ML20126M834

Amend 68 to License DPR-3,revising Tech Specs to Defer Certain Inservice Insp & Testing Requirements Until End of 1981 Refueling Outage

ML20126M834
Person / Time
Site:	Yankee Rowe
Issue date:	06/08/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126M832	List: ML20126M828 ML20126M834 ML20126M838 ML20126M843
References
NUDOCS 8106220432
Download: ML20126M834 (11)

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NUCLEAR REGULATO. Y CC"".7,*i?SiON 7

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+,... s YANKEE ATOMIC ELECTRIC COMPANY DOCKET N0.50-29_

YANKEE NUCLEAR POWER STATION (YANKEE-RCWE)

AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. OPR-3 1.

The Nuclear Regulatory Comission (the Comission) has fcund that:

A.

The application for amendment by Yankee Atomic Electric Ccmpany (the licensee) dated October 22,1950,(Froposed Change No.172) complies with the standards and require-ments of the Atomic Energy Act of 1954, as ananded (the l

Act), and the Commission's rules and regulations set l

forth in 10 CFR Chapter I; 3.

The facility will ccerate in conformity with the 3 poli-cation, the provisions of the Act, and the rules and regulations of the Com lission; C.

There is reascoable assurance (i) that the activities j

authori:ed by che amendment can be conducted without endangering the health and safety of tne public d

(ii) that such activities will be conducted in compliance with the Commission's gula tions ;

l D.

The issuance of this am ndment 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 aoolicable reauirenents have been satisfied.

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Accordingly, Facility Operating License No. DPR-3 is hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendrant, paragraph 2.C.(2),

to read as follows:

Technical Soecifications (2) The Technical Specifications contained in Appendix A, as revised through Amendment No. 68, are hereby

. incorporated in the license.

The licensee shall operate the facility in accordance with the Technical,-

Specifications.

3.

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

FOR THE TJC' EAR RETJL1.T:RY C v"!S$10N

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Doerating P.aactors 3rancr.E=5 Division of Licensing At;achnent:

C'.anges to the Technical S:ecifications Date of Issuance: June 8,1981 h

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ATTACHMENT TO LICENSE AME'iD'iENT__ NO. 68 FACILITY OPERATING LICE.NSE N0. DPR-3 DOCKET NO. 50-29 Revise Appendix A Technical Specifications by removing the following pages*

and inserting the enclosed pages.

The revised pages contain the captioned amendment number and vertical lines indicating the area of change.

Remove and Insert 3/4 4-28 3/4 4-32 3/4 4-34 3/4 5-8 l

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0verleaf pages 3/4 4-27, 3/4 4-31, 3/4 4-33 and 3/4 5-7 are included for document completeness.

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h l'AIN COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 6 An initial report of any abnormal degradation of the structural integrity of the Safety Class 1 cceponents dete'cted during the above required inspections shall be made within 10 days af ter detection and the detailed report shall be submitted pursuant to Specification 6.9.4 within 90 days after completion of the surveillance requirements of this specification..-

The Inservice Inspection Program shall be reviewed every 5 years to assure that the equipcent, techniques and procedures being utilized are current and appi f cable.

The results of these reviews shall be reported in S;e:ial p.eports to the Commission pursuant to Specification 6.9.6 within 90 days of compl etio n.

b.

Insoections Following Repairs or Replacanents The structural integrity of the Main Coolant System shall be d;ronstrated after completion of all repairs and/or replacs::ents to the system by verifying the repairs and/or raplacamants maat the requirements of Section XI of the ASME Boiler ana fressure Yessel Code,1970 Edition, and Addanda thr6 ugh '.iintar,1970, except for all Class 1 piping the ultrasonic calibration sh2ll be per:

1.

Article III-2000 of Appendix III - ASME Sec XI - Suaner 1976 except that 111-2410 shall be deicted, III-2430 shall be used except 50% Feference level recording shall be performed. Ten percent overlap shall ~be retained.

