Text

Amend 65 to License DPR-32,incorporating Steam Generator Inservice Insp Requirements & Reactor & Secondary Coolant Iodine Radioactivity Concentrations Into Tech Specs & Deleting Previous Conditions
	ML19341C825
Person / Time
Site:	Surry
Issue date:	02/10/1981
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
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ML19341C826	List: ML19341C825; ML19341C831;
References
	NUDOCS 8103040243
	Download: ML19341C825 (25)
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g NUCLEAR REGULATORY COMMISSION wAsmoron. o. c. nosss VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO.1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-32 J

1.

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

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated December 30, 1976 as supplemented May 24, 1979, Act of 1954, as amended (the Act) quirements of the Atomic Energy complies with the standards and re and the Commission'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 regulati.ons of the J

Commission; 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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by deleting paragraph E Steam Generator Inspection and by changes.to the Technical Specifications as indicated in the attachment to the license amendment, and paragraph 3.8 of Facility Operating License No. DPR-32 is amended to read as i

follows:

I 8 1 0 3 0.4 0 M l

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B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, are hereby incorporated in the license. The itcensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

F5F THE NU L EGULATORY COMMISSION L

Va'rga 5

Operating Reactor ranch #1 Division of Licensing

Attachment:

Changes to the

+

Technical Specifications Date of Issuance:

February 10, 1981 I

ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-32 DOCKET NO. 50-280 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Insert 1

11 11 3.1 -13a 3.1-15 3.1-15 3.1-15a 3.1-17 3.1-17 i

3.1-17a 3.6-2 3.6-2 3.6-5 3.6-5 4.1-10 4.1-10 4.1-10a 4.19-1 4.19-2 4.19-3 4.19-4 4.19-5 4.19-6 4.19-7 4.19-8 4.19-9 4.19-10 4.19-11 4.19-12 Appendix A-1 i

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Section Title Pa ge i

3.15 Containment Vacuum System TS 3.15-1 3.16 Emergency Power System TS 3.15-1 3.17 Loop Stop Valve Operation TS 3.17-1 3.18 Movable Incore Instrumentation TS 3.18-1 3.19 Main Control Room Ventilation System TS 3.154 3.20 Shock Suppressors (Snubbers)

TS 3.20-1 3.21 Fire Detection and Suppression System TS 3.21-1 4.0-SURVEILLANCE REQUIREMENTS TS 4.0-3 4.1 Operational Safety Review TS 4.1-1 4.2 Reactor Coolant System Component Tests TS 4.2-1

~ 4.3 Reactor Coolant System Integrity Testing Following Opening TS 4.3-1 4.4 Containment Tests TS 4.4-1

.l 4.5 Spray Systems Tests TS 4.5-1 4.6 Emergency Power Sys tem Periodic Testing TS 4.6-1 4.7 Auxiliary Feedwater System TS 4.8-1 4.9 Effluent Sampling and Radiation Monitoring System TS 4.9-1 4.10 Safety Injection System Tests TS 4.11-1 1

4.12 Ventilation Fiiter Tests TS 4.12-1 4.13 Nonradiological Environmental Monitoring i

Program TS 4.13-1 4.15 Augmented Inservice Inspection Program for High Energy Lines Outside of Containment TS 4.15-1 4.16 Leakage Testing of Miscellaneous Radioactive Material s TS 4.16-1 4.17 Shock Suppressors (Snubbers)

TS 4.17-1 4.18 Fire Detection and Protection System Surveillance TS 4.18-1 1

4.19 Steam Generator Inservice Inspection TS 4.19-1 l

l ii Amendment No. 65

TS 3.1-13n

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6.

If the primary-to-secondary leakage through all steam genera: ors not isolated from the Reactor Coolant System exceeds 1 gpm total and 500 gallons per day through any one s:cac generator not isolated from the Reactor Coolant System, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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Amendment No. 65

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TS 3-1-15 4

systen leak 2e.

Radiation monitors /_f.ch indicate primary system leakage in-n.

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clude the contain=ent air particulatt and gas monitors, the condenser air ejector conitor, the conponest cooli:s ve:er monitor, and the steam generator blowde a r caitor.

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References a

FSA?., Section 4.2.7 - Reactor Coolan: Sys:em Leakage ISAF., Section 14.3.2 - Rupture of a Esf.n 5:ea= Pipe D.

Maxi =um Reactor r

. ant Activit-5:ecifications 1.

