ML20235R412

Amend 95 to License DPR-61,replacing Tech Specs 3.19 & 4.13 Re Snubbers W/Tech Specs Consistent W/Nrc Model STS & W/ Current Industry Guidelines Such as Generic Ltr 84-13

ML20235R412
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/23/1987
From:	Thomas C Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235R350	List: ML20235R348 ML20235R412 ML20235R423
References
GL-84-13, NUDOCS 8710080039
Download: ML20235R412 (8)

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Id p r are o# UNITED STATES s j f, NUCLEAR REGULATORY COMMISSION g g- y. WASHINGTON, D. C. 20566 Ya f.

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CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213

% HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE 1 Amendment No. 95 License No. DPR-61 g

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

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A. The. application for amendment by Connectir.ut-Yankee Atomic Power Company (the licensee), dated June 1, 1987. complies with the standards and requirements of the Atomic Energy Act of 1954, J' as amended '(the Act), and the Comission's rules and regulations as 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 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 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 Comission's regulations and all applicable requirements have been satisfied.

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87100B0039 870923 PDR ADDCK 05000213

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2. According$y,thelicenseisamendedbychangestothe-Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised

! through Amendment No. 95, are hereby-incorporated into the license.-

The licensee shall operate the facility in accordance with the Technical Specifications.

L 3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION U$ m Cecil 0. Thomas, Director Integrated Safety Assessment Project Directorate Division of Reactor Projects III/IV/V and Special Projects

Attachment:

Changes to the Technical

- Specifications Date,of Issuance: September 23, 1987

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. . I t, ATTACHMENT TO LICENSE AMENDMENT NO.- 95 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Revise' Appendix A. Technical Specifications by removing the pages identified' {

below and. inserting the enclosed pages. The revised pages are identified .]

by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3-38 3-38 Table 3.19-1 --

4-26, 4-26 4-27' 4-27 1

4-28 4-28 4-29 4-29 1

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3.19 Snubbers Applicability: This specification applies to snubbers which are attached to the reactor coolant system and all other safety-related i y

r systems whose structural integrity is needed to be maintained during and following a seismic or other event initiating dynamic loads.

Objective: To assure reactor coolant system and other safety related system motions are adequately restricted should a design basis earthquake or other transient occur.

Specification: A. During Modes 1, 2, 3, and 4 (Modes 3 and 6 for '

snubbers located on systems required operable in those Modes) all safety-related snubbers shall be maintained in an operable condition except as noted in 3.19.B below. Snubbers on nonsafety-related systems shall be operable if their failure or failure of the system on which they are installed would have an adverse effect on any safety-related system.

B. 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 4.13.c on the supported component or declare the supported system inoperable and follow the appropriate specification for that system.

Bases All snubbers are required to be operable to ensure that the structural integrity c.

the reactor coolant system and all other safety-related systems are maintainn during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those insta!!ed 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.

When a snubber is found inoperable, an engineering evaluation is performed, in cddition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

Amendment No. 9, M , 95 3-38 P'

4.13 Snubbers I

1 Applicability: This specification applies to the snubbers required to be  ;

operable in accordance with Specification 3.19. I Objective: To provide assurance of snubber operability over the plant service lifetime.

Specification: Each snubber shall be demonstrated operable by performance of the following augmented inservice inspection program.

A. Visual Inspection Schedule All snubbers shall be visually inspected in accordance with the following schedule:

Number of Snubbers Found Inoperable During Inspection Next Required Or During Inspection Interval Inspection Interval *# l 0 18 months + 25 %

1 12 months ! 25%

2 6 months ! 25%

3, 4 124 days E 25%

5,6,7 62 days 1 25 %

8 or more 31 days 1 25 % l The snubbers may be categorized into two groups: those accessible, 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, i

1. The provisions of Specification 4.0.2 are not applicable.

B. Visual Inspection Acceptance Criteria Visual inspection shall verify (1) that there are no visible indications of damage or impaired operability, and (2) attachments to the foundation or supporting structure are secure. The inspection will also identify indications of excessive leakage from hydraulic snubber reservoirs or connections. Snubbers which appear inoperable as a result of visual inspections may be determined operable for the purpose l 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 that may be generically susceptible, and (2) the affected ,

snubber is functionally tested in the as-found condition and l determined operable per Specifications 4.13.D or 4.13.E, as i applicable.

4-26 Amendment No. 9, M , 95 L -____ ___ _ _

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C. - ~ Functional Tests j {

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l- At least 'once per 18 months during shutdown, a 5 y representative sample of at least 10% of the total of each  !

r type of 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 4.13.D or 4.13.E, an additional 5% of that type of snubber shall be functionally tested until no more failures are found or until all 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 j snubbers. At least one (1) snubber shall be selected from j each piping system containing snubbers. At least one (1) snubber shall be tested from the full range of snubber manufacturers and snubber sizes used. In the selection of .

the representative sample, consideration shall be given to i other effects on snubbers such as vibration in the vicinity of equipment such as pumps, motors, turbines, valves, etc.

or fluid forces from a relief valve discharge.

Functional test samples shall be rotated such that different snubbers are tested at each test interval.

In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period. If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these i snubbers may not be included for the re-sampling. { i If any snubber selected for functional testing either fails f to lockup or fails to move, i.e., frozen in place, the cause l will be evaluated and if caused by manufacturer or design )

deficiency, all snubbers of the same design subject to the i same defect shall be functionally tested. This testing requirement shall be independent of the requirements {

stated above for snubbers not meeting the 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 l engineering evaluation sha!! be to determine if the '

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4-27 Amendment No. $, 31, 95 l

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components supported by the snubber (s) were adversely I

affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of

,: meeting the designed service requirement.

D. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

2. Snubber bleed, or release rate, where required, is  !

within the specified range in compression or tension. 1 For snubbers specifically required not to displace "

under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

E. Mechanical Snubbers Functional Test Acceptance Criteria 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 the specified maximum drag force.

2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

3. Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under

, continuous load, the ability of the snubber to withstand load without displacement shall be verified.

F. Snubby S_ervice Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.h.

Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each safety-related snubber shall be reviewed to verify that the 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 will be exceeded prior to the next i

4-28 Amendment No. E , 95

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i scheduled snubber service life review, the snubber service

. life shall be reevaluated or the snubber shall be replaced 5 or reconditioned so as to extend its service life beyond l the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.

I Bases The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection 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 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 less than 25%) 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 of a 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, that 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.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18-month intervals. These tests will include stroking of snubbers to verify freedom of movement over the full stroke, restraining characteristics, and drag force (if applicable). Ten percent (10%) of the total of each type of snubber represents an adequate sampling for these tests. Observed failures on these samples require testing of additional units.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance program.

The service life is evaluated via manufacturer input and information with consideration of snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, high temperature areas, location of potential fluid transient loading, etc.) The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of age and operating conditions. (Due to implementation of the snubber service life monitoring program af ter several years of plant operation, the historical records to date may be incomplete.) Snubber service life records will provide a statistical basis for future consideration of snubber service life.

Amendment No. E , 95 4-29

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