2.

Article 111-3000 shall be used entirely.

f 3.

Article 111-4000 shall be used entirely.

4.

Supplement 7 shall be used for austenitic weids.

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When repairs and/or replacements are made which involve new strength welds on components greater than 2 inch diameter, the new welds shall r?ceive a surface and 100 perc2nt volumatric When examination and meet applicable code requirements.

repairs and/or replacements.are made 'which involve new strength welds on components 2 inch diameter or smaller, the new welds shall re:eive a surface examination and meet applicable code r equi r emen ts.

YANKEE-ROWE 3/4 4-27 Amendment No. 42 4

AUG 19 577

i SIN COOLA. T SYSTEM N

i SURVEII.1.ANCE REOUIREMENTS (Continued)

Insoections Following System Ooening The s tructural integrity of the Main Coolan System shall be demons:rs:ed af ter each closing by performing a leak test, with the system pressurized to at least 2200 psig, in accordance with Section XI of the ASME Boiler and Pressure l

Vessel Code, 1970 Edition, and Addenda through ~4 inter 1970, and the Pressure / Temperature limits of Specification 3.4.8.1-l 4.4. 9. 2* The following inspec: ion program shall be per formed at least once per 13 months during shutdown on at least one shroud tube per quadrant.

a.

Inspect the integrity of the bolts and locking devi:ei in the lower flange at the bottom of the shroud :ubes.

b.

Inspect the interf ace between the shroud tube lower flange and the d

e p. ate. eor separa: ion.

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c.

Inspect the interface between the shroud tube upper flange 2nd the l

op shroud tube support pla:e for separa: ion.

6 d.

Inspect the interf ace be:veen the top shroud tube support place and the lower core support plate for separation.

Il e.

Inspect for abnormalities one of each of :he :ypes of bolts per

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1.4.9.3x The pressurizer interior shall be inspec: 2d at least once ser 13 f

.. :n hs durin; shutdown using the best available :echniques to de termine if 2ny d :hange has occurred in the cladding ::acks that exist and whether any further 0 : racking of the cladding has taken place.

4.L.9.4 The 2" charging line be: ween CH-MOV-524 and CH-illa shall be dye penetrant tested at least once per 13 =onths during shutdewn.

xThe intent of the 13 month surveillance requirements for Sections 4.4.9.2 and 4.4.9.3 is that these surveillan:es would be performed on a refueling basis.

For this reason, as well as ALARA considerations, the surveillance

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a 3/4 4-31 YAN KE E -RCWE

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• N COOLANT SYS~EM STEAM OENERATORS ILIMIT!NG CONDITION FCR OPERATION 3.4.10 Each steam generator in a non-isolated main coolant loop shall be OPE RA3LE.

. A??LIC A3ILI TY : MCDES 1, 2, 3 and 4.

ACTION:

With one or more steam generators in non-isolated main coolant, loops inoperable, restore the inoperable generator (s) to OPERA 3LE status prior to increasing t about 2000F.

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.SCRVEILLANCE 150U REMENTS 5

f 4.4.10.1*

Steam Generator Sample Selection and Inspection - Iach steam

,3enerator shall be determined 0FERA3LE during shu:down by sale: tin; and linspecting at least the minimum number,of staam generators specified in Table 4.L-4.

q4.4.10.2 Steam Oenerator Samole Sele::icn and Inspection - The steam hgenerator tube minimum sample size, inspection rasult claasifica:ian acd the corrasponding action required shall be as specified in Table '.4-5.

4 The oinservice inspec: ion of steam generator tubes sh all be per f ormed at the hfrequencies specified in Specificatian 4.4.10.3 and the inspac:ed tubes shall dbe verified acceptable per the acceptance criteria of Specification 4.L.10. A.

tubes selected for each inservice inspection shall include at least 3% of i

jThe the t ot al number of tubes in all s: cam generators; the tubes selected for i these inspections shall be selected on a random basis except:

Where experience in similar plants with similar water chemistry a.

