ML20197D453

Amend 105 to License DPR-40,changing Tech Specs by Deleting safety-related Snubber Lists,Per Generic Ltr 84-13

ML20197D453
Person / Time
Site:	Fort Calhoun
Issue date:	03/26/1987
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20197D452	List: ML20197D447 ML20197D453 ML20197D462
References
GL-84-13, TAC-62173, NUDOCS 8704100009
Download: ML20197D453 (10)

Text

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. . l f r,eg Jy UNITED STATES

&g( n NUCLEAR REGULATORY COMMISSION

y WASHINGTON. D. C. 20655

\...../

OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 ,

l FORT CALHOUN STATION, UNIT NO. 1  !

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. DPR-40

1. The Nuclear Regislatory Comission (the Comission) has found that:

A. The application for amendment by the Omaha Public Power District (the licensee) dated August 19, 1986 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 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 (1) 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 comon defense and security or to the health and safety of the public; and E. The issuance )f 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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l 8704100009 870326 PDR ADOCK 05000285 1 P PDR

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2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, ,and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.105, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective 30 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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&h# HAW Asho C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B Attathment:

Changes to the Technical Specifications Date of Issuance: March 26, 1987 e

ATTACHMENT TO LICENSE AMENDMENT N0.105 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Pages Insert Pages 2-73 2-73 2-74 2-74 2-75 through 2-88a -

3-77 3-77 3-7E 3-78 3-79 3-79 3-79a 3-79a 5-19 5-19 4

2.0 LIMITING CONDITIONS FOR OPERATION 2.18 Shock Suppressors (Snubbers)

Applicability Operating Modes 1, 2 and 3 (Operating Modes 4 and 5 for snubbers located on systems required operable in those Operating Modes).

Specifications (1) All snubbers required to protect the reactor coolant and other safety related systems shall be operable except as noted in 2.18(2) through 2.18(4) below. These snubbers shall be identified as safety-related snubbers.

(2) With one or more safety-related snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l replace or restore the inoperable snubber (s) to operable status and perform an engineering evaluation per Specification 3.14(3) on the supported component or declare the supported system inoperable and follow the appropriate actions specified in the Technical Specifica-tions for that system.

(3) A safety-related snubber may be removed for surveillance in accordance I with Section 3.14(3) of these Technical Specifications, provided the following conditions are met:

(a) A given snubber station shall not be without an operable snubber for more than two hours during surveillance of attendant snubber. A snubber may be replaced by an operable snubber during surveillance and repair.

(b) No other snubber station is known to be inoperable. I (c) Only one snubber station shall be removed for testing at l a time to ensure that no two snubber stations are without an operable snubber during the same time interval.

(4) Safety-related snubbers may be added, changed, or deleted provided an engineering analysis justifies each change.

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Amendment No. 27,M,H,105 2-73

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2.0 LIMITING CONDITIONS FOR OPERATION 2.18 Shock Suppressors (Snubbers)

Basis Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup or shutdown.. The conse-quence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a seismic, or other event, initiating dynamic loads. 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.

Because the snubber protection is required only during low probability events, an inoperable period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements and an inoperable period of two hours is allowed for surveillance.

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l Amendment No. 27, ($, jf ///,105 2-74 (next page is 2-89) l

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l l 3.0 SURVEILLANCE REQUIREMENTS l

i 3.14 Shock Suppressors (Snubbers)

Applicability This specification applies to all safety-related snubbers.

Specifications (1) All hydraulic snubbers whose seal material has been demonstrated by operating experience, lab testing or analysis to be compatible with the operating environment shall be visually inspected. This inspection shall include, but not necessarily be limited to, inspection of the hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchor to verify snubber operability. In those locations where snubber movement can be manually induced without disconnecting the snubber, verify that the snubber has freedom of movement and is not frozen up. Visual inspe.tions shall be performed in accordance with the following schedule:

Number of Hydraulic Snubbers Found Next Required Inoperable During Inspection or Inspection During Inspection Interval Interval 0 18 months + 25%

1 12 months T 25%

2 6 months + 25%

3, 4 124 days T 25%

5,6,7 62 days + 25%

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31 days T 25%

The required inspection interval shall not be lengthened more than one step at a time.

Snubbers may be categorized in two groups, " accessible" or

" inaccessible", based on their accessibility for inspecticn during reactor operation. These two groups may be inspected independently according to the above schedule.

(2) All hydraulic snubbers whose seal materials are other than eythlene propylene or other material that has been demonstrated to be compatible with the operating environment shall be visually inspected for operability every 31 days.

(3) At least once per 18 months during shutdown and subject to the conditions below:

(a) A representative sample (88) of hydraulic snubbers shall be functionally tested either in-place or in a bench test.

I Amendment No. 27,59,105 3-77

3.0 SURVEILLANCE REQUIREMENTS 3.14 Shock Suppressors (Snubbers) (Continued)

(i) For each hydraulic snubber above 3 which does not meet the functional test acceptance criteria, an additional sample of 22 hydraulic snubbers shall be functionally tested.

