ML20100D951

Amend 113 to License DPR-49,changing Snubber Testing from 10% to 5% & Deleting Requirement to Increase Drag Force by 50% During Snubber Functional Tests

ML20100D951
Person / Time
Site:	Duane Arnold
Issue date:	03/12/1985
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Corn Belt Power Cooperative, Central Iowa Power Cooperative, Iowa Electric Light & Power Co
Shared Package
ML20100D955	List: ML20100D951 ML20100D967
References
DPR-49-A-113 NUDOCS 8504030197
Download: ML20100D951 (16)

Text

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NUCLEAR REGULATORY COMMISSION 3

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WASHINGTON, D. C. 20555

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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IDWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 113 License No. DPR 40 1.

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

A.

The application for amendment by Iowa Electric Light & Power Company, et al, dated August 20, 1984, as revised September 14, 1984, 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; B.

The f acility 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 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.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paraoraph P.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:

& A N $ N 31 P

PDR s

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(2) Technical Specifications The Technical Specifications contained in Appendic'es A and B, as revised throuah Amendment No. 113, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license anendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Rranch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 12,1985 r

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v ATTACHMENT TO LICENSE AMENDMENT NO. 113 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Revise the Appendix A Technical Specifications by removing the current pages and insertino the revised pages listed below. The revised areas are identified vertical lines.

LIST OF AFFECTED PAGES vi 3.6-10 3.6-11 1

3.6-12 3.6-13 3.6-14 3.6-15 3.6-37 3.6-38 3.6-39 3.6-40 3.6-41*

3.6-42(deleted 3.6-43 (deleted 3.6-44 (deleted 3.6-45 (deleted 3.6-46 (deleted) 3.6-47(deleted) 3.6-48 (deleted) 3.6-49 (deleted) 4 6.10-3

• Figure 3.6-1 was formerly on page 3 6-49 l

)

i

DAEC-1 TABLE NO.

TITLE PAGE NO.

4.2-D Minimum Test and Calibration Frequency for Radiation 3.2-29 Monitoring Systems 4.2-E Minimum Test Calibration Frequency for Drywell Leak 3.2-30 Detection 4.2-F Minimum Test Calibration Frequency for Surveillance 3.2-31 Instrumentation 4.2-G Minimum Test and Calibration Frequency for 3.2-34 Recirculation Pump Trip 3.6-1 Nunber of Specimens by Source 3.6-33 3.7-1 Containment Penetrations Subject to Type "B" Test 3.7-20 Requirements 3.7-2 Containment Isolation Valves Subject to Type "C" Test 3.7-22 Requirements 3.7-3 Primary Containment Power Operated Isolation Valves 3.7 25 4.7-1 Summary Table of New Activated Carbon Physical 3.7-50 Properties 4.10-1 Sunnary Table of New Activated Carbon Physical 3.10-7 Properties 3.12-1 Deleted 3.12-2 MCPR Limits 3.12-9a 3.13-1 Fire Detection Instruments 3.13-11 3.13-2 Required Fire Hose Stations 3.13-12 6.2-1 Minimum Shift Crew Personnel and License Requirements 6.2-3 6.9-1 Protection Factors for Respirators 6.9-8 6.11-1 Reporting Sunnary - Routine Reports 6.11-12 6.11-2 Reporting Sunnary - Non-routine Reports 6.11-14 V

Amendment No.113

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DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT H.

Shock Suppressors (Snubbers)

H.

Shock Suppressors (Snubbers)

1. During all modes of Each safety-related snubber operation, except Cold shall be demonstrated OPERABLE Shutdown and Refuel, all by performance of the following safety-related snubbers inservice inspection program.

shall be operable, except as noted in 3.6.H.2.

1.

Visual Inspections

2. With one or more snubbers The inservice visual inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inspection of snubbers replace or restore the shall be performed in inoperable snubber (s) to accordance with the OPERABLE status and perform following schedule:

an engineering evaluation per Specification 4.6.H.3 Nunber of on the supported component -

Snubbers Found or declare the supported Inoperable During Next Required system inoperable.and Inspection or Visual follow the appropriate During Inspection Inspection Limiting Conditions For Interval Interval Operation for that system.

0 18 months + 25%

1 12 months 17 25%

2 6 months 17 25%

3,4 124 days II 25%

5,6,7 62 days

][25%

),8 31 days

+ 25%

The required inspe'ction interval shall not be lengthened more than one step at a time.

3.6-10 Amendment No. 113

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DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT Snubbers are categorized in two groups inaccessible"ccessibleand "a

based on theiraccessIbilityfor inspection during reactor operation. These two groups will be inspected independently according to the above schedule.

2.

Visual Inspection Acceptance Criteria Visual inspection shall verify (1)dications of that there are no visible in damage or impaired OPERABILITY, (2) (for hydraulic snubbers) inspection of the hydraulic fluid reservoir and fluid connections, (3) attachments to the foundation or st'pportiny structure are secure, and (4) in those locations where snubser movement can be manu611y induced without disconnecting the sn;bber, that the snubber has freedom of movement and is not frozen. Snubbers which appear inoperable as a result of visual inspection, may be determined to be OPERABLE for the purpose of establishing the next visual inspection interval, of the rejection (1)is clearly providing that the cause established and remedied for that particular snubber and for other snubbers that may be generically or operationally susceptible; and (2) the affected snubber is functionally tested in 1

the as-found condition and l

determined to be OPERABLE per specifications 4.6.H.4 or 4.6.H.S as applicable.