I indicates critical areas to be inspected, then at least 50% of the rubas inspected shall be frem these cri:ical aress, b.

The first sample of tubes selected for each inservice inspection of each steam generator shall include:

1.

All nonplugged tubes that previously had detectable wall penetra: ions ( 20%).

O.

Tubes in those areas where experience its indi:2:ed potential t

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!WThe intent of the 13 month surveillance recuirement for Section 4.4.10.1 is n

tha: this surveillance veuld be perf ormed on a refueling basis.

For this as ell as ALARA c:nsider a tions, the su r/eil".ad:e requirement af h, r e a s o n,aections a.a.10.1 may be deferrec pastne 13 cntn lini: until ne Pend of the 1931 refueling outage, but no later than July 31, 1931.

I YAtiKEE-ROWE 3/4 4-32 Amendment No. 54, 68

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MA:N COCLANT SYSTD4 SURVEILLANCE RE0VIREMENTS (Continued.

3.

A tube inspecticn (pursuant to Specificatien 4.4.10.d.a.8) shall be performed on eacn selected tube.

If any selec ted tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c.

The tubes selected as the second and third samples (if recuired by Table 4.4-5) during each inservice inspection ray be subjected to a partial tube inspectico 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 fcund.

2.

The inspections include those pcrtions of the tubes whare imperfectiers were previcusly found.

The results of each s2mple insp3cticn shall be classified into cre of. the folicwing three categories:

c Categcry insceeticn Oesults I

C -1 Less than 5% of the total tubes inspected are dagraded tubes and ncne of the inspected tubes are defective.

C-2 Cne 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.

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l C-3 More than 10% of the total tubes l

inspected are degraded tubes or more tnan 1% of the inspected tubes are defective.

Note:

In all inspections, previously degraded tubes mus:

l exhibit significant (>1C%) further wall penetraticns I

to be included in the abcve percentage calculaticns.

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YANKEE-RCWE 3/4 4-33 Amendment No. 34

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5URVEILLANCE REQUIREMENTS (Continued) j t

l 4.4.10.3*

Insoection Frecuencies - The above required inservi:e inspe::icns l

- of stems generator tubes shall be performed at the following frequencies :

Inservice inspections shall be performed at intervals of not less a.

than 12 nor more than 24 calendar months af ter the previous inspec: ion.

If two consecutive inspections result in,all inspection

'results f alling into the C-1 category of if two consecutive inspec:icns demonstrate that previously observed degraded has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 conths.

5.

If the results of the inservice inspection of a sterm enerator co'nducted in accordance with Table 4.4-5 at 40 =onth intervals fall in Category C-3, the inspec: ion f requency shall be increased to at l

1eas: once per 20 conths.

The increase in inspection frequency l

shall 2pply until the subsequen: inspections sa:isfy the cri:eria of Specification 4.4.10.3.a; the intarval cay then be extended to a maximum of once per 40 months.

Additional, unscheduled insaryice inspecti na shall be performed an i

c.

each steam generator in accarilance wi:h the first sa:ple inspection specified in Table 4.4-5 during the shutdown. subsequent to any of the :. l. wing conditions:

a o 1.

?rizary-to-secondary :ubes leaks (not ine'.uding I33.s

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1 origi na tin g from tube-::-tube sheet welds) in ex:ess of the limits of Specification 3.4.5.2.

2.

A loss-of-coolant a cc iden t requiring actua:_ n of the engineered safeguards.

I 3.

A main steam line or feedwater line be sak.

h"The in:2n: o f :ne surveillance r equire e n: fsr Se:: ion 1.i.10.2 is :. a: thia i

surveillan:e would be perf ormed on a re fueling basis.

For this raas:n, as well as ALARA considerations, the surveillance require =ent of sections l

j 4.4.10.3 may oe deferred past the 18 month limit until the end of the g

l 1981 refueling outage, but no later than July 31, 1981.