(ii) For each inoperable hydraulic snubber found during a resample test, an additional 22 hydraulic snubbers will be tested until no additional inoperable hydraulic snubbers are found within a sample or until all hydrau-lic snubbers have been functionally tested; and (b) 10% of the safety-related mechanical snubbers shall be functionally tested either in-place or in a bench test.~

(i) For each mechanical snubber which does not meet the functional test acceptance criteria, an additional sample of 10% of the mechanical snubbers shall be functionally tested.

(ii) For each inoperable mechanical snubber found during a resample test, an additional 10% of the mechanical snubbers will be tested until no additional inoperable mechanical snubbers are found within a sample or until all mechanical snubbers have been functionally tested.

(c) The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At least 25% of the snubbers in the representative sample shall include snubbers from any of 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.

Snubbers that are especially difficult to remove or in high radiation zones during shutdown shall also be included in the representative sample. Permanent or other exemptions from functional testing for individual 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.

(d) 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 snubbers may not be included for the resampling.

Amendnent No. 27,U,105 3-78

3 3.0 SURVEILLANCE REQUIREMENTS

! 3.14 Shock Suppressors (Snubbers) (Continued)  ;

If any snubber selected for functional testing either fails to lockup l or fails to move, i.e., is frozen in place, the cause will be evaluated. If.the cause is a manufacturer or: design deficiency, i appropriate action shall be taken for snubbers of the same design subject to the same defect to determine if any more defects. exist.

This testing requirement shall be independent of the requirements

< stated above for snubbers not meeting the functional test acceptance criteria.

For any snubber (s) found locked up during normal operation or found '

inoperable following a seismic event, an engineering evaluation shall be performed on the comoonents which are supported by the snubber (s).

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

If the engineering evaluation shows the components to be capable of meeting the designed service without the failed snubber, that snubber may be deleted from service per Specification 2.18(4). l (4) Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the i designated service life commences.and the installation and maintenance 3 records on which the designated service life is based shall be main-tained as required by Specification 5.10.2.m. At least once per 18 months the installation and maintenance record for each snubber shall l 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 scheduled snubber service life review, the snubber service life shall be re-evaluated 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 re-evaluation, replace-ment or reconditioning shall be indicated in the records.

Basis All safety-related snubbers shall be operable to ensure that the structural l '

integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initi-ating dynamic loads. Snubbers excluded from this inspection program are >

those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse i effect on any safety-related system.

. 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 Amendment No. 17,59, 105 3-79

3.0 SURVEILLANCE REQUIREMENTS 3.14 Shock Suppressors (Snubbers) (Continued) number of inoperable snubbers found during an inspection. Inspections perfonned before that interval has elapsed may be used as a new reference point to detemine the next 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 a snubber is found locked up or frozen in place or when a snubber has been inoperable during a seismic event, an engineering evaluation she.ll be performed, in addition to the determination of the snubber mode of failure.

The purpose of the engineering evaluation is 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 nat the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

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. Selection of a representative sample of hydraulic snubbers according to the expression 35(1+c/2) provides a confidence level of approximately 95% that 90% to 100% of the snubbers in the plant will be operable within acceptance limits. The District selected the value of c to be 3. Observed failures of these sample snubbers shall require func-tional testing of additional units. For each number of snubbers above c which does not meet the functional test acceptance criteria, an additional sample selected according to the expression 35(1+c/2)(2/(c+1))2(a-c) will be functionally tested, where a is the total number of snubbers found inopera-ble during the functional testing of the representative sample. Functional testing will continued according to the expression b(35(1+c/a)(2/(c+1))2) where b is the number of snubbers found inoperable in the previous resample, until no additional inoperable snubbers are found within a sample or until all snubbers have been functionally tested.

A "10%" criterion is utilized for mechanical snubbers because of the considerably smaller number of mechanical snubbers.

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

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and 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 1 evaluation in view of their age and operating conditions. These records 1 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. l I

, Amendment No. 59,105 3-79a 4

5.0 ADMINISTRATIVE CONTROLS 5.10.2 The following records shall be retained for the duration of the Facility Operating License:

a. Records of drawing changes reflecting facility design modifications made to systems and equipment described in tha Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of facility radiation and contamination surveys.

d. Records of radiation exposure for all individuals entering radiation control areas.

e. Records of gaseous and liquid radioactive material released to the environs,

f. Records of transient or operational cycles for . iose facility com-ponents designed for a limited number of trans' ents or cycles.

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

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

1. Records of Quality Assurance activities requiral by the QA Manual.

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Records of reviews perfonned for changes made tc procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the Plant Review Comitte and the Safety Audit and Review Comittee.

1. Records of Environmental Qualification of Electr e Equipment pursuant to 10 CFR 50.49.

m. Records of the service lives of all hydraulic and uechanical snubbers which are covered under the provisions of Section 2.18 of the Technical Specifications, including the date at which the service life commences and associated installation and maintenance records.

n. Records of analyses required by the Radiological Environmental Monitoring Program.

5.10.3 A complete record of the analysis employed in the selection of any fuel assembly to be placed in Region 2 of the spent fuel racks will be retained as long as that bundle remains in Region 2.(reft.rence Technical Specifica-tions 2.8(12) and 4.8.4).

5.11 Radiation Protection Program Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. i l

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l 5-19 9/# f 19/#/$9, Amendment No. 59,$5,93,99,105 l

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