Tne total specific activity of the reactor coolant due to nuclides.iith half-lives of more than 15 1.nt:es shall not exceed 100/f pC1/cc when-l ever the reactor is critical or the crerage te=perature is greater than 500 F, where E is the average su: of the betc and gan:=a energies, i.t Mev, per disintegration.

If this lizi: is not satisfied, the reactor shall be shut dava -> cooled to SCO ? cr ~ess within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after detection.

oShould this 14-4 t be ex:eeded by 251, the reactor shall be cade sub-critical and cooled to 500 F er less eithin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after detection.

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.S to TS 3.1-15a The specific activity of the reactor coolant shall be Ifmited to < 1.0 2.

pCi/cc DOSE EQUIVid,ENT I-131 whenever the reactor is critical or the

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average temperature is greater then 500 F.

The requirements of D-2 above =ay be codified to allow the specific activity 3.

of the reactor coolent >1.0 pCi/cc DOSE EQUIVALENT I-131 but less than.

i.

10.0 pCi/cc DOSE EQUIVALENT I-131, opwae-ion. cay.. continue for up to, 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided that operation under these circumstances shall not,ex,.

1 With the ceed 10 percent of the unit's total yearly operating time.

specific acti rity of the reactor coolant >1.0 pCi/cc DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous ti=e interval or exceeding 10.0 pCi/cc DOSE EQUIVALENT I-131, the reactor shall be shut down and cooled to 500 F or less within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months af ter detection.

If the specific activity of the reactor coolant exceeds 1.0 pCi/cc DOSE 4.

EQUIVALENI I-131 or 100/E u/C1/ce, a report shall be prepared and submitted l

to the Cv ission pursuant to Specification 6.6.2.b(2). This reporr shall contain the results of the specific activity analysis together with the following infor=ation:

1 Reactor povar history starti=; 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample a.

in which the limit was exceeded, t

b.

Fuel burnup by core region, Clean-up flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first c.

a sa=ple in which the limit was exceeded, Eis:ory of degassing operations, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior d.

to the first sa=ple in'which the lic: t was exceeded, and The time duration when the specific activity of the primary s

e.

coolant exceeded 1.0 vCi/cc DOSE EQUIVALENT I-131.

TS 3.1-1/

Thus, these d:ses boundary would be 0.30 Rem whole. body, a.d 0.28 Rem thyroid.

u are well below the guidelines suggested.in 100FR100.

Permitting reactor operation to continue for limited eine periods with the reactor coolant's specific activity >1.0 pCi/cc but < 10.0 pCi/cc DOSI IQ I VALENT I-131 accomodates possible iodine spihing phenomenon which may cccur I

following changes in thernal power.

Operation within these limits must be t

res'tricted to no more than 10 percent of the unit's yearly operating time i

since the activity levels allowed cay slightly increase the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thyroid dese at the site boundary following a postualted steam generator tube rupture.

The basis for the 500 F tecperature contained in the Specification is that the saturation pressure corresponding to 500 F, 680.8 psia, is well below the pressure at which the atmospheric relief valves on the secondary side could be actuated.

Measurement of E will be performed at least twice annually.

Calculations re-quired to determine 5 will consist of the following:

E shall be the average (weighed in proportion to the concentration 1.

of each radionuclide in the reactor coolant at the time of sampling) of the average beta and gacca energies per disintegration of the sum (in MeV) f or isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

A determination of the beta an/. ga=ca decay energy per disintegration

2. e of each nuclide determined in (1) above by applying known decay energies and schemes.

A calculation of E by approp-iate weighing of. each nuclide's beta 3.

and ga ::a energy with its concentration as determined in (1) above.

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TS 3.1-17a

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.a DOSE IQUIV/J.ENT I-131 shall be that ec..;e:tratien of I-131 (pCi/cc) which alone

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would produce the same thyroid dose as the quantity and isotopic ab:ture of I-

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131, I-132, I-133, I-134 and I-135 actually present.

The thyroid dose con-version factors used for this calculation shall be those listed in Table III of TID-14S44, " Calculation of Distance Factors for Power and Test Reactor Sites".

E.

. Minimum Temperature for Criticalirv Specifications o

Amendment No. 65 2

TS 3c6-2

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2.

A minimum of 96,000 gal of water shall be available in the tornado missle protected condensate storage tank to supply e=ergency water to the auxiliary feedwater pump suctions.

3.

All main stern line code saf ety valves, associated with steam gen-erators in unisolated reactor coolant loops, shall be operable.-

4.

System piping and valves required for the operation of the components enumerated in Specification B.1, '2, and 3 shall be operable.

