ML20082U146

Amend 136 to License DPR-72,changing Surveillance Requirements of TS 4.4.5 to Permit Option of Using B&W Sleeving Process for SG Tube Repair

ML20082U146
Person / Time
Site:	Crystal River
Issue date:	09/11/1991
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20082U149	List: ML20082U146 ML20082U160
References
NUDOCS 9109200026
Download: ML20082U146 (13)

Text

--.

'. r asa w),

UNITE D ST ATES

[ $. // h NUCLE AR REGULATORY COMMISSION 4

WWHNGtON, D C 70abb yn, y FLOR 10A POWER CORPORAT10tl CITYl T AFACHilA i

CITV~0TE5TiWEEE CITY OF GAlWE5VTELE CITY OF KIS51TEEE~

CITY DFEEEKEW CITY OF NEW SliYRNA BEACH AND VTILITIT5 CMMT5S10N, CITY OF NEW SMYRNA BEACH CITY D ICCALA ORLAtlD0 UTILITIES EDMT55TOTFAND CITY OF ORLAtlDO SURlWB~UTTETTTE57DTIRTI5 TON SEMINDLE ELECTRTC70MERATTVE~ Illc.

CITY OF TAT.TAirA55EE DOCKET NO. 50-302 CRYSTAL RIVER tlHIT 3,NilCLEAR GENERATillG Pl.Alli AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.136 License No. DPR-72 i.

The Nuclear Regulatory Commission (the Commi:sion) has found that:

A.

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

(the licensees) dated April 6, 1990, as modified by letter dated

-May ?, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (+.he Act), and the Comission'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 regulations of the Commission; C.

There is reasonable assurance (i) that the activities authori. led by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in complianc.e 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 l

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

91092OOT6 91O?!1 PDR ADOCK 05000302 t

l P

PDR

I t

t 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i

and paragraph 2.C.(2) of fecility Operating License No. DPR-72 is hereby I

amended to read-as follows:

j Technical Specifications t

The Teu,nical Specifications contained in Appendices A and B, as i

revised through Amendment No.136, are hereby incorporated in the i

license.

Florida Power Corporation shall operate the facility in i

accordance with the Technicr1 Specifications.

3.

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

}

FOR THE NUCLEAR REGULATORY COMMISSION i

Of I

\\ J5

[l* &cb~

l Hf ert N. Berkow, Director Project Directorate 11 2 i

Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regblation

Attachment:

Changes to the Technical Specifications t

Date of issur.nce: September 11, 1991 l

t i

l r

i I

l I

l

{

l

j.

ATTACHMENT TO LICEllSE AfiEliDMENT NO.136 iAClllTY OPERATING LICENSE NO. DPR-72 i

DOCKET NO. 50-302 Replace the following pages of-the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain. vertical lines indicating the area of-change. The corresponding overleaf pages are also provided to maintain document completeness.

t Remove Insert 3/4 4-7 Tf4T7 3/4 4-8 3/4 4-8 3/4 4-9 3/4 4-9 l

3/4 4-10 3/4 4-10 3/4 4 3/4 4-12 3/4 4-124 3/4 4-12a B3/4-4-3 B3/4 4-3 l

i t

i h

t i

4

',+,n..

w wr -r-Y'

-w '-

w w v' -

er** e -w - -

'y wm.

m -w-m we v*r-w wws ewm

~ - se-me e-

-+-*=++ -

.-r

~_.___m-REACT 0_R CQqLMQ SYSTEM SVRVEILLMfCIE0VIREMENTS (Continued) b.

The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:

1.

All nonplugged tubes that previously had detectable wall j

penetrations (>20*.'), and i

2.

Tubes in those areas where experience has indicated potenti61 problems.

c.

The second and third inservice inspections may be less than a full tube inspection by concentrating (selecting at least 50". of the tubes

(

to be inspected) the inspection on those areas of the tube sheet l

array and on those portions of the tubes where tubes with imperfectioits were previously found.

i d.

Tubes in specific limited areas which are distinguished by untque i

operating conditions and/or physical construction may be excluded

[

from random samples if all-such tubes in the specific area of a steam t

generator are inspected with the inspection result classification and the corresponding action required as specified in Table 4.4 6.

