the snubber (s) in order =
to ensure that the supported component remains capable'of meeting the designed service, d.
Mechanical Snubbers Functional Test Acceptance Criteria
'l The mechanical snubber' functional test shall verify,that:
1.
The force that initiates' free movement of the snubber rod in.
either tension or compression is less than theTspecified maximum drag force.
Drag. force shall not havelincreased more than 50% since the last functional test.
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l-Permanent or other exemptions from functional testing for individual l
snubbers in these' categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or-snubber life -
destructive testing was performed to qualify snubber operability for:all design conditions at either the completion of their fabrication or at a subsequent date.
, Yankee Rowe 3/4 7-29 Amendment No. #I, //129
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PLANT SYSTEMS l
SURVEILLANCE REOUIREMENTS (Cor.tinued) 2 l.
2.
Activation (rehtraining action) is achieved withinithe specified'renge of. velocity or acceleration in.both tension and compression.
3.
Snubber release rate, where required, is within the specified; range in compression or. tension.- Forl snubbers specifically.
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= required not-to displace'under continuous. load the ability of the snubber to withstand load'without displacement shall be verified.1 e.
Snubber Service Life Monitoring A record of the servf.ce life of each~ snubber 4 the date at which the designated service life' commences and the installation-and maintenance records ~on whic'h,the-designated service life is based shall be maintained as required by Specification 6.10.2.n.
. Concurrent with the first inservice visual inspection and at least t
once per 18 months thereafter..the: installation and maintenance records for each snubber.shall be reviewod to verify that-t'he l.'
indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated service life vill be exceeded prior to the next scheduled snubber service life-review, the snubber service life shall be.
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re-evaluated or the snubber sha11 be replaced or reconditioned so as
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to extend its service. life beyond the1date'of the next scheduled' service life review. This _ re-evaluation', J replacement, or
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3 reconditioning shall be indicated in the records..
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Yankee Rowe 3/4 7-29a
. Amendment No. #I, 7I, //,129
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3/4.7.8 ENVIROFMENTAL MONITORING DELETED t
3/4.7.9 SNUBBERS All snubbers are reqsired OPERABLE to ensure that the structural
-1 integrity of the. reactor coolant system and all other' safety-related systems is maintained during and following a seismic or other event initiating dynamic' loads.
The visual inspection frequency is. based upon maintaining a const'nt'
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a level of. snubber' protection to systems.. Therefore, the required inspection 4
interval varies inversely with.the observed snubber failures and-is determined; by the number of inoperable snubbers found during'an inspection.- Inspections performed before that interval has elapsed may.be used as a new1 reference
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point to determine the next inspection. However, the-results of such'early:
inspections; performed before the original? required l time interval has elapsed (nominal time less125%) may not be used to lengthen the required' inspection interval. Any inspection whose results require a shorter inspection interval' will override the previous schedule.
When the cause of'the rejection ofLa snubber is' clearly established and remedied for that' snubber and for any other snubbers that:may be generically susceptible, and verified by inservice functional testing,Dthat snubber may be exempted from being 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' environmental' conditions such as.
temperature, radiation, and vibration.
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AmendmentNo.f/,//,//129-
.l YANKEE-ROWE B 3/4'7-6 e
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e ADMINISTRATIVE CONTROLS-n.
Records of the service lives of all snubbers, including the date at 1
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l which the service life commences and associated installation and l-maintenance records.
4 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be' prepared consistent
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r with requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for'all operations involving personnel radiation exposures.
6.12 HIGH RADIATION AREA 6.12.1 Paragraph 20.203 " Caution signs, labels, signals, and controls".
In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2), each high radiation area in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a'high' radiation area, and entrance:thereto shall be controlled by requiring issuance of a Radiation Work Permit.* An individual or group of individuals permitted to enter such areas shall be provided with one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring. device which continuously integrates the
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radiation dose rate in the area, and alarms when a preset integrated l
l dose is received. Entry into such areas with this' monitoring device L
may be made after the dose rate level in the. area has been-established and personnel have been made knowledgeable of.them.
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A Health Physics qualified individual (i.e., qualified in. radiation protection procedures), with.a radiation-dose rate monitoring device, who is responsible for.providing positive control over the activities within the area and who will' perform radiation i
surveillance at the frequency specified in the RRP. The-surveillance frequency will be established by the Plant' Health Physicist.
Health Physics personnel shall be exempt from the RWP issuance requirementi during the performance of their assigned radiation protection duties,.
providing they are following plant radiation protection procedures for entry into high radiation areas.
YANKEE-ROWE 6-24 AmendmentNo.7I,80,//,129 t
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