The iodine - 131 activity in the secondary side of any steam generator, C.

in an unisolat'ed reactor coolant loop, shall not exceed 9 curies.

Also the specific activity of the secondary csolant system shall be < 0.10 pCi/cc DOSE EQUIVALENT I-131.

If the specific cetivity of the secondary coolant system exceeds 0.10 pCi/cc DOSE IQUIVALENT I-131, the reactor shall be shut down and cooled to 500 F or less within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after detection and in the Cold Shutdown Condition within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

D.

The requirements of Specification B-2 above may be modified to, allow utilization of protected condensate storage tank water with the auxiliary steam generator feed pumps provided the water level is caintained above 60,000 gallons, sufficient replenishomat water is available in the 300,000 Fallon condensate storage tank, and replenishment of the protected con-a densate storage tank is co=menced within two hours af ter the cessation of protected condensate storage tank water consumption.

EA5:5 A rcac:or which has been shutdown froc power requires removal of core residu'al heat.

iihile reactor coolant te=perature-or pressure is greater than 350 F or Amendment No. 65

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, TS 3.6-5 The steam generator's specific iodine - 131 activity limit is calculated by dividing the total activity limit of 9 curies by the water volume of a 3

steam generator.

At full power, with a steam generator water volume of 47.611, the specific icdine - 131 licit would be.18 pCi/ce; at zero power, with a 3

steam generator water volume of 101 M, the specific iodine - 131 limit would be.089 pCi/cc b

1 The li=itations on secondary system specific activity ensure that the ' resultant off-site radiation dose will be limited to a small fraction of 10CFR Part 100 li=its in the event of a steam line rupture.

References TSAR Section 4 Reactor Coolant System TSAR Section 9.3 Residual Eeat Re= oval Systen FSAR Section 10.3.1 Main Stean Syste=

FSA?.Section 10.3.2 Auxilia: y Steam System FS;J.Section 10.3.5 Auxiliary 7eedvater Pumps FSAR Section 10.3.8 Vent and Drais Syste=s FEA?.Section 14.3.2.5 Environ = ental Eff ects of a steam Line' Break e

Amendment No'. 65

TAE _E 4.1-23 TS 4.1-10 MINIhTM FP2QUENCIES FO?. SAMPLI':G TE'STS s

FSA?.

SE::T:0N DISCRIPTION TEST FREQUENCY FIF7.nn;CE 1.

Reactor Coolant Liquid Radio-chanical Monthly (5)

Sanples Analysis (1)

Gross Activity (2) t 5 days / week (5) 9. l' Tritium Activity Weekly (5)

,9,1,

Chemis:ry (C1, 5 days / week.

4 F & 02)

Boron Concentration Twice/ week 9.1 E Deter nir.ation Se:tiannually(3)

(5)

DOSE EQUIVALENT I-131 Once/2 weeks (6)

Radio-iodine Once/4 hours Analysis (including aind (7) below I-131,

-133 & I-135) 2.

Refueling Water Storage Boron Concentranion Weekly 6

Tank Water Sample 3.

Beric Acid "'anks

Boron Concentration Twice/ week 9.1 4.

Boron Injection Tank Boron Concentration Twice/ week 6

5.

Chemical Additive NaOH Co. centration Monthly 6

Tank 6.

Spent Fuel Pit

Boron Concentration Monthly 9.5

7. Secondary Coolant Fif teen =inute de-Once/72 hours 10.3 gassed 3 and y acti-vity (4)

DOSE EQUIVALENT I-131 Mouthly (4)

Semiannually (8) 8.

Stack Gas Iodine and

I-131 and particu-Weekly Particulate Samples late radioactive re-leases 9.

1:cu=ulator Boron Concentration Monthly 6.2

See Specification 4.1.D (1)

A radiocher.ical analysis will be ade to evaluite the following -corrcsion products:

Cr-51, Fe-59, Mn-54, co-58, and co-60.

(2)

A gross beta-gn==a degassed activity analysis shall consist of the quanti-i tative measurecent of the coal radioactivity of the primary coolant in units of pCi/cc.

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Amendment No. 65

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'AS 4.1-103 1

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E determination will be started when the gross gamma degassed activity n

of radionuclides with half-lives greater than 15 uinutes analysis in-c dicates > 10pci/cc.

Routine sample (s) for E analyses shall only be taken after a minimum of 2 EFPD and 20 days of power operation have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer. -

1 (4)

If the fif teen minute degassed beta and ga==a activity is 10% or more of the 9 Curie limit given in Specification 3.6.C, a D35E EQUIVALENT I-131 analy-sis will be perf ormed.

