ML20096E993

Amend 142 to License DPR-72,revising Snubber Visual Insp Requirements to Be Consistent W/Guidance Contained in Generic Ltr 90-09,dtd 901211

ML20096E993
Person / Time
Site:	Crystal River
Issue date:	05/04/1992
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20096E998	List: ML20096E993 ML20096E999
References
GL-90-09, GL-90-9, NUDOCS 9205200131
Download: ML20096E993 (9)

Text

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UNITED STATES 5

NUCLEAR REGULATORY COMMISSION k

[c WASMNGTON, D.C. 20566 ELORIDA P0WER CORPORATION

[]TY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF-KISSIMMEE

[1TY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION. CITY OF J[W SMYRNA BEACH

' CITY OF OCALA QB1ANDO UTILITIES COMMISSION AND CITY V ORLANDO SEMIN0LE ELECTRIC COOPERATIVE. INC.

'LLTY OF Tall AHASSEE QQ{d.LJ:t. 50-302

[RYSTAL RIVER UNIT 3 NUCLEAR GENERATING-PLANT AMENDMENT TO FACILITY OPERATING LICENSE--

Amendment No.142 4

License No. DPR-72 1.

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

A.

The application for amendment by Florida Power-Corporation, et al.

(the licensees) dated June 20, 1991, as supplemented December 19, a

1991 and January 20,-1992, complies with the standards-and requirements of-the Atomic' Energy Act of:1954; ~as amended- (the Act),

and the Comission's rules and:regelations _ set-forth in-10 CFR Chapter.I;-

B.

The facility will operate in confo'cmity withithe application, the provisions of the Act, and the ruies and regulations of.the:

Comission; C.

There is ieasonable 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; c

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 of.this amendmentLis in accordance with-10 CFR Part 51

.of the Comission's regulations;and all_ applicable requirements have been satisfied.

9205200131 920504 PDR ADOCK 05000302 j

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-PDR-

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. 2.

Accordingly, the. license in amended by Lchanges to the Technical Specifications as indicated in the attachment toithis license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-72 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as re'. ! sed through Amendment No.142, are hereby incorporated in' the license.

Florida Power Corporation shall operate theLfacility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance ana shall be implemented within 30 days.

F

-THE NUCLEAR REGULATORY-COMMISSION'

(~l Y

H rbert N. Berkow, Director Projecc Directorate.II-2 Division of Reactor Projects - 1/II Office of Nuclear. Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 4, 1992 l

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l ATTACHMENT TO LICENSE AMENDMENT NO,142 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by atendment number and.

contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert 3/4 7-25 3/4 7-25 3/4 7-26 3/4-7-26 3/4 7-35 3/4 7-35 B 3/4 7-5 B 3/4 7-5 l

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PLANT SYSTEMS 3/4.7.9 HYDRAULIC SNUB 8ERS LIMITING CONDITION FOR OPERATION 3.7.9.1 All hydranTic snubbers shall be OPERABLE.- The only_ snubbers-excluded om the requirement are those installed on non-safety related s),tems 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.

APPLICABILIT11 MODES 1, 2, 3, and 4.

ACTION:

With one or more hydraulic snubbers inoperable, replace or restore the inoperable snubber (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be-in at:least HOT-STAliD8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.9.1 Each snutber shall be demonstrated OPERABLE-by the performance of-the following augmented inservice inspection-program in addition to-the requirements of Specification.4.0.5.

a.

Insoection Tvolti.

As used in this specification, " type" shall apply to snubbers of the same design and manufacturer, irrespective of capacity.

s b.

Visual insnections

- Snubbers _are categorized as: inaccessible or accessible 'during_:

reactor operation._ Each of these1 categories (inaccessible-and accessible) may be-inspected =. independently;according to the-schedule determined by Table 4.7-4.

The Alsual inspection -

interval-for each category of snubber _ shall be determined based upon the criteria:provided in Table 4.7-4. -

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CRYSTAL RIVER - UNIT 3 3/4 7-25 Amendment No ' #E,77,EE,142; y

= _- A

~1 ELANT SYSTEMS HYDRAULIC SHUBBERS (Continued)

SURVEILLANCE RE0VIREMENTS (Continued) l c.

Visual Insnection Acceptance-Criteria Visual inspections shall verify that (1) the snubber has no -

visible indications of damage or impaired CPERABILITY, (2) attachments to'the foundation or supporting structure are functional, and (3)- fasteners' for =thecattachment of.the snubber to the component and to the' snubber anchorage'are functional.

Snubbers which-appear inoperable as a result ofLvisual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose 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 irrespective of-type that may be generically susceptible;cand-(2)-the affected--

snubber is functionally tested in the as-found condition and determined'0PERABLE.

All: snubbers found connected to an i

inoperable common hydraulic fluid reservoir shall be Lcounted as-I z

unacceptable for determining the next' inspection interval. A review-and evaluation shall be' performed-and documented-to justify continued operation with an unacceptable snubber If-continued operation cannot-be justified,'theLsnubber-shall be declared inoperable and the-ACTION requirements shall-be met.

d.

At least 'once-per 18 months during shutdown, a; representative sample of at least 10 hydraulic snubbers ~ or at least 10% 'of all snubbers referenced in Specification 3.7.9.1, whicheverLis less, shall be selected and functionally testedito verify correct piston movement, locktup and bleed. : Snubbers greater-s than 50,000 lbs. ' capacity-may.be; excluded:from functional:

testing requirements. Snubbers 1 selected;for functional: testing shall be selected on a rotating; basis.

Snubbersiidentified as either "Especially. Difficult:tc: Remove" or in "High: Radiation:

- Zones" may be exempted from functional testing-provided these L snubbers were demonstrated OPERABLE!during-previous functional' tests.

Snubbers fc'1r+ inoperable: during c functional-testing.

shall be 'restorec to OPERABLE status prior.toiresuming.

operation. ~ For each'snubbercfound Linoperable!during these functional tests, an. additional minimum: of-10% ofr a'l snubbersi or 10 snubbers, whichever~ is less,- shaliz also be fui.ctionaily-tested until no more. failures.are-found-or all: snubbers; have '

been. functionally tested.

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CRYSTAL RIVER - UNIT 3.

3/4 7-26

~ Amendment No. 58,142, i

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TABLE 4.i-4 i'

SNUBBER VISUAL INSPECTION INTERV8.L

-NUMBER OF UNACCEPTABLE'SNUMERS Populatton.

Column A Column-B Column-C:

l or Category Extended Interval Repeat Interval:-

Reduced IntervalL i

Sizes F

(Note 1)

(Note 2)

(Notes 3 and 5)

(Notes 4-and G)--

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100 0

1 4

150 0

3 8

L 200 2

5 13 j

300 5-

-12 25 1

400 8

18 36 k

i Note 1: 1 Snubbers may be. categorized, based upon their accessibility dur.ing-i

- rower operationnas -accessible or. inaccessible. These categories may l

be examined separately or jointly.' However, the licensee must make l

and document that decision-before-any inspection and shall use that-i decision as the b,. tis _upo_n which to' determine the next-inspection-interval for that category..

Note 2:

Interpolation between population or category si::es:and the number of:

unacceptable snubbers is. permissible. The'nexi; lower integer for the value of, the. limit for Columns A,' B, or C is used if that i

integer includes a fractional value of unacceptable snubbers as l

determined-by interpolation.

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Note 3:

If the number of unacceptable snubbers is equal to or less than the number in' Column-A, the next; inspection interval: mayibe twice the previous: interval but not greaterLthan 48 monthr.>

Note 4:

If the number of: unacceptable snubbers is equal to or:less than the' numoer in' Column B but greater than the number.in Column A-the next' L

inspection interval shall be the same as the: previous 11nterval..

Note-5:

If the number of unacceptable snubbers is equal to or greater than~-

i.

the number in Column C, tne next inspection intervallshall-be two-l thirds of the previous interval. -However,. ;if the number ofi L

unacceptable snubbers is lesu than dhe number in Column C.but-F greater than'the' number in Column 8,ithe next interval-shall be-

reduced proportionally-by interpolation,Lthat :is, the_ previous' 7

l interval shall be reduced by_ a. factor thatuis tone-third of the ratio of the difference between the number of. unacceptable snubbers found during the previous interval and the' number in: Column 3 toithe j-difference in the numbers in Columns B and C.

1 Note 6:

The provisions of. Specification 4.0.2 are applicable-for all.

inspection intervals up to and. including 48 months.

i CRYSTAL RIVER

. UNIT 3:

3/4-7-35~

. Amendment-No.;pp,pp,~.

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~77 m,142,.

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PLANT SYSTEMS 3/4.7.10 SEALED SCURCE CONTAMINATICN LIMITING CCNDIT,1J]ft FOR OPERATION 3.7.10.1 Ehch seahd source containing radioactive material either '.n excess of 100 microciries of br+a and/or gama emitting rtaterial or 5 zicroc'Jries of alpha witting material shall be free of 3,0.005 micro-curies of removable coitamination.

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APPLICABILITY _: At all t1ms.,

ACTION:

Each sealed source with removable contamination in excess of a.

the above.imit shall be imediately withdrawn from use and:

1.

Either decertaminated and repaired, or 2.

Disposed of in accordance with Comission Regulations.

b.

The provisions of Specifications 3.0.3 and 3.0.a are not applicabis.

