ML20148S590

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Amend 59 to License DPR-34,deleting Tabular Listing of safety-related Snubbers from Tech Specs
ML20148S590
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 04/07/1988
From: Calvo J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20148S568 List:
References
NUDOCS 8804190098
Download: ML20148S590 (9)


Text

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  • O i NUCLEAR REGULATORY COMMISSION

'j W ASHING TON, D. C. 20555

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PUBLIC SERVICE COMPANY OF COLORADO p0CKETNO.50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AltENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. OPR-34

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

A. The application for amendtnent by Public Service Company of Colorado (the licensee) dated December 23, 1986 as supplemented December 17, '

.. 1987, complies with the standards and re Energy Act of 1954, as amended (the , and Act)quirements the Comission's of the Atemic rules and regulations set forth in 10 CFR Chapter I; ,

B. The facility will operate in conformity with the application, as amended, 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 cerducted in compliance with the Comission's regulations; D. The issuance of this license amendment will rot 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 the Comission's regulations and all applicable requirements have

'been satisfied.

8004190090 000407 PDR ADOCK 05000P67 P ppa

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. OPR-34 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications centained in Appendices A and B, as revised through Amendment No,59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amerdmant is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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d , d/N Jose A. Calvo, Director <

Project Directorate - IV Division of Reactor Projects - III, l IV, Y and Special Projects l

j Office of Nuclear Reactor Regulation l

Attachment:

l Changes to the Technical l

Specifications Date of Issuance: April 7,1988 8 6 F

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'4 e ATTACHP.ENT TO LICENSE AffENCPENT NO. 59 FACILITY OPEPATING LICENSE NO. OPR-34 DOCKET NO. 50-267 Replace the following pages of the Appendix A Technical Specifications with the attached pages as indicated, the revised pages are identified by ar.endment rumber and contain vertical lines indicating the areas of change.

Pemove Insert

  • 4.3-7 4.3-7 ,

4.3-8 4.3-8 4.3-9 to -

4.3-16 5.3-9 5.3-9 5.3.10 5.3-10 ,

5.3-11 5.3-11 5.3-15 - 5.3-15 e

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Fort _St. Vrain #1 Technical Specifications ,

Amendment No. /7,51 '

Page 4.3-7 Specification LC0 4.3.10 - Shock Suppressors ($nubbers) -

1.imitino Condition for Operation a) The reactor shall not be operated at power unless all l

Shock suppressors (snubbers) supporting Class I piping 1

systems are operable except as noted in b) through d) of this LCO.

l b) With one or more snubbers removed from service in a Class I system or subsystem, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace ,

i or restore the snupber(s) to operable status. If one l

or more snubber (s) is found inoperable, within 72 e

I huurs replace or restore the inoperable snubber (s) and perform an engineering evaluation per Specification $R 5.3.8.c) on the supported component or declarm the supported system inoperable &Ld follow the appropriate action staterrent for that system.

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c) If the requirements of a) and b) of this LCO cannot be ,

met, an orderly shutdown shall be initiated and the f

reactor shall be in a low power condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. ,

4 d) If a shock suppressor is determined to be inoperable while the reactor is in the shutdown or refueling mode, the suppressee shall be made operable or replaced prior to reactor operation at power.

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,'~ Fort St. Vrain #1 Technical Specifications Amendment No. # ,59 Page 4.3-8 P

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Basis for Specification LC0 4.3.10

$ hock suppressors (snubbers) are designed to prevent unrestrained pipe motion under dynamic loads, as might occur during an earthquake, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubbec is an increase in the probability of structural damage to piping resulting from the dynande loads produced by a seismic event. It is therefore necessary that all snubbers required to protect the e Class I systems, subsystems, or componests be operable during reactor power operation.

Because snubber protection is required only during relatively low probability events, a 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 repair or replacement. In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a low power condition will pe rmit an orderly power reduction consistent with standard operating procedures. 31rce reactor operation at power should not be conducted with defective safety-relsted equipment, reactor power

- operation is prohibited with inoperable snubbers, except as Jteted above.

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Fort St. Vrain #1 Technical Specifications Amendment No. 47,59 Page 5.3-9 activity level decreases to less than 10% of the limit of LCO 4.3.8, at which time weekly sampling may be resumed.

Basis for Specification $R 5.3.7 The specification surveillance interval is adequate to monitor the activity of the secondary coolant.

Specification SR $.3.8 - Shock Suppressors ($nubbers)

Surveillance ,

The following surve'lliance requirements apply to all Class I piping system shock suppressors (snubbers): '

a) Visual Inspections The first in-service visual inspection of snubbers shall be performed within six months from issuance of l this Technical $pecification (Amenoment H ). For the purpose of entering the schedule described in this section, it shall be assumed that the factitty had been on a six-month inspection interval. i

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Fort St. Vrain #1 Technical Specifications Amendment No. A7, 59 Page 5.3-10 4

The first in-service visual inspection of snubbers l shall include all Class ! piping systes snubbers. If less than two snubbers are found inoperable during the first in-service visual inspection, the second in-service visual inspection shall be performed 12 months plus or minus 25% from the date of the first inspection. Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:

period Inspection period' 0 18 Months plus or minus 254 1 12 Months plus or minus 25%

2 6 Months plus or minus 25%

3, 4 124 Days plus or minus 25%

5,6,7 62 Days plus or minus 25%

8 or more 31 Days plus or minus 25%

'The inspection interval shall not be lengthened more than one step at a time, b) Visual inspection Acceptance Criteria Visual inspections shall verify (1) that there are no l

visible indications of damage or impaired operability, j (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has j freedom of movement and is not seized. Snubbers which appear inoperable as a result of visual l

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, Fort St. Vrain el Technical Specific Amendment No M . DV gions Page 5.3-11 Inspections may be determined operable for the purpose of establishing the next visual inspection interval, providing that (1) the cause of .the rejection is clearly estabitshed and remedied for that particular snubber 49d 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 Sections 5.3.8.d) and 5.3.8.e). However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERA 8LE via functional testing for the purpose of establishing the next visual inspection interval. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

c) Functional Tests ,

At least once' per 18 months (not to exceed 221/2 months),a representative sample of each type of '

Snubber shall be tested using one of the following sample plans: The sample plan (s) 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 (s) selected for each type of snubber prior to the test period or the sample plan (s) used in the prior test period shall be implemented:

1) At least 10% of the total of the type of snubber shall be functionally tested either in place or in e a bench test. For each snubber of that type that does not meet the functional test acceptance critsria of Specification $R 5.3.8.d) or SR 5.3.8.e), an additional 10% of that type of F

Fort St. Vrain #1 Technical Specific Amendment No. 47. 3 $tions

, Page 5.3-15 f) Enemetten From Visual Inspection or Functional Tests Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the l Commission if a justifiable basis for 9xemption is l presented.

I g) neeord x...ino Record keeping shall consist of e

1) A historical record for each snubber shall be maintained. <
2) Concurrent with the first in-service visual inspection and at least once per refueling cycle thereafter, the historical recards for each l snubber shall be reviewed to deteen.ine any trends that may adversely affect service life.
3) The maximum expected service life for the various seals, seal materials, and applications shall be

! determined and established based on engineering information and the seals shall be replaced so that the maximum espected service Itfe will not be I *

! exceeded during a period when the snubber is required to be OPERABLE. This monitoring progras

.. shall be fully implemented within 22 1/2 months l

from the issuance of this Technical Specification (Amendment 39).

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