4 (5) 1 hen reactor is critical and average prir.ary coolant temperature >350 F.

0 1

(0) k~nenever the specific activity exceeds 1.0 pCi/cc DOSE EQUIVALENT I-131 or 100/E uCi/cc and until the specific activity of the reactor coolant system is restored within its li=its.

(7)

One sample between 2 & 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a ther=al power change exceeding 15 percent of the rated ther=al power within a one hour period provided.

the average pr4 ry coolant temperature >350 F.

(0) traen the fifteen minute degassed beta and gac=a activity is less than 10%

e of the 9 Curie limit given in Specification 3.6.C.

d Amendment No. 65

TS 4.19

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l' 4.19 STEAM GENERATOR INSERVICE INS?ECTION fh9 9 0

o Jw ad A

o Aoplicability Applies to the periodic inservice inspection of the steam generators.

Objective To provide as surance of the centinued integrity of the steam generate; pressure boundaries.

Specifications A.

Each steam generator shall be demonstrated op3rable pursuant to Specification 3.1.'A.2 by performance of the following augmented inservice inspection prog a= and the requirement of Specificatien 4.2.A.

B.

Steam Generator Sample Selection and Inspection - Each stea=

l generator shall be deter =ined operable during shutdown by selecting and inspection at least the sinimum number of steam generaters specified in Table 4.19-1.

C.

Steae Generater Tube Sa=r' e 5electi:n and Insoection - The s te a:

generzter tube minimum sm:ple si:e, inspection result clas s ification, and the corresponding actiec required shall be as specified in Amendment No.65

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i Table 4.19-2.

The inservi:e inspection of stets ge=erator tubes 1

shall be performed at the frequencies specified i: Specifica ic:

4.19.D and the inspected tubes shall be verified a:ceptable per the acceptance criteria of Specification 4.19.E.

The tub,es selected for each inservice inspection shall include at least 3 of,the total number of tubes in all steam generators; the tubes selected for these inspec: ions shall be selected on a rendem basis excep::

Where experience in si=ilar plan:s with si=ilar water chemistry a.

indicates critical are as to be inspected, the: at least 502 of the tubes inspected shall be fren these criti:a1 areas.

b.

The first sample of :ubes selected for each i: service inspe= tion (subsequent :o the preservice inspection) c f each steam ge:erator shall include:

1.

All nonplugged :ubes that previously had detectable vall penetrations > 20%.

2.

Tubes in those areas where experience has indicated potential problems.

a 3.

i. :ube inspecti:n ' pursuant :o Specifi: s:i:n 1.19.I.a.!:

shall be perforced cc each selee:ed ::b e.

If any sele::ed cube does not perti:~ :he passage of :he eddy curren p ::e for a tube inspection, this shall be re:::ded and an Amendment No. 65

h TS 4'l9-3 10 0'

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adjacent tube shall be selected and subjected to a tube l

l inspection.

t The tubes selected as the second and third samples (if required c.

i by Table 4.19-2) during each inservice inspection may be.

subjected to a partial tube inspection provided:

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1.

The tubes selected for these so=ples include the tubes from l

those areas of the tube sheet array where cubes with leperfections were previously found.

2.

The inspections include those portions of the tubes where imperfections were previously fcund.

T'.- e results of each sample inspection shall be classified into one of the fellowing three categories:

Categorv Inspe: tion Results C-1 Less. than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

4 C-2 One er nore tubes, but not more than 1%

of the' total tubes inspected are def ective, or between 5 and lo: of the total tubes inspected are degraded tubes.

Arendment No. 65

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C-3 More than 10% of the total tubes inspected are degraded tubes or note than 1% of the inspected tubes are defective.

Note:

In all inspections, previously degraded tubes.must emhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.

D.

Inspection Trecuencies - The above inservice inspections of steam generator tubes shall be perfor=ed at the following frequencies:

a.

The first inservice inspection shall be performed af ter 6 Effective Tull Power Months but within 24 calendar months of initial criticality.

Sub s equent inservice inspectio:s shall be perfor=ed at intervals of not less than 12 nor more than 24 calendar months af:er the previous inspection.

If two consecutive inspections following service under FT conditions, not including the prese-vice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections de=enstrate that previously observed degradation has not continued and no additional degradaH.on has occurred, the inspection interval may be ex: ended to a maxinu= of once per !..} :onths.