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3/4 ;-24 A:endmen:

YASKII-RCWE 1

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-EMER3ENCY CORE CCOLING SYSTEMS

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. SURVEILLANCE REOUIREMENTS (Continued) 9.

Verifying that the charging header ficw metering in-l strument is CPEPJ5LE by observing charging f1:w rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

By a visual inspection which verifies that no loose debris-c.

(regs, trash, clothing, etc.) is present in the. containment which cculd ~be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1.

For all accessible areas of the c:ntair, ment prior to '

establishing containment integrity, and

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2.

Of the areas affected within containment at the ::mple-tien of each containment entry when containment integrity is es tablished.

d.

At least ence per 18 months by visual ins:ection of the c:n-tainment suco :nd verifying that the subsystem suction inlats are not restricted by debris and that tha sump c:mp:ncnts (trash ra:ks, screens, etc.) sn:w no avidence of structural distress or corrosion, At least once per 18 months, during shutdcwn, by:

e.

1.

Cycling each pcwer ccerated (excluding automatic) valve in the flow path through at least one complete cycie of l

full' travel.

2.

Verifying that valve CS-MOV-532 actuates to its correct position on a safety injection signal.

-3.

Verifying that each of the folicwing pumps start aut -

matica11y upon receipt of a safe,ty injection signal:

l (a) M'gh oressure sif tty injaction (HPSI) pump (b,) L:w pressure sar aty in;a::i:n s _ra.,

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E.#E ROENCY CORE COOLING SY3TEMS SURVIILLANCE REOUIREMEN'S (Continued) low pressure safecy injec: ion pumps develop l

4.*

Verifying that two a :embined flew 2130 ;pm. Test every LPSI pump at least once per 36 conths.

5.

Verifying that each charging pump stops auto =a:ically upon recetpt or a sarety injec:lon signal.

6.

Verifying that the charging header flow metering instrument is 0? ERA 3LE by performing a CHA.tiEL CALI3 RATION.

7.

Verifying that each valve listed in Specificatio,n 4.5.2.b.3 is in its normal,y open position.

Verifying the proper positioning of the HPSI throttle valves 3.

SI-V-671, 672, 673, and 674 by per forming an inspec: Con to insure tha::

a)

Each valve locking device is in place and securely welded to the v alve h andle 2nd to the v alve.roke.

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The scribe mark on each valve body aligns vi:h :he scribe b)

I mark on the valve yoke.

.eg in;act;;n :.nr;;:.2 9.

Vert:ytag tne proper posicion ng o:..act s

talve 31-V-5S5 2: lias on:e per 36 cen:hi by ficw t as ting.'

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A: leas: every 36 months, and/: any ti=e either tes: under 4.5.e.3 I

is f ailed, by developing a backpressure of 375 psi; in the high safety injectica header with two 3?SI pu=ps cper2:ing 23 l

pressure follows:

1.

Prassure to the succion of the H?S: pumps :o be 170; 10 psi.

2.

L?SI flew is isola:ed.

Injection flow is to one loop with the other loops isolated by 3.

closing the appropriate injection gate valves CS-McV-536, CS-MCW-537, CS-MOV-538, and CS-MOV-539.

4.

The flow to the injection loops shall not be less than 200 gpm.

shall be rapeated to include the operation of 5.

The above test

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i h # he intent of :ne sur/elllan:e require =en: for 3ee: ion 4.5.2.:.a is that this i

For :his reason, as 4 surf eillance would be performed on a re fueling basis.

' veil as ALARA ::nside r a:icas, the surreillance require:ent of sec: ion

ne end of l

j a.5.2.a.a may se deferred cast the 15 *cnth limit untii d,the 1951 re#aeling outace, ut no later than Jui.v 31, '931.

D YA.KEE-RCWE 3/4 5-8 1

Amendment :;o. J8, M, J?,,54',

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