Text

Amend 54 to License DPR-37,incorporating Steam Generator Inservice Insp Requirements & Reactor Coolant & Secondary Coolant Iodine Radioactivity Concentration Limits
	ML19296C002
Person / Time
Site:	Surry
Issue date:	12/20/1979
From:	Schwencer A; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19296C003	List: ML19296C002; ML19296C011; ML19296C016;
References
	NUDOCS 8002250040
	Download: ML19296C002 (25)
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UNITED STATES

[&7, e f'h NUCLEAR REGULATORY COMMISSION C

WASHINGTON D. C. 20555

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u V!R3If4IA ELECTRIC Af10 POWER CCMPA!1Y DOCKET fl0. 50-281 SURRYPOWERST'10fi,Uf1ITfl0.2 AMEri:MEf1T TO FACILITY OPERATIfiG LICEf4SE Amendment tio. 54 License fio. DPR-37 1.

The fiuclear Regulat:ry Commission (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, c:mplies with the standards and requirements of the Atoric Er.ergy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 3.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amend tent can be conducted without endangering the health and safe y of the public,~and (ii) that such activities will be conducted in compliance with the Commission'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.

Of' g 0022 50

2 2.

Accordingly, the license is amended by deleting paragraph E Steam Generator Insceccion and by changes to the Technical Specifications as incicated in the atcachment to the license amendment, and paragraph 3.8 of Facility Operating License fio.

OPR-37 is amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment tio.

54, are hereby incorpor,ated in the license.

P.e licensee shall operate the facility in accordance witn the Technical Specifications.

3.

This license a ;endment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSI0ft q[

WLWd'"

A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Attac hment:

Changes to the Technical Specifications Date of Issuance: Cec ember 20, 1979

ATTACJME'4T TO LICEftSE AMEf4DMErlT fl0. 54 FAC*LITY OPERATIftG LICEllSE fi0. OR-37 DOCKET fl0. 50-281 Replace the following ; ages 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 11 11 3.1 -13a 3.1-15 3.1-15 3.1 -15 a 3.1-17 3.1-17 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 4.1 9-11 4.19-12 Appendix A-1

Section Ti tl e Pa ge 3.15 Containment Vacuum System TS 3.15-1 3.16 Emergency Power System TS 3.16-1 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 3.19-1 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 4.0-1 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 4.5 Spray Systems Tests TS 4.5-1 4.6 Emergency Power Sfs 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 4.12 Ventilation Filter Tests TS 4.12-1 4.13 Norradiological Environmental Monitoring 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 Materials 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 4.19 Steam Generator Inservice Inspection TS 4.19-1 ii Amendment No. 54, Unit 2

+

TS 3.1-13a 6.

If the pri=ary-to-secondary leakage through all steas generators not isolated f rem the Reactor Coolant Systes exceeds 1 gpo total and 500 gallons per day thecugh any one steam generator not isolated f rem the Reactor Coolant System, reduce the leakage rate to within limits withia 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 hcurs and in cold shutdown within the following 30 hcurs.

Amendment No. 54, Unit 2

15 3.1-15

a le

1..a.,

P nliat ion r.mtiturs which ind ica te p r L::. t r y sy'; t c.1 letkam in-e i v'

-'- c o r.t.' I t u n t a ir p.irt icu la t..in] :;ra noultorn, the conde.';er air 2 3 e e r. o r

nitur, the c a.a p u r,e a t cooling vat.n nonitor, anJ the team generator

'2 lu<.A.en ns a1 :; r.

P e t e r u ~. :n,

F3.u, Sec tion 4. 2. 7 - Ce.icto r Coolant Systen Leakay,e FSAR, Cection 14.3.2 - Rupture of a Itain Steam Pipe D.

fiaximua Peactor Coolant Activity S ercif inat ienu i

1.

The total specific activity of the reactor coolant due to nuclides with half-lives of more than 15 minutes shall not exceed 100/E Ci/cc when-l ever the reactor is critical or the average temperature is greater than 500 F, where E is the average sum of the beta and gamma energies, in Mev, per disintegration.

If this limit is not saticfied, the reactor shall be shut do. '.ed 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.

Should this limit be exceeded by 25%, the reactor shall be made sub-crit ical and ;oled to 500 F or less within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ef ter detection.