Amendment No. 65

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If the results of the inservice inspecti:n af a stea= genera:n:

b.

conducted in accordance with Table 4.19 ~. at 40 = cath interva_s fall in Category C-3, the inspectica frequency shall be i=:ress -

ed to at least once per 20 months. The increase is i=spectic=

frequency shall apply until the subseque=t inspectiois satisfy the criteria of Specification 4.19.D.a; :he interval,=ay the:

be extended to a maximum of once per 40 =enths.

Additional, unscheduled inservice inspecticns shall be perfor=ed c.

on each steam generator in accordance vi h the first sample inspection specified in Table 4.19-2 d: ring the shutdo- :

subsequent to any of the fo11 cuing condiziens:

1.

Primary-to-secondary tube leaks (not including leds criginating f rem tube-to-tube shee: velds) in ex:ess cf :he limits of Specification 3.1.C.6.

2.

A seismic occurrence greater than the Cpera:ing 3 asis Earthquake.

3.

A loss-of-cociant accident requiring actuat'.o= cf the engineered safeguards.

4 A major main steam line or f eedwater lir.e bre d.

Amendment No. rs -

TS 4 19-c 0

E. ' Acceptance Criteria e

9 As used in this Specification:

a.

1.

_Immerfection means an exception to the dimensions,'

fi=ish cr conteur of a tube fre= that required by,

fabrication drawings or specifications. Eddy-curre=t testing indications below 20* of the noeinal tube wall thickness, if detectable, cay be considered as imperfec-tiens.

2.

Degrada: ion means a service-induced cracking, vastage, wear er genera *. corrosion occurring on either inside or outside of a tube.

3.

Derraded Tube eans a tube containing' i= perfections

>20% of the ne inal vall thickness caused be degradatio:.

4.

% Derradation = cans the percentage of the tube wall thickness afincted or removed by degradation.

e 5.

Defe:t =eans an imperfection of such severity that it ex:eeds the plug-ing limit.

A tube cen:aining a de f ect is defective.

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Amendrent No. 65 l

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6.

Plugging Limit ceans the imperfection depth at or beyond which the tube shall be removed from service because it may becoce unserviceable prior to the next inspection and is equal to 40% of the nominal, tube vall thickness.

7.

Deserviceable_ des:ribes the condition of a tube if It 13aks or contains a defect large enough to affect is structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant acciden:, or a steam line or.feedwater line break as specified in 4.19.D.c, above.

8.

Tube.Tasaectirn e ans an inspection of the steam generator tube fro: the peint of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

9.

Preservice Insnee:icn means an inspection of the full length of each tube ia each steam generator performed by eddy current te:hniques prior to service to establish a baseline condition of the tubing.

This inspection shall be performed using 'the equipment and techniques expected to be used during subsequent inservice inspections.

b.

The steam generator s..all be determined cperable af ter cc=pleting the corresp:nding actions (plug all tubes exceedi:g the plugging' limit and all tubes containing through-wall cracks) required by Taile 4.19-2.

Amendment No. 65

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IS 4.19-8 g

F.

Reports a.

Following each inservice inspection of stear. Issera:or tubes, the r. amber of tubes plugged in each steau geners:or shall be reported to the Coc:mistica within 15 days.

b.

The complete results of the steam generator tule inservice inspection'shall be repor:ed on an annual basis for the period in which the inspection was ce=pleted. This repor shall include:

1.

Number and extent of :ubes inspected.

2.

Location and percent of wall-thickness pece: ration for each indication of a: i=perfec:icn.

3.

Identification of cubes plugged.

c.

Results of stean generater tube inspections whi:b fall into Category C-3 and recuire prompt notiff.:ati:n of the Co==ission shall be repor:ed pursuan: to S;-ecificatin 6.6 prior to resumption of plant operatien.

The t.--it zer. f ollevup of this report shall previde a descriptien rf n.es:igations cenducted to determine cause of :he tube degrau: ice and I

corrective measures ta.ke: to prevent recurrenct.

Amendment No. 65

TS 4.19-9 D**0

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BASIS cc c

3 The surveillance requirements for inspection of the steam genera:::

tubes ensure that the structural integrity,of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.

Inservice inspection of' steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event tha: there is evidence of =echanical damage or progressive degradation due to design, manufae:uring errors, or inservice conditions that lead to corrosion.

Inservice inspectics of steam generator tubing also provides a means cf charac:eri:ing the nature and cause of any tube degradation so that corrective measures can be taken.