No 3

credit will be taken for these tubes in meeting minimum sample size requirements.

Degraded or defective tubes found in'these areas will i

not be considered in determining the inspection results category as long as the mode of degradation is unique to that area and not rando, in nature.

The results of each sample inspection shall be classified into Me of the fcilowing three categories:

e Cateaory Insoection Resulti j

t C1 Less than 5% of the-total tubes inspected are i

degraded tubes and none of the inspected tubes are i

defective.

[

C2 One or more tubes, but-not more than 1% of the total tubes inspected are defective, or between 5% and 10*.

of the total tubes inspected are degraded tubes.

j C3 More than 10% of the total tubes inspected are

-i degraded tubes or more than 1% of the inspected tubes are defective.

Note:

In all inspections, previously hgraded tubes whose degradation has not been spanned y a sleeve must exhibit t

significant (>10%) further wall-penetrations to be included in j

the above percentage calculations.

i i

i CRYSTAL RIVER - UNIT-3 3/4 4 7 Amendment No. 33* 136, l 8

p

._,_____a,__.,._.-

REACTOR COOLANT SYSTEB M YIILLANCE RE0VIRQiENTS (Cont.ingedi 4.4.5.3 Insoection Frecugnlin The above required inservice inspections of steam generator tubes shall oe performed at the following frequencies:

a.

The first inservice inspection shall be performed after 6 Cffect he Full Power Months. but within 24 calendar months of initial criticality.

Subsequent inservice inspections stiall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection, if two consecutive inspections following service under all volatile treatment (AVT) conditions, not including the preservice inspection, result in all inspection results falling into the C 1 category, or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months, b.

If the inservice inspection of a steam generator, conducted in accordance with Table 4.4 2 and/or Table 4.4 6 requires a third sample inspection whose results fall in Category C 3, the inspection frequency shall be reduced to at least once per 20 mon as.

The reduction in inspection frequency shall appl,' until a subsequent inspection demonstrates that a third sample inspection is not required.

c.

Additional unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4 2 and/or Table 4.4 6 during the shutdown subsequent to any of the following conditions:

1.

Primary to secondary tube leaks (not including leaks originating from tube to tube sheet welds) in excess of the limits of Specifiestion 3.4.6.2, 2.

A seismic occurrence greater than the Operating Basis Earthquake, f

3.

A loss of coolant accident requiring actuation of the engineered safeguards, or 1

4.

A main steam line or feedwater line break.

4.4.5.4 Acceptance Criteria a.

As used in this Specification:

1.

Tubina or Tubt mean> ui;t nortion of the tube or sleeve which forms the primary system to se:9ndary system pressure boundary.

2.

1moerfection means an exception to the dimensions, finish or I

contour of a tube frcn that required by fabrication drawings CRYSTAL RIVER UNIT 3 3/4 4 8 Amendment No. 33,136c

i REACIOR COOLANT SYSTEM SURVEILLANCE REQUIREMENUEgntinuedl or specifications.

Eddy current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.

3.

EtattA4. tion means a service induced cracking, wastage, waar, or l

general corrosion occurring on either inside or outside of a tube.

4.

Dearaded Tuhg means a tube containing imperfections 2 20% of the nomins) wall thickness caused by degradation except where all such degradation has been spanned by the installation of a sleeve.

5.

% Dearadation means the parcentage of the tube wall thickness l

affected or removed by degradation.

6.

Defect means an imperfection of such severity that it exceeds the plugging / sleeving limit except where the imperfection has been spanned by the installation of a sleeve. A tube containing a defect in its pressure bounda v it defective. Any tube which does not permit the passage i the eddy current inspection probe 6

shall be deemed a defective tube.

7.

Pluaaina/51cevina limit means the imperfection depth at or beyond which the tube shall be restored to serviceability by the installation of a sleeve or removed from service because it may

-become unserviceable prior to the next inspection and is equal to 40% of the nominal tube or sleeve wall thickness. No more than j

five thousand sleeves may be installed in each steam generator.

8.

Unserviceablg describes the condition of a tube if it leaks or l :

contains a defect large unough to affect its 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 4.4.5.3.c, above.

9.