Amendment No. 54, Unit 2

TS 3.1-15a 2.

The specific activity of the reactor coolant shall be lhaited to < l.0 LCi/cc DDSE ECU1 VALE.';T I-131 waenever the reactor is critical or the avera;e temperature is graater than 500 F.

3.

The rcquirements of D-2 above cay be codified to allow the specific ac tivity of the reactor coolant >1.0 uCi/cc DOSE EQUIVALENT I-13L but less than 10.0 pCi/cc DOSE EQUIVALEST I-131, opecaeion.may. 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-With tha ceed la percent of the unit's total yearly operating time.

specific activity of the reactor coolant >1.0 pCi/cc DOSE EQU1 VALENT 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 pC1/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 pCL/cc DOSE 4.

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

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

Reactor power history starting 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, 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.

sample in which the limit was exceeded, d.

Eistory of degassing operaticns, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior

the f irst sampla in'which the limit was exceeded, and The time duration when the specific activity of the pricary e.

ccolant exceeded 1.0 pC1/cc DCSC EQUIVALENT I-131.

Amendment tio. 54, Unit 2

TS 3.1-17 bouncar; would be 0.30 Rea shole body and 0.28 Rea t hyro id.

Thus, these doses are tell beles the guidelines sug;;ested in 10CER100.

Fernitting reactor operation to continue for limited time periods with the reactor coolant's specific activity >1.0 pCi/cc but < 10.0 pCi/cc COSE EQUl-VALE:;T l-13L accomodates possible iodine spiking phenomenon which may occur following changes in thernal pouer.

Opecation within these limits must be restricted to no core than 10 percent of the unit's yearly operating time 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 dose at the site boundary following a postualted steam generator tube rupture.

The ba;is for the 500 F temperature 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.

Measurecent of E will be performed at least twice annually.

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

1.

E shall be the average (weighed in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for 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.

2.

A detereination of the beta and gam =a decay energy per disintegration cf each nuclide determined in (1) above by applying known decay energies and schemes.

3.

A cair_l:ti:n of EI by appropriate weighing of each nuclide's beta and gccra energy with its concentration as determined in (1) above.

Amendment No. 54, Unit 2

TS 3.1-17.t 4

D D S E l'.QU '.',.J.E'; E I-131 sitall be that concentration of I-131 (pCi/ce) '.shich a lone uo~'.d produce the uane thyroid dose as the quantity and isotopic ninture of i-1H, 1-132, I-133, 1-13 ' and I-135 actually present. The thyroid dose con-voraion factor; 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.

linitun Temperature for Criticality Specifications l

8

/cendment No. 54, Unit 2

TS 3.6-2 2.

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

3.

All main steam line code safety 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.

C.

The iodine - 131 activity in the secondary side of any steam generator, in an unisolated reactor coolant loop, shall not exceed 9 curies.

Al so the specific activity of the secondary coolant systes shall be < 0.10 pC1/cc DOSE EQUIVALENT I-131.

If the specific activity of the secondary coolant system exceeds 0.10 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 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 maintained above 60,000 gallons, sufficient replenish =ent water is available in the 300,000 gallon condensate storage tank, and replenishment of the protected con-densate storage tank is ev=cenced within two hours after the cessation o f protected condensate storage tank water consumption.

SASI3 A reactor which has been shutdown from power requires removal of core residual heat.

Chile reactor coolant tecperature or pressure is greater than 350 F or Amendment flo. 54, Unit 2

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

steam generator. At f ull power, with a steam generator 'sater volume of 47.6 M,

the specific iodine - 13l licit would be.lS uCi/ce; at zero power, uith a 3

steam generator water volune of 101 M, the specific iodine - 131 limit would be.039 pCi/cc The limitations on secondary systeo specific activity ensure that the resultant of f-site radiation dose will be limited to a small traction of 10CFR Part 100 limits tu the event of a steam line rupture.