The unit is expt::ed to be operated in a nanner-such that the secondary coolant will be maintained within those parameter limits found to result in negligible corrosion of the steam generator tubes.If the secondary coolant che=istry is not maintained within these para =eter limits, localized corrosion may likely result in stress corrosion cracking.

The extent of cracking during plant operation vould be 1! sited by the limitatin of steam generator tube leakage be:veen,the primary coolant system any the secondary coo'. ant systen (pri=ary-to-secondary leakage of 500 gallons per day per s:c a:

gene rat or).

Cracks having a primary-to-secondary leakage less than this li=i: during opera:in vill have an adequa:e cargin of safe:7 :o Amendment No. 6'S' 7

TS 4.19-10 qq m

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.vithstand the loads imposed during normal operation and by postulated

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ac:idents. Operating plant have demonstrated that prima ry-t o-s e ccndary leakage of 500 gallons per day per ste n: generator can readily be detected by radiation monitors of steam generator blowdown. Leakage j

in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes vill be located and plugged.

W'astage-type defects are unlikely with the all volatile treat =ent (AVT) of secondary coolant. However, even if a defect of similar type should develop in service, it will be found during scheduled inservice steam g=nerator tube examinations.

Plugging will be required of all tubes with i=perf ections exceeding the plugging li=it which, by the definition of S pecificatien 4.19.E.a is 40% of the tube nominal wall thickness.

Ster = generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of ths neiginal tube wall thickness.

l Whenever the results of any steam generator tubing inservice inspection f all into Category C-3, these results will be promptly 5

reported to the Co==ission pursuant to Specification 6.6 prior to resu=ption of plant operatien.

Such cases will be considered by the Commissi:n on a case-by-case basis and =ay esult in a requirement for analysis, laboratory exa inaticns, tests, additienal eddy-current in spe ct ien, and revision of tne Technital Specifications, if necessary.

Amendment No. 65

I.

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TABl.E t.I9-1 IIINilflill HlfHilEli 0F STEAH CEllERATORS TO BE INSPECTED Dilit tlN: INSEltVICE INSPECTION No Yes Prenezvice i nnpert i sni Two Titree Two Three tio. of Steam Generalnru All One Two First innervice_Ig pection I

One2 I

. One Scrond & Snhneslnent innervice Inspectionn_

Onc Tahic Hntation:

1.

The innezvice innpcetion may he limited to one steam generator on a rotating schedule encompassing 3 N 2 of she inhen (where H in the number of nienm p,cncrntorn in tne plant) i f tlie results of the first or previous inspections inslicate that all steam generators are performing in a like manner. Note that under some-circumaannten, the operating con.litionn in one or more stenus generators may he found to bc enore severe than those in ot her etcare generators. Under auch circumstances the sample sequence shall be snodified to inspect the most nevere conditions.

2.

The ot her si cain generator not inspectcil during the first inservice inspection shall be inspected. The third and suh cquent inspections should follow the instructions described in I above.

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.ii TABLE 4.19-2 STEAM CENERATOR TURE INSPELTION I

I n t-SAHPI.E I NSI'ECTION 2nd SAMPl.E INSPECTION 3rd SAMPLE INSPECTION Ssmple Size Itenni t-~

Action !!cquired Result Action Required Result Action Required A minimum of C-1 None N/A N/A N/A N/A S Tubes per

!;.C.

C-2 Plug de feet ive tubes C-1 None N/A N/A

ind innptict additional C-2 Plug defective tubes C-1 None

?!i tuben in thin fl.C.

and inspect ndditional C-2 Plug defective tubes 4S tubco in this S.C.

C-3 Perform actinn for C-3 result of first sample I

9@

.:-1 r..ro..

a.M I nn for N/A N/A g.g C-3 result of fira:

nnmpic 5

Msa N/A C-3 Inspect all tubes in All other None this S.C., plug de fec-S.C.s are ive tubes and inspect C-1 Some S.C.s Perf orm act inn for N/A N/A CT7) 2S tubes in each other S.C.

C-2 but no C-2 result of second Prompt notification additional anmple 3

to NRC pursuant-to S.C. nre specificatin 6.6.

C-3 Additional Inspect all tubes g

S.C. is C-3 in each S.C. and a

plug defective tubes.

Prompt notification N/A N/A d

2 to NRC pnrauant to m

syecifIcution 6.6.

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w

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SJ 3.NZ Whr s c N i n t he nomher of steam generators in the unit, and n is the number of steam generators inspected

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doring nn in9pection Il

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ML19341C825

Text

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