However, wiien the fluid port of a hydraulic snubb-is found to be uncovered, the snubber shall be determined to be inoperable and cannot be considered OPERABLE via functional testing for the purpose of establishing the next visual inspection j

interval.

3.6-11 Amendment No.113

DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.

Functional Tests At least once per 18 months a representative sanple (10%

of the total of safety-related of each 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 4.6.H.4 or 4.6.H.5, an additional 5% of l

that type of snubber shall be functionally tested.

The representative sample selected for functional testing shall represent the various configurations,

. operating environments and range of sizes of snubbers.

At least 25% of the snubbers in the representative ssnple shall include snubbers from the following three categories:

1.

The first snubber away from each reactor vessel nozzle 2.

Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.)

3.

Snubbers within 10 feet of the discharge from a safety relief valve In addition to the regular sample, snubbers which f ailed the previous functional test shall be retesh.d during the next test period. If a spare snubber has been installed in place of a failed snubber, then 3.6-12 Amendment No. 113

=

DAEC-1 i

LIMITING CONDITIONS FOR OPERATION.

SURVEILLANCE REQUIREMENT both the failed snubber (if it is repaired and. instal. led 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 functional testing either f ails 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 requirenent shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

For any snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are restrained by the snubber (s).

The purpose of this engineering evaluation shall be to determine if the components restrained by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the component remains capable of meeting the designed service requirement.

3.6-13 Amendment No.113

DAEC-1 LIMITING CONDITION FOR OPERATION SURNEILLANCEREQUIREMENT 2.

Snubber bleed, or release rate is within the specified range in compression or tension.

For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

5.

Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

)

1.

The drag force of any snubber in tension and compression is less than the specified maximum drag force.

2.

Activation (restraining l

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

3 3.6-14 Amendment No.113

DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.

Snubber release rate, l

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.

6.

Snubber Service 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 6.10.2.13.

Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber l

shall be reviewed to verify that the indicated service life has not been exceeded and will not be exceeded l

prior to the next scheduled snubber service life review.

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

3.6-15 Amendment No. 113

=

DAEC-1 The type of inspection planned for each component depends on location, accessibility, and type of expected defect. Direct visual examination is proposed wherever possible since it is fast and reliable.

Surface inspections are planned where practical, and where added sensitivity is required. Ultrasonic testing or radiography shall be used where defects can occur in concealed surfaces. Appendix J of the DAEC FSAR provides details of the inspection program for the first 40-month cycle.

3.6.H & 4.6.H BASES:

Shock Suppressors (Snubbeis)

Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or other severe transient, while accommodating normal thermal motion during system startup and shutdown.

The consequence of an inoperable snubber is an increase in the probability of damage to piping as a result of a seismic or other event initiating dynamic loads or, in the case of a frozen snubber, exceeding allowable stress limits during system thermal transients.

It is therefore required that all snubbers required to protect the primary coolant system or any other safety system or component be operable during reactor operation.

3.6-37 Aner.dncnt flo.113

DAEC-1 All safety-related snubbers are visually inspected for overall integrity and operability. The inspection will include verification of adequate hydraulic fluid reserve, when applicable, proper attachment of snubber to piping and structures, and an overall assessment of the condition of each snubber.

The inspection frequency is based upon maintaining a constant level of snubber protection. Thus the required inspection interval varies inversely with the number of observed snubber failures, i.e., the number of inoperable l

snubbers found during a required inspection determines the time interval for the next required inspection.

Inspections performed before that interval has elapsed may be used as a new reference for determining the next l

inspection.

However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 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 for rejection of a snubber during visual inspection 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 inoperatjle. Generically susceptible snubbers are those which are of a 4

9 3.6-38 Amendment No.113 n

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DAEC-1 specific make or model and have the same design features directly related to the cause of rejection of the snubber, or are similarly located or exposed to the same environmental conditions such as hunidity, temperature, radiation, and vibration.

To further increase the assurance of snubber reliability, functional tests will be performed once per each 18 mor.ths. These tests will include stroking of the snubbers to verify. proper movement, restraining characteristics and drag force (if applicable). Ten percent (10%) of the total of each type of snubber represents an adequate sample for such tests.

Observed failures on these samples require testing of additional units.

When a snubber is found inoperable, an engineering evaluation is performed to determine the snubber mode of failure and identify any safety-related component or system that may have 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.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and 3.6-39 Amendment No. 113

DAEC-1 associated installation and maintenance records (newly installed snubber, 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 age and operating conditions. Due to implementation of the snubber service life monitoring program after several years of plant operation, the historical records to date may be incomplete.

The records will be developed from engineering data available.

If actual installation data is not available, the service life wil1 be assumed to commence with the initial criticality of the plant.

These records will provide statistical bases for future consideration of snubber service life.

The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

3.6 and 4.6 References 1)

General Electric Company, Low-Low Set Relief Logic System and Lower MSIV Water Level Trip for the Duane Arnold Energy Center, NEDE-30021-P, January, 1983.

3.6-40 Amendment No. 113

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f 3.6-41 Amendment No. 113

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DAEC-1 7.

Records of training and qualification for current members of the plant staff.

8.

Records of in-service inspections performed pursuant to these Technical Specifications.

9.

Records of Quality Assurance activities required by the QA Manual.

' 10. Records of reviews p'e'rformed for changes made to pr'ocedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

11. Records of meetings of the Operations Committee and the Safety Committee.

12. Records for Environmental Oualification which are covered under the provisions of paragraph 6.13.

13. Records of the service lives of all safety-related hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.

6.10-3 Amendment No.113

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