References FSAR Section 4 Reactor Coolant System FSAR Section 9.3 Residual Heat Removal Systen FSAR Section 10.3.1 Main Steam System CS AR Sec tion 10. 3. 2 Auxiliary Steam System FS AR Section 10.3. 5 Auxiliary Feedwater Pumps FSAR Section 10.3.8 Vent and Drain Systems FSAR Section 14.3.2.5 Environmental Eff ects of a Steam Line Break Amendment No. 54, Unit 2

TS 4.1-10 TABLE 4.1-23 MINIMU'4 F?IQUENCIES FOR SAMPLI::C TESTS FSAR SECTION DESCRC? TION TEST FREQUENCY REFERENCE Monthly (5) 1.

Reactor Coolant Liquid Radio-chemical Sanples Analysis (1)

Gross Activity (2) 5 days / week (5) 9.1 Tritius Activity Weekly (5) 9,1

Chemistry (C1, 5 days / week 4

F & 02)

Boron Concentration Twice/ueek 9.1 E Determination Semiannually (3)

(5)

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

Radio-iodine Once/4 hours Analysis (including and (7) below I-131, I-133 & I-135) 2.

Refueling Water Storage Boron Concentration Weekly 6

Tank Water Sacple 3.

Boric Acid Tanks

Boron Concentration Twice/ week 9.1 4.

Boron Injection Tan _k Boron Concentration Twice/ week 6

5.

Chemical Additive NaOH Concentration Monthly 6

Tank 6.

Spent Fuel Pit

Boron Concentration Monthly 9.5

7. Secondary Coolant Fifteen minute de-Once/72 hours 10.3 gassed B and y acti-vity (4)

DOSE EQUIVALENT I-131 Monthly (4)

Semiannually (8)

S.

Stack Gas Iodine and

I-131 and particu-Weekly Particulate Sa=ples late radioactive re-leases 9.

Accurulator Baron Concentration Ebathly 6.2

See Specificatic 4.1.D U-)

radiochenical analysis will be cade to evaluate the following corrosion c.

products:

Cr-51, Fe-59, Mn-54, Co-53, and Co-60.

(2)

A gross beta-gn=2 degassed activity analysis shall consist of the quanti-tative censure:ent of the teal radioactivity of the primary coolant in units of uCi/ce.

Amendment flo. 54, Unit 2

E

.e TS 4.l-10a (3) E detertiaatica will be started whea the gross ganea desassed activity of radionuclides with half-lives greater than 15 ainutes analysin in-dicates 2.10LCi/cc. Routine sample (s) for 5 analyses shall only be taken af ter a nini=ua 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.

(0)

If the fif teen minute degassed beta and gn--,

activity is 10% or more of the 9 Curie limit given in Specification 3.6.C, a DOSE EQUIVALENT I-131 analy-sis will be pertacted.

(5)

When reactor is critical and average primary coolant temperature >350 F.

(0)

Uhenever the specific activity exceeds 1.0 pC1/cc DOSE EQUIVALENT I-131 or 100/E pC1/cc and until the specific activity of the reactor coolant system is restored within its limits.

(7)

One sc=ple between 2 6 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a ther=al power change exceeding 15 perceat of the rated ther=al power within a one hour period provided tha cverage pri:ary coolant tecperature 2,350 F.

(S)

'.; hen the fifteen minute degassed beta and gn--n activity is less than 10%

of the 9 Curie li=it given in Specification 3.6.C.

Amendment No. 54, Unit 2

TS 4.19-1 6.19 3 TEAM CE:tERATOR I:iSERVICE I:ISPECTIC:1 Acolicability Applies to the periodic inservice ir.spection of the stean generators.

Objective To provide assurance of the continued integrity of the steam generator pressure boundaries.

Specifications I

A.

Each steam generator shall be demonstrated cperable pursuant to Specification 3.1.A.2 by perfor=ance of the following aug=ented ins e rvice inspection program and the requirement of Specifi:ation 4.2.A.

3.

Steam Generator Sa= ole Selection and Insoection - Each steam generator shall be determined operable during shutdewn by selecting and inspection at least the minimum number of steam generators specified in Table 4.19-1.

C.

Ste2 Generator Tube Saeole Selection and Insoection - The steam gener2ter tube sinimum sample size, inspection result c; ass ificatica, and tne corresponding action required shall be as specif ad in Amendment No. 54, Unit 2

TS 4.19-2 Table i.19-2.

The inservice inspection of steam generator tubes shall be performed at the f requencies specified in Specification i.19.D and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.19.E.

The tubes selected for each inservice inspection shall include at le as t 3" of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:

a.

Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be frem these critical areas.

b.

The first sample of tubes selected tor each inservice inspection (subsequent to the preservice inspection) of ea a steam generator shall include:

1.

All nonplugged tubes that previously had detectable wall penetrations > 20%.

2.

Tubes in those a eas where experience has indicated potential problems.

3.

. tube inspect t,n (pursuant ta Specifi:stion 1.17.I.a.S) m shall be perforr.ed on each selected tube.

If any selected tube dces not permit the passage of the eddy current probe for a tube inspectica, this shall be recceded and an Amendment No. 54, Unit 2

TS 4.19-3 adjacent tube shall be selected and subjected to a tuba inspection.

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

by Table 4.19-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1.

The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2.

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

The results of each sample inspection shall be classified into one of the following three categories:

Categorv Inscection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and ncne of the inspected tubes are defective.

C-2 One ;r core tubes, but not ore th an 10 of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.

Amendrnent flo. 54, Unit 2

TS 4.19-6 C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are def ect ive.

Note:

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

D.

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

a.

The first inservice inspection shall be perfor=ed af ter 6 Ef fective Full Power Months but within 24 calendar months e

of initial criticality.

Subsequent inservice inspections shall be perfor=ed at intervals of not less than 12 nor

= ore than 24 calendar conths after the previous inspection.

If two consecutive inspections following service under AVT conditions, not including the preserrice inspection, result in all inspection results falling ir.co the C-1 category or if two consecutive inspections deconstrate that previously observed degradation has not continued and no additional dagradation has occurred, the inspection interval cay be m: ended :o a naxi=us of once per ' O onths.

Amendment No. 54, Unit 2

TS 4.19-5 5.

If the results of the inservice inspection of a steca generator conducted in accordance with Table 4.19-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increas-ed to at least once per 20 conths. The increase in inspec tion frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.19.D.a; the interval =ay then be extended to a maxi =um of once per 40 =onths.

Additional, unscheduled inservice inspections shall be perfor:ed c.

on each steam generator in accordance with the first sample inspection specified in Table 4.19-2 during the shutdown subsequent to any of the following conditions:

1.

Primary-to-seccudary tube leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.1.C.6.

2.

A seismic occurrence greater than the Operating Basis Earthquake.

3.

A loss-of-coolant accident requiring actuation of the engineered safeguards.

A major main steam line or feedwater line break.

Amendment No. 54, Unit 2

TS 4.19-6 E.

Acceptance Criteria a.

As used in this Specification:

1.

Imoerfection =eans an exception to the di= ens ions, finish or conteur of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, =ay be considered as i=perfec-tions.

2.

Degradation means a se rvice-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.

3.

Degraded Tube means a tube containing imperfections

>20% of the nominal wall thickness caused be degradation.

A.

Degradation means the percentage of the tube wall thickness affected or recoved by degradation.

5.

Defect means an i= perfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.

Amendment No. 54, Unit 2

TS 4.19-7 6.

Pluzainz Limit ceans the imperfection depth at or beyond which the tube shall be recoved from service because it may become unserviceable prior to the next inspection and is equal to 40~ of the nominal tube wall thickness.

7.

Unserviceable describes the c7ndition of a tube if it leaks or contains a defect large enough to af fect is structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.19.D.c, above.

8.

Tube. Inspection meane an inspection of the steam generator tube frem the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

9.

Preservice Inspecticn ceans an inspection of the full length of each tube in each steam generator perfor=ed by eddy current techniques prior ta service to establish a baseline condition of the tubing. This inspection shall be performed using the equipment and techniques expect.ed to be used during subsequent ins eriice inspections.

b.

Tr. e steam generator shall be determined operable after er:pleting the correspcnding acticas (plug all tuces exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.19-2.

Amendment No. 54, Unit 2

TS 4.19-8 F.

Reports Collowing each inservice inspection of steam generator tubes, a.

the number of tubes plugged in each steam generator shall be reported to the Ccemission within 15 days.

b.

The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which the inspection was completed. This report shall include:

1.

Number and exter.t of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an i= perfection.

3.

Identification of tubes plugged.