Tube Inspection means an inspection of the entire steam generator I

-tube as far as possible, b._

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or sleeve all tubes exceeding the plugging / sleeving limit and all tubes containing through wall cracks) required by Table 4.4-2 (and Table 4.4-6, if the provisions of Specification 4.4.5.2.d are utilized).--Defective tubes-may be rcpaired in accordance with the B&W process (or method) equivalent to the method described in report BAW 2120P.

4.4.5.5 Reports a.

Following each inservice inspection-of steam generator tubes, the number of tubes plugged and tubes sleeved in each steam generator shall-be reported to the Commission within 15 days.

CRYSTAL RIVER - UNIT 3 3/44-9 Amendment No. 77,n,136, t

~..

i REACTOR COOLANT SYSTEM-SURVElLLANCE REQUIREMENTS (Continued) i b.

The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the 4

inspection.

This Special Report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall thickness penetration for each

. indication of an imperfection.

3.

Tdentification of tubes plugged and tubes sleeved.

Results of steam generator tube inspections which fall into Category c.

C 3 shall be. reported to the Commission pursuant to 10 CFR 50.72 prior to resumption of plant operation.

The written followup of this report shall provide-a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence pursuant to 10 CFR 50.73.

4.4.5.6 The-steam generator shall be demonstrated OPERABLE by verifying steam generator level-to be within limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l I

f 1

l CRYSTAL'RIVERL-UNIT 3~

3/4 4-10 Amendment No. 33.pp,136 -

TABLE 4.4-1 HINIMUM NUMBER OF STEAM GENERATORS TO BE

((

INSPECTED DURING INSERVICE INSPECTION

' 0!9 C

E

-4 Preservice Inspection yes No. of Steam Ger.erators per Unit Two first Inservice Inspection One w);

7 5'econd & Subsequent Inservice Inspections One Table Nota tion :

k 1.

The inservice inspection may be limited to one steam generator on a g

rotating schedsle encompassing 6% of the tubes if the reselts of the g

first or previous inspections indicate that both stean generators are g

performing in a like manner. Note that under some circumstances, the operating conditions in one steam generator may be found to be more severe than those in the other steam generator. Under such circumstances o

~

the sample sequence shall be modified to inspect the most severe y(

conditions.

I m

l

-c$

l D

l r-l-

n l

5 l

=

IAbtI 4 4 2 1

e

$1 LAM GlNERAlOR IUB1 IMSPICllON r

f n

1 A

151 SAMPtE II 5PtCll0N 2ND $AMPti INSP(CIION 3RD ',AM?ti 1N511(IlON i

Sample Size Result Action Required Result A(tion Required Result A(tson kcquired N/A N/A N/A M/A a minimum C-1 leone N/A ft/A

(

of 5 tubes CI None i

per SG C-2 Plug or sleeve defective tubes and inspett CI kne additional 25 tubes in C-2 Plug or sleeve deln tive l

tubes and inspect additional 45 tutres in L2 Plug ur sleeve this SG de t et t ive t utes 4

this SG y

N an

(.

3 Perform attson fue t 3 result i.f f ir st a

semple Ci rerform at t son f or C 3 N

result of ferst sample.

M/A

'A I

All ottier C-3 inspect &ll tubes in this N/A N/A

$Gs are None SG. plug or sleeve defective tubes, and C-l inspect 25 tubes in each Periera 4(tson ior ( 2 Scee SGs 3*

C - 2 tna t no result of setond sample.

N/A N'A other SG M

Notify NRC pursuant to additional SGs are 10 CIR 50.72.

C-3 g

inspett all tubes an cash N; A M_' A 3e Additional g

SG is SG and plug or sleeve 3

x O

C3 def ettive tubes. Notify MRC pursuant to 10 CIR 50.72.._

^~

w7

• tie unit and n is nuatwv

~

?

$ - M Where N is the number of steam generatois w

eri,ge tnun of steam gener ators insgw(t ed due sw; n

L; IN m.

y 1ABit 4.4-6

?'

SPEClfIC LIMITED AREA INSPECil0N 9

IST SAMPLE INSPEC110N OF A 2ND SAMPtE INSPECTION OF A Q

' SPECIFIC LIMITED AREA"

" SPECIFIC LIMITED AREA

• il Sample Size Result Action Required Result Action Required m

100% of C-1 None N/A N/A l

Area in both SGs C-2 Plug or sleeve defective

~/A N/A I

tubes.

