ML20081K539
| ML20081K539 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/18/1991 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081K541 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9106280098 | |
| Download: ML20081K539 (9) | |
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UNITED STATES Vs NUCLEAR REGULATORY COMMISSION
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DUKE P0WE,R,,C,0MPAtiY fiOR1H CAR 0LillA ELECTRIC ftEf ttERSHIP CORPORATION
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DOCKET 110. 50-413 C AT AWPA tRU,CLE,AR, STAT 10ti, UN1,T, j Af4Et:DtiElli TO FACILITY OPERAT1tlG LICEtlSE Ariendo.er,t flo, 88 License flo. tiPF-35 1.
The I:ucicar Pcgulatory Cortission (the Commission) has found that:
A.
The en licet ien for ariendo.ent to the Catawba t!uclear Station, Unit 1 (the facility) Facility Operating License tio. NPF-35 filed by the Dule Power Company, acting for itself, t; orth Carolina Elcctric l'er tarship Corpoiation and Saluda river Electric Cooperative, Inc.
'lico, tees) dated April ?,1991 complies with the standards and ruivirtr,u.ts of the Atoric Energy Att of 1954, as amended (the Act),
and the Connission's rules and regulations as set forth in 10 CFR Chapter 1; D.
The f acility v.ill operate in conforriity with the application, the previsions of the Act, and the rules and regulations of the Con <rissiu ;
C.
Thcre is reascrable assurance (i) that the activities authori:ed by this ar.u drent can be conducted without endangering the health and seft-ty of the public, and (ii) that such activities will be conducted in con:pliance with the Conciission's regulations set forth in 10 CFR Chapter 1; i.
The issuance of this anendnent will oct be inimical to the common defense and security or to the hecith and safety of the public; and f.
The issuance of this an4endnent is in accordance with 10 CFR Part 51 of the Corrission's regulations and all applicable requirements have been satisfied.
l 9106280090 910618 PDR ADOCK 05000413 P
. T.
Accordingly, the license is hereby amended tiy page changes to the Technical specificationi as indicated in the attachnent to this license oriendn.ent, and Paragraph F.C.(P) of f acility Operating License tio.14PF-35 is hereby an'end(d to read as follows:
Technical Sp,(cj,fications The Technical Specifications containeci in Appendix A, as revised through Arrendrent tJo. 88, and the Environn> ental Protection Plan containec' in Appendix 0, both of which are attached hereto, are hertby incorporated into this license. Duke Power Cornpany shall opera *e th( f acility in accordance with the Technical Specifications anc' the Envirornental Protection Plan.
Thit licer,se ar,endn+nt is ef fective as of its date of issuance.
4 F00 THE lit'CLE AR _ REGifLATORY COMMISS1011 0$ M4 Cas P. !!atthews, Director Project Directorate 11-3 Division of Reactor Projects-1/11 Office of t'uclear Peactor Regulatico A*tochrtrt:
Techtital Erfcificatier Changes Pett of 'ssuer.ce:
June 18. 1991 i
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UNITED STATES 2?'
i NUCLEAR REGULATORY COMMISSION
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WASmNGTON. D C ?W4 i
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DilKE POWER C0t<PAtiY l
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[_1 E Df'Of:Lf'pplCR((.,[0y,Ef,3[s[pCy DOCKET 00. 50-414 ih CATAWLA f p,Ch u STAT 10tk L141T,f bf.Epptf Ep,T, JO,[ A y,1JY 0PER ATINCi_ L ICEtiSE Anendt.ent f:o.
82 L icense flo, fiPF-EP 1.
Th( f:uclear h c ulatcry Cort it 5
- on (the Conir issict ) has f ound that:
1 The eglicatico for amendr ent to the Catawba f:uclear Station, l' nit ?
(the f acility) Fetility Operatirg iicense flo, flPF-52 filed by the Dub Power Corpry, active fcr itself, !! orth Carolina l'unicipal power Agency t'o.1 aid Piedront t'uniciral Power Agency (licensees) dated April 7,1901 corrplies with the staridards and requirer.ents of the Atoriit Energy Act of 19E4, as arerided (the Act), and the Commission's rules erd iegulations es set forth in 10 CFR Chapter 1; F.
The f acility will operate in conferr ity with the application, the provisica of the Act, and the rules and regulations of the C or:rii s sio r ;
There is reasoret le assurhnte (i) tLat the activities authorized by C.
this ar t odrent ton tie cortuctec' without endangering the health and seft ty of the public, and (4i) that such activities will be conducted in corpliance with the Commission's regulations set forth in 10 CFF Chapter I; D.
The issuance of this enendnent will not be inimical to the common defense and security or to the health and safety of the public; and f.
The issuance of this enendnent is in accordance with 10 CFR Part 51 of the Conmission's regulations and all applicable requirements have been set isfiec'.
7-T.
Ac cordir, gly, t t t license is heret.y er er.ded t>y page changes to the Technical
!pecificatier,s as indicated in the attachnent to this license anendr,ent, arid Paragraph ?.C.(7) of f acility Operating License fio. titr-LP is hereby arended to read as follows:
i Ieh!i!'.i 81..SITF.i.f i c a t i o n s f
The Technical !pecifications contained in Appendix A, as revised through An,endtrent tio. 82 arid the Environniental Protection Plan contairied in Appendix 0, both of which are attached hereto, are heret>y incorporated into this license.
Dule Power Cornpany shall operate the facility iri accordance with the Technical Specifications and the Environniental Protection Plan.
2.
't i ! lict t;se an endr er,t is effcctive as of its dote of issuatic(.
I DI: 1PE 1100t [ At nf gut ATOPY C0!'.f'l!f10!!
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lias ic f l'8t t hews, Dirt c t or Project Directorate 11-3 Divisic.r ef Reactor Project s-1/ll Office of iucitar Peactor Pogulation Id '. a c t i ( r t -
Tt-ita ital fi c c ificct iet: Changes Patt of 1ssuerce:
June 18. 1991
ATTACHMENT TO LICENSE AMENDMENT NO. 88 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with j
the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Pages insert Pages 4
3/4 7-19 3/4 7-19 3/4 7-19a 3/4 7-19b 3/4 7-20 3/4 7-20
PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION t
3.7.8 All snubbers shall be OPERABLE.
The only snubbers excluded from the requirements are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are instaHed would have no adverse effect on any safety-related system.
l APPLICABILITY:
MODES 1, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE
.'n those MODES.
ACTION:
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 4.7.8g. on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program in lieu of the requirements of Specification 4.0.5.
a.
Inspection Types As used in this specification, " type of snubber" shall mean snubbers l
j of the same design and manufacturer, irrespective of capacity.
b.
Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor 4
operation.
Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7-2.
The visual inspection interval for each category of snubber shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment 88 (Unit 1) and Amendment 82 (Unit 2).
l CATAWBA - UNITS 1 & 2 3/4 7-19 Amendment No. 88 (Unit 1)
Amendment No. 82 (Unit 2)
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Table 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL
+
l NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval (Notes 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) 1 0
0 1
d 80 0
0 2
100 0
1 4
i 150 0
3 8
200 2
5 13 i
300 5
12 25 400 8
18 36 500 12 24 48 4
750 20 40 78 1000 or greater 29 56 109 Note 1:
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspec-tion interval and the numb r of unacceptable snubbers found during e
that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as e cessible or inaccessible.
These categories may be examined separately or jointly.
- However, the licensee must make and document that decision before any inspec-tion and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
Note 3:
If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
Note 4:
If the number of unacceptable snubbers is equal to or less than the number in Column B but greater that the number in Column A, the next a
inspection interval shall be the same as the previous interval.
Note 5:
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of unaccept-able snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced propor-tionally by interpolation, that is, the previous interval shall be CATAWBA - UNITS 1 & 2 3/4 7-19a Amendment No. 88 (Unit 1)
Amendment No. 82 (Unit 2)
Table 4. 7 2 (Continued)
SNUBBER VISUAL INSPECTION INTERVAL reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
1 1
i t
l l
t CATAWBA - UNITS 1 & 2 3/4 7-19b Amendment No. 88 (Unit 1)
Amendment No. 82 (Unit 2)
PLANT SYSTEMS SUR/EILLANCE REQUIREMENTS (Continued) l c.
Visual Inspection Acceptance Criteria q
Visual inspections shall verify that:
(1) the snubber has no visible 4
indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result i
of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that:
(i) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be f
generically susceptible; and (ii) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.8f.
All.cnubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable and may be reclassified as acceptable for determining the next inspection interval provided that criterion (i) and (ii) above are met.
A review and evaluation shall be performed and documented to justify continued j
operation with an unacceptable snubber.
If continued operation cannot be justi',ed, the snubber shall be declared inoperable and the ACTION requirements shall be met.
d.
Refueling Outage Inspections At each refueling, the systems which have the potential for a severe i
dynamic event, specifically, the Main Steam System (upstream of the main steam isolation valves) the main _ steam safety and power-operated relief valves and piping, Auxiliary Feedwater System, main steam supply to the auxiliary feedwater pump turbine, and the letdown and charging portion of the CVCS System shall be inspected to determine if there has been a severe dynamic event.
In the case of a severe dynamic event, mechanical snubbers in that system which experienced the event shall be inspected during the refueling outage to assure that the mechanical snubbers have freedom of movement and are not frozen up.
The inspection shall consist of verifying freedom of-motion using one of the following:
(1) manually induced snubber movement; or (2) eval-uation of in place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.
If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced or repaired before returning to power.
The requirements of Specification 4.7.8b. are independent of the requirements of this specification, t.
Functional Tests During the first refueling shutdown and at least once per 18 months thereafter during shutdown, a representative sample of snubbers of each type shall be tested using one of the following sample plans.
The large-bore steam generator hydraulic snubbers shall be treated as CATAWBA - UNITS 1 & 2 3/4 7-20 Amendment No.88 (Unit 1)
Amendment No.82 (Unit 2)
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