Results of steam generatar tube inspections which fall c.

into Category C-3 and require pec=pt notification of the Cc==iss ion shall be repor:ed pursuant to Specificatin 6.6 prior to resumption of plan: cperation. The vri::en followup

f :his repor: snail previae a description of investigaticns c:nducted to determine :ause of the tube degradati:n and

cerec:ive ceasures taken :o prevent re cu rre nce.

Amendment No. 54, Unit 2

TS 4,19-9 3 ASIS The surveillance require =ents for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be caintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.

Inservice inspection cf steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damsge or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.

Inservice inspection of steam generator tubing also provides a =eans of characterizir_g the nature and cause of any tube degradation so that corrective ceasures i

can be taken.

Tb ? unit is expected to De operated in a canner such that the secondary coolant will be maintained within those parameter limits found to result in negligible corrosion of the steam generator tubes.If :he secondary coolant che=istry is not maintained within

hese para =eter limits, lccalized corrosion may likely result in stress corresion cracking. The extent of cracking during plant opera: ion would be limited by the.i=itatin of steam generator tube le2:<a ge ' e :ve en :he pri=a ry coolant system and the secondary colan:

sys:em (pri=ary-to-secondary leakage of 500 gallons per day per steam gene rat or ). Cracks having a primary-to-secondary leakage less than this lici: during operatin vill have an adequate =argin of safety to Amendment flo. 54, Unit 2

TS 4.19-10 withstand the laads i= posed during normal operation and by postulated accidents. Operating plant have de=onstrated that primary-to-secondary leakage of 500 gallons per day per ste as generator can readily be detected by radiation =onitors of steam generator blowdown. Leakage in excess of this linit will require plant shutdcwn and an unscheduled inspection, during which the Icaking tubes will be located and plugged.

Wastage-type defects are unlikely with the all volatile treatment

( AVT) of secondary coolant. However, even if a defect of similar type should develop in service, it will be found during scheduled inservice steam ganeraror tube examinations.

Plugging will be required of all tubes with imperfections exceeding the plugging limit which, by tne definition of Specification 4.19.E.a is 40% of the tube nominal wall chickness.

Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.

Whenever the results of any steam generater tubing inservice inspectien f all into Category C-3, these results will be premptly reported to the Cc==ission pursuant to Specification 6.6 prior to re sumptian of plant operatien.

Such cases will be considered by the Cceniss;:n :n a c ase-by-case bas is and may result in a requirement f:r ana'. sts, laboratorv examinaticas, tests, additional eddy-current in s pe c t i:n, and revision of the Technical Spacificaticas, if necessary.

Amendment flo. 54, Unit 2

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3L D

TAllLE 4.19-2 STEAM GEllEllATOR TilliE IrlSPECTION lut S AtlPI.l: l ilS PI' GT I O!!

2nd SAlfPLE INSPECTIOtt 3rd SAMPLE I t1S Pl:CT IOli Siunp l e Size it. su l t Act ion Required 1(es u l t Action Required Result Action R3 niaed A minimum of C-I tloue N/A li/A ll/A 11/A S Tubes pe S.G.

C-2 Plug ile fect ive tubes C-1 None N/A fl/A and inspect adili t i ona l C-2 Plug defective tubes C-1 tione 23 tubes in this S.G.

and inspect additional C-2 Plug defective tubes 4S tubes in this S.G.

C-3 Periorm act ion for C-3 result of first sample C-3 Perrorm act ion for ti/A N/A C-3 result of first aample C1 Inspect alI tubes in Al1 other None N/A t1/A this S.C.,

plug de fec-S.G.s are tive tubes and inspect C-1 2S tubes in each other S.G.

Some S.C s Perform act ion for fl/A N/A C-2 but no C-2 result of second Prompt not. i f ica t ion additional sample

,y t o NitC pursuant to S.G. are g

specificatin 6.6.

C-3 a

Additional Inspect all tubes cos S.G.

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

plug defective tubes.

O Prompt notification N/A N/A d

to NRC pursuant to e

speci ficat ion 6.6.

r m _.

e a

w O

f4

'9 = 3 H.

!?h e t e !! is the number of steam generators in the unit, and n is the number of steam generators inspected 7

u during an inspection

ML19296C002

Text

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