SURVEILLANCE REOUIREMENTS 4.7.10.1.1 Test Recuirements - beh sealed source shall be tested for leakage and/or contamination cy:

a.

The licensee, or b.

Other persons specifically authorized by the Commission er an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcurieu per test sample, 4.7.10.1.2 Test Frecuencies - Each catey' y of sealed scurces shall be tested at the frequency described below.

Sources in use (excludino startuo soure_es and fission detectors a.

previously subjected to core flux) - At least once per six -

nontns for all seulec sources containing radioactive material:

CRYSTA!. R1YER - UNIT 3 3/4 7-36

ELANT SYSTfM BASES 3/4.7.8 AUXILIARY BUILDING VENTILATION EXHAUST SYSTEM The OPERADILITY of the Auxiliary Building ventilation axhaust system

[

ensures that suitable ambient conditions for personnel and equipment are maintained for all operating periods and that the effects of post accident conditions in the Auxiliary Building are mitigated.

Supply and exhaust duct systams are arranged f o direct air from areas of low to higher activity eventually directing it to the ma+

exhaust filter system and from there through the fans to the exhah vent.

The main exhaust filters include roughing, HEPA, and charcoal cells.

3/4.7.9. HYDRAULIC SNUHjfM The hydraulic snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and folleving a seismic or other event initiating dynamic loads.

The only snubbers excluded from this ic.spection program 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.

Tha inspection frequency applicable to sabbers containing seals fabricated from materials which have bet demonstrated compatible with their operating environment is based upon maintaining a constant level of snubber protection.

Therefore, the required inspection interval varies inversely with the observed :nubber failures.

To provide further assurance of snubber reliability, a representative sample 9 the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.

These tests will include stroking of the snubbers to verify proper piston l

movement, lock-up and bleed. Observed failures of these sample l

snubbers will require functional testing of additional units. To minimize personnel exposures, snubbers installed in high radiation zones or in especicily difficult to remove locations may be exempted from these functional testing requirements provided the OPERABILITY cf these snubbers was demonstrated during function;l testing at tither the coupletion of their fabrication or at a subsequent date.

l CRYSTAL RIVER - UNIT 3 B 3/4 7-5 Amendment No. Sit,142, I

4 PLANT SYSTEMS BASES l

R.~. ! C SE ALED SOURCE CONT AMINATION The limi:ations on removable rentamination for sourcei requiring leak testing, incjuding alpht emitters, is based on 10 CFR 70.39(c) limits for plutonium. This

!!mitation wii! ensure inat leakage from byprocu::, source, and special nuclear ma'erial sources wi!! not exceed a!!owable intake values.

3 /L.7.11 FIRE SUPPRi3510N SYSTEMS Tm C?ERASILITY of the fire sur ression systems ensures that adequate fire sappress;or cacacility is availacle to con!% anc extinguisn fires occurring in any portion cf :ne facili:y wnere safety A acc equipment is located.

Tne hre suppression system consists of tne water systern, deluge and sp-inklers, hose stations and Halon. The collective capability of the fire suppression systems is a: equate to mirumi:e potential damage to safety related equipment and is a major eleme.n in tne f acility fire protec-ion program.

In :he even: na portions of the fire suppression systems are inoperable, alternate backup fire fignung equipment is required to be made available in the aff acted areas un:1. ne aff ec:ec equipment can 5: res:orec :o service.

M the ever- -ha: the fire suppression water system becomes inoperable, immeciate

rre:.tve neasures mus: be taken since this system provices the major fire wpressi:t capacility of me plant. The requiremen for a twen y-four hour report

:ne Commission provides for prompt evaluation of the acceptability of the correc:ive measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

3/4.7.12 PENETRATION TIRE SARRIERS The func;ional Lntegrity of the pene: ration fire barriers ensures that fires will be confinec :.: adequately retarded from spreacmg to acjacent portions of the f acility.

This design feature minimizes the possibility of a single fire rapidly involving several areas of the f acility prior to detection and extinguishment.

The pnetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspection.

Fire barrier penetrations, including cable penetration barriers, fire doors and dampers are considered functional when the visually cbserved condition is the see as tne as-designed condition.

For these t' ire barrier penetra-tions that are not in the as-designed condition, an evaluation shall be performed to show that the modi fication has not degraded the fire rating of the fire barrier penetration.

During periods of time when a barrier i.s not functional, either 1) a continuous fire watch is required to be maintained in the vicinity of the affected_batfier, or 2) the fire detectors on at least one side of th,e.

affected barrier must be verified CPEPABLE and 'an hourl'y fire watch patrol

. established, until tne barrier is restored to functional status.

CRYSTAL TdVEE-UNIT 3 B34 7-6 Amendment No. 73, 65 s

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