C-3 Plug or sleeve defective N/A N/A l

tubes.

m 100% of C-1 None N/A f/A Area in one y

SG C-2 Plug or sleeve defective C-1 None I

tubes and inspect 100% of corresponding area in C-2 Plug or sleeve defective l

other SG.

tubes.

C-3 Plug or sleeve defective l

tubes.

C-3 Plug or sleeve d?fective C-1 Noae l

tubes and inspect 90% of corresponding area in C-2 Plug or sleeve detettive I

k other SG.

tubes.

tfj C-3 Plug or sleeve defective i

g tubes.

=

M

BEACTOR COOLANT SYiTB BASES system and the secondary coolant system (primary-to secondary leakage 1 GPM).

Oracks having a primary to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accideats.

Operating plants hve demonstrated that primary to secondary leakage of 1 GD" can be detected by monitoring the secondary coolant.

Leakage in excess of th s

limit will require plant shutdown and an unscheduled inspection, during which sne leaking tubes will be located and plugged.

Operational experience has shown that tube defects can be the result of unique operating conditions and/or physical arrangements in specific limited areas of the steam generators (for example, tubes adjacent to the open inspection lane or tubes whose 15th tube support plate hole is not broached but drilled). A full inspection of all of the tubes in such specific limited areas will provioe complete assurance that degraded or defective tubes in these areas are detected.

t+cause no credit is taken for these distinctive tubes in the constitution of the first sampin or its results, the requirements for the fi t sample are unchanged. This requirement is ossentially equivalent to and meets

'e intent of the requirements set forth in Regulatory Guide 1.83, " Inservice insi.:: tion of Pressurized W ter Reactor Steam Generator Tubes", Rev.1, July 1975, and does not reduce the margin of safety provided by those requirements.

Wastage type defects are unlikely with proper chemistry treatment of the secondary coolent.

However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations. Plugging or sleeving will be required for all tubes with imperfections exceeding the plugging / sleeving limit of 40% of the nominal tube or sleeve wall thickness.

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.

For examination of the sleeved steam generator tubing at the lower slceve end, the indications will be compared to those obtained during the baseline sleeved tube inspection.

Significant deviations between these indications will be considered sufficient sidence to warrant designation as a degraded tube. Defective tubes may be repaired in accordance with the B&W prncess (or method) equivslent to the method described in report BAW-2120P.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.9.1 prior to resumption of plant operation. Such cases will be considered by the Ccmmission on a case-by case basis and may result in a i

requirement for analysis, laboratory examinations, tests, additional addy-current inspection, and revision of the Technical Specifications, if necessary.

l The steam generator water level limits are consistent with the initial condition i

assumptions in the FSAR. The maximum steam generator level, as a function of steam superheat, is sufficient to assure a mass inventory of less than or equal to 62,600 lbm in the event of a main steam line rupture.

CRYSTAL RIVER - UNIT 3 8 3/4 4-3 Amendment No.33,3E,fE.136, l

1 R!tCTOR COOLANT SYSTEM EASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE'OETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant P Boundary.

Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.)

3/4.4.6.2 OPERATIONAL LEAKAG Industry experience has shown that, while a limited amount of leakage is expected from the RCS, the UNIDENTIFIED LEAKAGE portion of this can be reduced to a threshold value of less than 1 GPM.

This threshold value is sufficiently low to ensure early detection of additional leakage.

PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may There-be indicative of an impending gross failure of the pressure boundary.

fore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be j

promptly placed in COLD SHUTDOWN.

The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited L amount of leakage from known sources whose presence will not interfere with l the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

}

The CONTROLLED LEAKAGE limit of 10 GPM restricts operation with a total GPM.

RC5 leakage to,all.RC pump seals 'in excess of 10 The total steam generator tube leakage limit of l'GPM for all steam I

J generators ensures that the dosage contribution from tube letkage will be l limited to a small fraction of Part 10 limits in the event of either a steam The 1 GPM limit is consistent generator tube rupture or steam lins break.

with the assumptions used in the analysis of these accidents.

B' 3/4 4-4 CRYSTAL RIVER - UNIT 3

(

l

_ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ - - _